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1.1. |
Medical uses of ionizing radiation are among the longest established applications of ionizing radiation. In 2008, the estimated worldwide annual number of diagnostic and interventional radiological procedures (including dental) was 3.6 billion, the estimated number of nuclear medicine procedures was over 30 million, and the estimated number of radiation therapy procedures was over 5 million [1]. The number of such procedures has continued to increase since then. These medical uses bring considerable public health benefits. |
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1.2. |
However, ionizing radiation can cause harm and a systematic approach should be applied to ensure that there is a balance between utilizing the benefits from medical uses of ionizing radiation and minimizing the risk of radiation effects to patients, workers and members of the public. |
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1.3. |
Medical uses of ionizing radiation have a place only in the context of medical practice. The system for ensuring radiation protection and safety should form part of the larger system for ensuring good medical practice. This Safety Guide focuses on the system of radiation protection and safety. |
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1.4. |
IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles [2], presents the fundamental safety objective and principles of protection and safety. Requirements designed to meet this objective and these principles are established in IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards [3]. |
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1.5. |
This Safety Guide provides guidance on fulfilling the requirements of GSR Part 3 [3] with respect to medical uses of ionizing radiation. |
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1.6. |
The International Commission on Radiological Protection (ICRP) has developed recommendations for a system of radiation protection [4]. These and other current recommendations of the ICRP and the International Commission on Radiation Units and Measurements (ICRU) have been taken into account in preparing this Safety Guide. |
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1.7. |
It is assumed in this Safety Guide that the individual State has in place an effective governmental, legal and regulatory infrastructure for radiation protection and safety that covers medical uses of ionizing radiation. |
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1.8. |
This Safety Guide supersedes IAEA Safety Standards Series No. RS-G-1.5, Radiological Protection for Medical Exposure to Ionizing Radiation, issued in 2002, and several Safety Reports issued by the IAEA in 2005 and 2006. |
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1.9. |
Unless otherwise stated, terms in this publication are to be understood as defined and explained in GSR Part 3 [3] or the IAEA Safety Glossary [5]. |
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1.10. |
GSR Part 3 [3] establishes requirements for the protection of people from harmful effects of exposure to ionizing radiation, for the safety of radiation sources and for the protection of the environment. This Safety Guide recommends how medical uses of ionizing radiation should be carried out safely within the framework of GSR Part 3 [3]. |
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1.11. |
The purpose of this publication is to provide recommendations and guidance on meeting the requirements for the safe use of radiation in medicine as established in GSR Part 3 [3], and these publications should be used together. This Safety Guide is aimed primarily at end-users in medical radiation facilities in which radiological procedures are performed, including managers, radiological medical practitioners, medical radiation technologists, medical physicists, radiation protection officers (RPOs) and other health professionals. It also provides recommendations and guidance to: health professionals who refer patients for radiological procedures; manufacturers and suppliers of medical radiological equipment; and ethics committees with responsibilities for biomedical research. National requirements may vary, being stricter in some States; the related national regulations and guidelines should be known and followed. |
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1.12. |
This publication provides recommendations and guidance on appropriate regulatory activities and infrastructure, and is therefore also applicable to regulatory bodies, health authorities, government agencies in general and professional bodies. |
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1.13. |
This Safety Guide provides recommendations for ensuring radiation protection and safety of radiation sources with regard to patients, workers, carers and comforters, volunteers in biomedical research and the public in medical uses of ionizing radiation. It covers radiological procedures in diagnostic radiology (including dentistry), image guided interventional procedures, nuclear medicine and radiation therapy. Some of these radiological procedures may be carried out in other medical specialties, including, but not limited to, cardiology, vascular surgery, urology, orthopaedic surgery, gastroenterology, obstetrics and gynaecology, emergency medicine, anaesthetics and pain management. |
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1.14. |
Depending on the laws and regulations in the State, medical uses of ionizing radiation may include the use of ionizing radiation in other health care practices, such as chiropractic, osteopathy and podiatry. These uses are also within the scope of this Safety Guide. |
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1.15. |
This Safety Guide does not include recommendations or guidance on human imaging using ionizing radiation for purposes other than medical diagnosis, medical treatment or biomedical research. Such human imaging using ionizing radiation for other purposes includes exposing people to radiation for employment related, legal or health insurance purposes without reference to clinical indications, and human imaging using ionizing radiation for the detection of concealed objects for anti-smuggling purposes or for the detection of concealed objects that could be used for criminal acts that pose a national security threat. |
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1.16. |
Following this introductory section, Section 2 provides general recommendations for radiation protection and safety in medical uses of ionizing radiation. This includes: the application of the principles of protection and safety; the use of the graded approach; roles and responsibilities; education, training, qualification and competence; management systems for protection and safety; and safety assessments. |
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1.17. |
Sections 3–5 provide recommendations for specific areas of medical uses of ionizing radiation: Section 3 covers diagnostic radiology and image guided interventional procedures; Section 4 covers nuclear medicine; and Section 5 covers radiation therapy. Guidance for hybrid modalities is addressed in the relevant sections, as appropriate. |
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1.18. |
Appendix I provides summary guidance on typical causes of, and contributing factors to, accidental exposure in medical uses of radiation. Appendices II and III provide recommendations on the avoidance of pregnancy following radiopharmaceutical therapy and on the cessation of breast-feeding following administration of radiopharmaceuticals for nuclear medicine, respectively. |
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1.19. |
It is important to note that the sections on specific areas (Sections 3–5) should always be read in conjunction with Section 2. In addition, each section should be considered in its entirety. |
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2.1. |
Medical uses of ionizing radiation take place in a variety of settings, including hospitals, medical centres, health clinics, specialist clinics, and dental practices. A medical radiation facility is the term used in GSR Part 3 [3] to cover all such possible settings. A medical radiation facility may provide services for one or more medical uses of radiation. For example, a large hospital typically has facilities for diagnostic radiology, image guided interventional procedures, nuclear medicine and radiation therapy. The authorization process for medical uses of ionizing radiation varies from State to State. In some States, a single authorization may cover all specialties and activities within the facility, whereas others may authorize each specialty or application separately. For example, in one State a hospital may have a single authorization covering all of diagnostic radiology, image guided interventional procedures, nuclear medicine and radiation therapy, whereas in another State each of these areas or applications may be authorized separately. Despite such differences in authorization, the guidance in this Safety Guide remains applicable. |
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2.2. |
Traditionally, each of the areas of diagnostic radiology, nuclear medicine and radiation therapy were separate, with little or no combined usage. This has changed, with hybrid imaging systems involving both diagnostic radiology and nuclear medicine expertise, and with the planning, guidance and verification stages of radiation therapy increasingly involving both imaging and radiation therapy expertise. Within this Safety Guide, cross-references are provided where appropriate when such systems are addressed. |
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2.3. |
As stated in paras 1.13 and 1.14, the setting for this Safety Guide is the practice of medicine (including dentistry, chiropractic, osteopathy and podiatry). The requirements of GSR Part 3 [3] for radiation protection and safety of radiation sources apply to the uses of radiation in medicine as for elsewhere. The requirements should be met and included within medical structures and processes and in medical guidelines, with the objective of improved patient care and patient outcomes. |
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2.4. |
The requirements of GSR Part 3 [3] are structured according to the three types of exposure situation: planned exposure situations, existing exposure situations and emergency exposure situations. Medical uses of ionizing radiation are a planned exposure situation and the requirements of sections 2 and 3 of GSR Part 3 [3] apply, as appropriate. This includes situations of potential exposure, which is defined in para. 1.20(a) of GSR Part 3 [3] as an exposure that “is not expected to occur with certainty, but could result from an accident or from an event or a sequence of events that may occur but is not certain to occur”. Potential exposure can be applicable for any occupational, public and medical exposure where the event, if it occurs, results in an exposure over and above what would be expected normally. Unintended and accidental medical exposures should be treated as planned exposure situations (para. 3.145 of GSR Part 3 [3], see Table 1). Sections 2–5 of this Safety Guide cover the prevention and mitigation of the consequences of events leading to a potential exposure. In extreme situations in medical facilities of emergency preparedness category III [7] (such as a radiation therapy facility), an emergency exposure situation may occur that affects either workers or members of the public. For preparedness and response for emergency exposure situations, the applicable requirements include section 4 of GSR Part 3 [3] and IAEA Safety Standards Series Nos GSR Part 7 [7], GSG-2 [8] and GS-G-2.1 [9]. |
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2.5. |
Medical uses of ionizing radiation involve all three categories of exposure: occupational exposure for those involved in the performance of radiological procedures; medical exposure, primarily for the patients undergoing the radiological procedures, but also for carers and comforters and for volunteers subject to exposure as part of a programme of medical research; and public exposure for members of the public, such as in waiting rooms. The requirements for radiation protection and safety differ according to the category of exposure, so it is important that the exposure of persons is categorized correctly. For example, a nurse assisting with image guided interventional procedures would be considered to be occupationally exposed. A nurse working on an inpatient ward where occasional mobile radiography is performed by a medical radiation technologist would also be considered to be occupationally exposed; however, because in this case the radiation source is not required by or directly related to the work, this nurse should be provided with the same level of protection as members of the public (see para. 3.78 of GSR Part 3 [3]). The term ‘carer and comforter’ is defined in GSR Part 3 [3] as: “Persons who willingly and voluntarily help (other than in their occupation) in the care, support and comfort of patients undergoing radiological procedures for medical diagnosis or medical treatment.” Carers and comforters are subject to medical exposure, whereas a casual acquaintance visiting a patient who has undergone radionuclide therapy would be considered a member of the public and hence subject to public exposure. More extensive guidance is provided in each of the specialty Sections 3–5 of this Safety Guide. |
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2.6. |
Unintended and accidental medical exposures are covered in detail in Sections 3–5. Such events include any medical treatment or diagnostic procedure in which the wrong individual is exposed. |
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2.7. |
The three general principles of radiation protection, namely justification, optimization of protection and safety, and the application of dose limits, are expressed in Principles 4–6 and 10 of the Fundamental Safety Principles [2]. In terms of Requirement 1 of GSR Part 3 [3], those responsible for protection and safety are required to ensure that the relevant requirements applying these principles are met. |
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2.8. |
Medical exposure differs from occupational and public exposure in that persons (primarily patients) are deliberately, directly and knowingly exposed to radiation for their benefit. In medical exposure, applying a dose limit is inappropriate, as it may limit the benefit for the patient; consequently, only two of the radiation protection principles apply — justification and optimization. Justification plays the role of gatekeeper, as it will determine whether or not the exposure will take place. If it is to take place, the radiological procedure should be performed in such a way that radiation protection and safety is optimized. |
| Justification |
2.9. |
Justification in medical uses of ionizing radiation involves consideration of all three categories of exposure: medical exposure, occupational exposure and public exposure. |
| Justification |
2.10. |
From an occupational exposure and public exposure perspective, the practice should be justified. This aspect of justification is the process of determining whether the use of the given radiological procedure is expected to yield benefits to the individuals who undergo the procedure and to society that outweigh the harm (including radiation detriment) resulting from the procedure. In almost all cases, the occupational exposure and public exposure considerations in justification are overshadowed by the justification of medical exposure (see para. 2.11). While a medical radiological procedure is expected to do more good than harm to the patient, account should also be taken of the radiation detriment from the exposure of the staff of the medical radiation facility and of other individuals. |
| Justification |
2.11. |
The application of the justification principle to medical exposure requires a special approach, using three levels (the three-level approach). As an overarching justification of medical exposure, it is accepted that the proper use of radiation in medicine does more good than harm (level 1). At the next level (level 2), generic justification of a given radiological procedure should be carried out by the health authority in conjunction with appropriate professional bodies. This applies to the justification of current technologies and techniques and new technologies and techniques as they evolve. The decisions should be reviewed from time to time, as more information becomes available about the risks and effectiveness of the existing procedure and about new procedures. Those radiological procedures that are no longer justified should be removed from medical practice. The possibility of accidental or unintended exposure should also be considered at level 2. For the final level of justification (level 3), the application of the radiological procedure to a given individual patient should be considered. The specific objectives of the exposure, the clinical circumstances and the characteristics of the individual involved should be taken into account. National or international referral guidelines, developed by professional bodies together with health authorities, are required to be used (para. 3.158 of GSR Part 3 [3]). The approach to the implementation of justification of a procedure for an individual patient (level 3) depends on whether it is a diagnostic procedure, an image guided intervention, or a treatment. Specific guidance on justification in each specialty is given in Sections 3–5. |
| Justification |
2.12. |
The level 3 justification of medical exposure for an individual patient does not include considerations of occupational exposure. If the proposed radiological procedure is justified for that patient, then the participation of particular staff in performing the procedure is governed by the requirements for optimization of occupational radiation protection and safety and limitation of occupational dose. |
| Optimization of protection and safety |
2.13. |
The optimization of protection and safety, when applied to the exposure of workers and of members of the public, and of carers and comforters of patients undergoing radiological procedures, is a process for ensuring that the magnitude and likelihood of exposures and the number of individuals exposed are as low as reasonably achievable, with economic, societal and environmental factors taken into account. This means that the level of protection and safety would be the best possible under the prevailing circumstances. |
| Optimization of protection and safety |
2.14. |
As is the case with justification, the application of the requirements for optimization to the medical exposure of patients and to the medical exposure of volunteers as part of a programme of biomedical research requires a special approach. Too low a radiation dose could be as bad as too high a radiation dose, in that the consequence could be that a cancer is not cured or the images taken are not of suitable diagnostic quality. The medical exposure should always lead to the required clinical outcome.
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| Optimization of protection and safety |
2.15. |
Optimization is a prospective and iterative process that requires judgements to be made using both qualitative and quantitative information. Specialty specific guidance on optimization of medical, occupational and public radiation protection and safety is given in Sections 3–5. |
| Optimization of protection and safety |
2.16. |
Dose constraints are used in the planning stage in the optimization of protection and safety. Dose constraints are applicable for occupational exposure and for public exposure in medical uses of ionizing radiation. Dose constraints are also used in the optimization of protection and safety for carers and comforters and for volunteers subject to exposure as part of a programme of biomedical research. Dose constraints are not applicable for the exposure of patients in radiological procedures for the purposes of medical diagnosis or treatment (see also paras 2.46–2.50). |
| Optimization of protection and safety |
2.17. |
One of the purposes of establishing a dose constraint for each particular source of radiation exposure is to ensure that the sum of doses from planned operations for all sources under control remains within the dose limits. Dose constraints are not dose limits; exceeding a dose constraint does not represent non-compliance with regulatory requirements, but it might result in follow-up actions. |
| Optimization of protection and safety |
2.18. |
In X ray medical imaging, image guided interventional procedures and diagnostic nuclear medicine, diagnostic reference levels (DRLs) are a tool used in the optimization of protection and safety. Periodic assessments are required to be performed of typical patient doses or, for radiopharmaceuticals, of activities administered in a medical radiation facility (para. 3.169 of GSR Part 3 [3]). Doses in this context may be expressed in one of the accepted dosimetric quantities as described in para. 2.40 [10–12]. For simplicity, the term ‘dose’ in Sections 3 and 4 will be used when referring generally to measurements of medical exposure in radiological imaging, with specific forms of dose or activity used where necessary. |
| Optimization of protection and safety |
2.19. |
If comparison with established DRLs shows that the typical doses or activities to patients are either unusually high or unusually low, a local review is required to be initiated to ascertain whether protection and safety has been optimized and whether any corrective action is required. DRLs are not dose limits (see also paras 2.34–2.45). |
| Optimization of protection and safety |
2.20. |
Other tools used in the optimization of protection and safety applied to all three categories of exposure include, inter alia, design and operational considerations and programmes of quality assurance. These are described in detail in the specialty Sections 3–5. |
| Dose limits |
2.21. |
Dose limits apply to occupational exposure and public exposure arising from any use of ionizing radiation. Schedule III of GSR Part 3 [3] sets out these dose limits, which are reproduced here for convenience (see Box 1). Dose limits do not apply to medical exposure (i.e. exposure of patients, carers or comforters, and volunteers as part of a programme of biomedical research). |
| Dose limits |
2.22. |
The occupational dose limit for the lens of the eye is lower in GSR Part 3 [3] than previously recommended. There are some areas of medical uses of ionizing radiation, such as image guided interventional procedures, where, if good radiation protection practice is not being followed, there is a possibility of exceeding this dose limit. Specific guidance is given in Sections 3–5. |
| Dose limits |
2.23. |
The graded approach is a concept that underpins the application of the system for protection and safety. Paragraph 2.12 of GSR Part 3 [3] states: “The application of the requirements for the system of protection and safety shall be commensurate with the radiation risks associated with the exposure situation.” |
| Dose limits |
2.24. |
The risks associated with medical uses of ionizing radiation vary significantly, depending strongly on the particular radiological procedure. At the low risk end are dental exposures (excluding cone beam computed tomography, CBCT), and dedicated bone densitometry studies (dual energy X ray absorptiometry, DXA). At the high risk end is radiation therapy, where the doses involved could be lethal, and image guided interventional procedures, where radiation injuries can occur. |
| Dose limits |
2.25. |
GSR Part 3 [3] places responsibilities for a graded approach on the government, the regulatory body, registrants and licensees, and employers. The government and the regulatory body are required to use a graded approach in setting and enforcing regulatory requirements. For example, it would be expected that regulatory bodies devote fewer resources and less time to regulating dental practices than to regulating the use of radiation in radiation therapy or image guided interventional procedures. |
| Dose limits |
2.26. |
The registrants, or licensees, and employers are required to use a graded approach in the measures they take for protection and safety. For example, the registrant or licensee of a dental practice would not need to implement a quality assurance programme that is as comprehensive as the programme implemented for a radiation therapy facility in order to meet the requirements of GSR Part 3 [3]. |
| Dose limits |
2.27. |
Guidance incorporating the graded approach is given in the specific guidance for each specialty and for the various modalities within those specialties (see Sections 3–5). |
| General |
2.28. |
The roles and responsibilities of the government with regard to protection and safety are established in Requirement 2 and paras 2.13–2.28 of GSR Part 3 [3], with further detailed requirements established in IAEA Safety Standards Series No. GSR Part 1 (Rev. 1), Governmental, Legal and Regulatory Framework for Safety [13]. These include: Establishing an effective legal and regulatory framework for protection and safety in all exposure situations.
Establishing legislation that meets specified requirements.
Establishing an independent regulatory body with the necessary legal authority, competence and resources.
Establishing requirements for education and training in protection and safety.
Ensuring that arrangements are in place for:
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| General |
2.29. |
As noted in para. 1.7, this Safety Guide assumes that an effective governmental, legal and regulatory infrastructure for radiation protection and safety is in place. However, there are some additional considerations that are important for ensuring radiation protection and safety in medical uses of ionizing radiation. |
| General |
2.30 |
The government has a responsibility to facilitate and ensure that the health authority, the relevant professional bodies and the radiation protection regulatory body communicate and cooperate in working towards establishing the infrastructure necessary for radiation protection and safety in medical uses of ionizing radiation. The role of the health authority typically includes determining policy, which in turn may dictate the resources allocated to the various areas of health care, including medical uses of ionizing radiation. Up to date information on developments in medical uses of ionizing radiation, and how that might shape and influence medical practice, should be available so that appropriate policy can be developed and implemented. The professional bodies of the various health professionals associated with radiation in health care represent the collective expertise of the given health profession and, as such, can strongly influence the practice of radiation protection and safety. The health authority and the professional bodies should be active working partners with the radiation protection regulatory body in achieving effective regulation of medical uses of ionizing radiation (see paras 2.52–2.69 for more guidance on the health authority and professional bodies). |
| General |
2.31. |
Mechanisms for formal recognition of health professionals should be put in place to ensure that only persons with the appropriate competencies are allowed to take on particular roles and responsibilities. In medical uses of ionizing radiation, this applies in particular to persons undertaking the role of radiological medical practitioner, medical radiation technologist or medical physicist. Detailed guidance is provided in paras 2.119–2.137, on education, training, qualifications and competence. |
| General |
2.32. |
Other organizations can make a worthwhile contribution to radiation protection and safety in medical uses of ionizing radiation. These include technical standards associations, regulatory bodies for medical devices and health technology assessment agencies that issue standards and reports that could have direct implications for radiation protection and safety. Not all States have such organizations but, where they exist, the government should ensure that they interact cooperatively with the radiation protection regulatory body, the health authority and the relevant professional bodies. In States that do not have such organizations, the government should consider means to adopt or adapt relevant standards or reports from such organizations in other States. |
| General |
2.33. |
Other organizations can have an indirect, but not necessarily insignificant, effect on radiation protection and safety in medical uses of ionizing radiation. Such organizations include health insurance or re-imbursement companies and standards accreditation bodies. The former, by deciding on what radiological procedures (and other alternative techniques) are covered, and the latter, by including radiation protection and safety in its scope, can positively influence how well radiation protection and safety is being implemented in medical facilities seeking accreditation. Again, the government should be aware of these organizations and should utilize their influence to improve the practice of radiation protection and safety in medical uses of ionizing radiation. |
| Diagnostic reference levels |
2.34. |
DRLs are an important tool and should be used for optimization of protection and safety for diagnostic medical exposure (see para. 2.18). The government has a particular responsibility to ensure that DRLs are established for the State. DRLs can also be established for a region within the State or, in some cases, regions of several small States. In establishing values for the DRLs, typical (e.g. median or average) doses for patients are obtained from a representative sample of rooms and facilities where these procedures are being performed. In this way, a snap shot of current practice in the State or region is obtained, reflecting both good and poor practices, for that particular imaging procedure. The value of the DRL for that particular procedure is typically the rounded 75th percentile of the distribution of typical doses for the room or facility [14–17]. In establishing DRLs, it is important to include only radiological procedures whose image quality is adequate for the medical purpose (for further guidelines, see para. 3.215 for diagnostic and interventional radiology and para. 4.207 for nuclear medicine). |
| Diagnostic reference levels |
2.35. |
Once DRLs have been established, medical radiation facilities should compare their typical doses (sometimes called facility reference levels or local reference levels) with the relevant DRLs, as described in Sections 3 and 4. The use of the median value rather than the average value of the distribution of data collected from a representative sample of standard sized patients should be preferred for comparison with DRLs, as the average value could be substantially affected by a few high or low values (see also Ref. [14]). Optimization of protection and safety for a particular radiological procedure should be reviewed if the comparison shows that the facility’s typical dose exceeds the DRL, or that the facility’s typical dose is substantially below the DRL and it is evident that the exposures are not producing images of diagnostic usefulness or are not yielding the expected medical benefit to the patient. The resulting actions aimed at improving optimization of protection and safety will usually, but not necessarily, result in lower facility typical doses for the procedure or procedures. At some predetermined interval, typically three to five years, there should be a review of the established national or regional DRL values. More frequent surveys may be necessary when substantial changes in technology, new imaging protocols or image post-processing become available. A new national or regional survey will result in a new distribution of facility typical doses, which will reflect the improvements made as a result of using the existing DRLs. After initial evaluations, it is likely that the new values of the DRLs will be lower than the previous values. This cycle of establishment of national or regional DRLs, their use by imaging facilities, corrective actions by imaging facilities, and periodic review of national or regional DRLs brings about a steady improvement in the optimization of protection and safety across the State or region. After several cycles, it would be expected that the value of the DRL would stabilize. However, a DRL may increase if there is a major change in technologies or techniques in which the relationship between the diagnostic content of the image and the dose changes. |
| Diagnostic reference levels |
2.36 |
There are several steps to the establishment of DRLs. At the national or regional level, decisions should be made whether to use actual patients or phantoms to represent a ‘standard patient’ for each modality. Whenever possible, DRLs should be established on the basis of surveys of procedures performed on an appropriate sample of patients. The use of phantoms avoids most of the issues with variations in patient size indices (e.g. mass, height and body mass index) (see paras 2.39 and 2.41). However, their use does not truly represent clinical practice with patients and clinical images and, as such, it would seem less appropriate for use in establishing DRLs. Nevertheless, a phantom based approach, in the absence of adequate patient data, can be used first to establish DRLs and then later in their application [14, 17]. |
| Diagnostic reference levels |
2.37. |
The imaging procedures for which DRLs are to be established should be decided upon at a national or regional level. The criteria that may help in this decision are the relative frequencies of the imaging procedures and the magnitude of the doses incurred. A graded approach may be used to select procedures for which DRLs are to be established for adults and children — the more frequent and higher dose procedures should have a higher priority. Specific consideration should be given to paediatric imaging. Depending on national or regional resources, the actual number of procedures for which DRLs are established will vary [18]. It is beneficial if the health authority and professional bodies adopt a common terminology for procedures. |
| Diagnostic reference levels |
2.38. |
Another consideration with DRLs is whether the procedure is simply defined in terms of the anatomical region being imaged or whether there should be a further refinement to include the clinical purpose of the examination (e.g. indication based protocols). For example, a CT of the abdomen may be performed differently depending on the diagnostic purpose. For those embarking on establishing DRLs for the first time, it is advisable to define the procedure simply in terms of the anatomical region being imaged. |
| Diagnostic reference levels |
2.39. |
The next step is to perform, for the selected procedures, a representative survey — preferably widespread in terms of the types and sizes of facility (rural, urban, private and public), the equipment and the geographical locations. Most imaging radiological procedures are performed on adults, and traditionally national DRLs have been established first for adults. For each room or facility in which the given procedure is performed, the sample size depends on the frequency of the imaging procedure and variability in patient doses, but clearly a larger sample size will reduce the statistical uncertainties (for further guidelines, see para. 3.213 for diagnostic and interventional radiology and para. 4.205 for nuclear medicine). Not all adults are the same size, so many States have established DRLs for a standard adult patient, limiting patient eligibility to the sample on the basis of mass, for example 70 ± 20 kg, and aiming for a sample average in a given mass range, for example 70 ± 5 kg (see Refs [14–16]). Other States have adopted a more pragmatic approach, accepting all adults in the initial sample but excluding extreme outliers in terms of patient size indices. |
| Diagnostic reference levels |
2.40. |
The dose metrics used to represent the dose to the patient should be easily measurable and should be in accordance with the recommendations of the ICRU, as established in para. 1.46 of GSR Part 3 [3]. The following are commonly used terms for diagnostic and interventional radiology [10, 11]:In radiography: air kerma–area product, incident air kerma or entrance surface air kerma (which includes backscatter).
In fluoroscopy: air kerma–area product.
In CT: CT air kerma index and CT air kerma–length product.
In mammography and tomosynthesis: incident air kerma or entrance surface air kerma and mean glandular dose.
In dentistry: incident air kerma for intraoral radiography and air kerma–area product for panoramic radiography and CBCT.
In image guided interventional procedures: air kerma–area product and cumulative reference air kerma at the patient entrance reference point.
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| Diagnostic reference levels |
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Further guidance on dose metrics is given in paras 3.202–3.204. It is crucial that the dose data for each contributing facility is only collected for procedures where the image quality was confirmed as adequate for the clinical purpose. In nuclear medicine, DRLs are set in activity administered to the patient and in activity per unit of body mass (MBq/kg) (see paras 4.205 and 4.206). |
| Diagnostic reference levels |
2.41. |
Optimizing protection and safety for average adult patients does not necessarily mean that optimization is being achieved for other size or age groups. Experience, in particular with children undergoing CT examinations, has clearly demonstrated that this is not the case [19]. This means that consideration should also be given to establishing DRLs for children undergoing imaging procedures. The same problem of size and mass, as stated in para. 2.39, also pertains to children. Patient age has been used to define groups of children for the purpose of establishing paediatric DRLs. Some States or regions have adopted a simple age approach, for example newborn, 1, 5, 10 and 15 years, while others use age bands, for example less than 1 year, 1–5 years, 5–10 years and 10–15 years. Because the size of children, and hence the dose level, significantly varies not only across different ages but also at any given age, this alone is not a good indicator, and patient mass or patient equivalent thickness should also be considered. When DRLs for several mass, size or age groups are defined, the groups should be defined unambiguously by using intervals (e.g. body mass bands). The number of groups chosen should take into account the practical difficulty in collecting a sufficient number of patient dose data in each group. In nuclear medicine, administered activities should be adjusted on the basis of agreed factors linked to size or mass. More guidance on grouping patients for establishing typical doses and DRL is given in para. 3.213 for diagnostic and interventional radiology, in para. 4.205 for diagnostic nuclear medicine and in Ref. [14]. In addition, guidelines on DRLs for paediatric imaging are also being prepared by the European Commission. |
| Diagnostic reference levels |
2.42. |
The processes and steps towards establishing DRLs, as described in paras 2.36–2.41, are likely to involve many parties, including the imaging facilities, the health authority, professional bodies and the regulatory body. In particular, there should be collective ownership of the DRLs in deciding which procedures and age groups will be used, how the data will be collected, who will manage the data, and when the DRLs should be reviewed and updated. In some States, a national governmental body administers the national patient dose database that underpins the establishing of DRLs. In other States, this role may be taken by the regulatory body or a professional body. There is no preferred custodian: what is important is that a patient dose database for DRLs is established and maintained, DRL values are set and then promulgated through the regulatory processes, and a process for periodic review is established. It may be more appropriate to take a regional rather than a national approach to DRLs (see para. 2.34). |
| Diagnostic reference levels |
2.43. |
The methodology used in performing the initial survey can range from a paper based approach through to a web based, electronic submission approach. As the interconnectivity of imaging systems, with the availability of patient dose metrics, and radiology and hospital information systems (HISs) improves, the process of gathering data for DRLs is likely to become easier. States embarking on establishing DRLs for the first time should consider applying an electronic submission approach. |
| Diagnostic reference levels |
2.44. |
The national or regional DRL values should be periodically reviewed and updated, typically with a cycle of three to five years (see para. 2.35). The review can be performed in many ways, but in all cases there is first a collection phase, followed by analysis of the data collected. The collection of facility typical doses can occur throughout the cycle, or it can be restricted to a shorter time frame towards the end of the cycle. Pragmatically, the occasion of a medical radiation facility comparing its facility typical doses with the current DRLs would seem to be an appropriate time for the facility to submit its new facility typical doses to the national or regional database being used for the DRLs. At the end of the cycle, an analysis of the submitted facility typical doses would take place, and the values of the DRLs would be updated accordingly. While increased digital connectivity would technically support the continuous collection and analysis of data, a given set of DRL values should be kept stable for a period of time to allow the improvement cycle to take place. |
| Diagnostic reference levels |
2.45. |
Finally, if the State is not able to facilitate the establishment of its own national DRLs or to participate in a regional approach, there is the option to facilitate the adoption of the DRLs from another State or region. While such DRLs might not reflect the State’s own practice, with judicious selection, the adopted DRLs can still perform the same role of bringing about an improvement in the optimization of protection and safety in the adopting State. Care is needed when comparing DRLs from States that use significantly different generations of imaging systems. |
| Dose constraints |
2.46. |
Dose constraints are not dose limits; they are tools for optimization of protection and safety, including considerations of social and economic factors. The role of dose constraints for occupational exposure and for public exposure is introduced in para. 2.16. In particular, the government, typically through the radiation protection regulatory body, has responsibilities with respect to public exposure, where its primary role is to ensure that no member of the public can exceed the public dose limit as a result of cumulative public exposure arising from multiple authorized facilities, including medical radiation facilities. A simple approach that can be taken is to set a dose constraint for public exposure arising from a single facility at some fraction of the dose limit. Some States use a dose constraint of approximately one third of the dose limit, namely an effective dose of 0.3 mSv per year [20]. In establishing such a dose constraint, the regulatory body should consider the number and type of radiation sources used in a particular State or region that may result in public exposure. |
| Dose constraints |
2.47. |
In addition to patients, two other groups of people that can incur medical exposure are carers and comforters, and volunteers in biomedical research. Since it is medical exposure, neither of these groups is subject to dose limits for the exposures incurred. Instead, reliance is placed on the use of dose constraints as a means for ensuring that optimization of protection and safety takes place (see para. 2.16). For both of these groups of people, the government, through consultation with the health authority, the relevant professional bodies and the radiation protection regulatory body, has the responsibility to ensure that dose constraints are established. |
| Dose constraints |
2.48. |
For carers and comforters, the usual approach is to apply dose constraints on an episode by episode basis — that is, the dose constraint applies to the cumulative exposure of the carer or comforter over the duration of that person giving care and comfort to a patient. In the case of a parent assisting with his or her child undergoing a diagnostic X ray procedure, the episode is the time in which the X rays are being produced, which is extremely short. In the case of a carer or comforter for a person having undergone treatment with radiopharmaceuticals, the episode will last several days until the radionuclide has decayed to negligible levels. Consideration should be given to the cumulative dose of a carer or comforter acting in this role for several distinct episodes. In such cases, a dose constraint per annum may be used in addition to an episode based dose constraint. |
| Dose constraints |
2.49. |
In setting dose constraints for carers and comforters, consideration should be given to the age of the individual and the possibility of pregnancy. A particular issue is that of children in this role. The definition of a carer or comforter includes that the person “willingly and voluntarily” helps in this role. It could be argued that young children might not understand such concepts. Nonetheless, it is reasonable and likely that the children of a parent undergoing treatment would want to provide and receive comfort. The framework for radiation protection and safety should accommodate such wishes. A pragmatic approach is often taken, whereby children in this role are effectively treated as members of the public and their medical exposure is constrained to an effective dose of 1 mSv per episode. A pregnant carer or comforter presents a similar situation, and consideration should be given to the embryo or fetus. The same approach of constraining the effective dose to the embryo or fetus to 1 mSv per episode is often taken. For an adult carer or comforter, a value of dose constraint commonly used is 5 mSv effective dose per episode. For elderly persons, more lenient dose constraints may be used. In any of these cases, flexibility may need to be applied with respect to the dose constraint. |
| Dose constraints |
2.50. |
In setting dose constraints for diagnostic radiological procedures that are performed on volunteers participating in a programme of biomedical research, the intention is that government, through consultation with the health authority, the relevant professional bodies and the radiation protection regulatory body, provides broad guidance for the ethics committees (see paras 2.99–2.102) who, in turn, would adapt the dose constraints to suit the particular programme of biomedical research under consideration. Typical patient doses and national DRLs would be two considerations in setting such dose constraints. |
| Criteria and guidelines for the release of patients after radionuclide therapy |
2.51. |
Many factors can influence the exposure that members of the public and carers and comforters can incur following the release of a patient who has undergone a therapeutic procedure with unsealed sources or who retains implanted sealed sources (for detailed information on these factors for unsealed sources, see Ref. [21]). The role of government, through consultation with the health authority, the relevant professional bodies and the radiation protection regulatory body, is to ensure that criteria are established, with accompanying guidance, to help to simplify the process when individual medical radiation facilities are considering the release of a patient. Guidance for such actions of the medical radiation facility is given in Sections 4 and 5. |
| Health authority |
2.52. |
All medical facilities should be authorized by the health authority to ensure that the facility meets the applicable requirements for quality of medical services. When the medical facility uses ionizing radiation, authorization for medical practice and health care should be granted by the health authority only if the radiation safety requirements are met (paras 2.70–2.76). As noted in para. 2.30, the health authority should contribute to radiation protection and safety. This includes participation in establishing DRLs, dose constraints for carers and comforters and for volunteers in biomedical research, and criteria and guidance for the release of patients after radionuclide therapy (see the guidance in paras 2.34–2.51). Coordination and collaboration between the health authority and the radiation protection regulatory body should ensure radiation protection and overall safety of the medical facility. |
| Health authority |
2.53. |
Radiation protection and safety in medical uses of ionizing radiation should be assured by the proper specialization of health professionals, namely that only health professionals with the appropriate competencies can take on roles that include specific responsibilities for radiation protection and safety. The health authority has responsibilities in providing policy and guidance with respect to health profession specialties and their subspecialties, including on the scope of practice, and requirements for competence. Guidance on recognition of competence in a specialty is given in paras 2.119–2.133. |
| Health authority |
2.54. |
Adequate numbers of radiological medical practitioners, medical radiation technologists, medical physicists and other health professionals with responsibilities for patient radiation protection should be available for a medical radiation facility to function correctly and safely. This includes sufficient capacity to cover absences of key personnel through sickness, leave or other reasons. The health authority, through its policy making role, should set clear standards for acceptable medical practice. |
| Health authority |
2.55. |
The health authority has particular roles in the application of the radiation protection requirements for justification, namely with respect to: Generic justification of radiological procedures;
Justification of radiological procedures in health screening programmes;
Criteria for the justification of radiological procedures for health assessment of asymptomatic individuals intended for the early detection of disease, but not as part of a health screening programme.
|
| Health authority |
2.56. |
Generic justification of radiological procedures is an ongoing process as new procedures become available and as established procedures are reviewed in the light of new knowledge and developments. It should be decided whether a new radiological procedure should become a new addition to the existing procedures. Conversely, an existing radiological procedure may need to be withdrawn from use if there is evidence that an alternative modality or technology has greater efficacy. The health authority, together with relevant professional bodies, should make these decisions. |
| Health authority |
2.57. |
The use of radiological procedures as part of a health screening programme involves subjecting asymptomatic populations to radiation exposure. The decision to embark upon such a programme should include consideration of, inter alia, the potential of the screening procedure to detect a particular disease, the likelihood of effective treatment of cases detected and, for certain diseases, the advantages to the community from the control of the disease. Sound epidemiological evidence should provide the basis for such health screening programmes. The health authority, together with relevant professional bodies, should consider all the factors before reaching a decision. |
| Health authority |
2.58. |
The use of radiological procedures on asymptomatic individuals, intended for the early detection of disease but not as part of an approved health screening programme, is now increasingly common. Such radiological procedures are not established medical practice, nor are they performed as part of a programme of biomedical research. Therefore, the health authority, together with relevant professional bodies, has a role in providing guidance on the applicability and appropriateness of such procedures. Such guidance would help the referring medical practitioner and the radiological medical practitioner carry out the process of justification for an individual patient (see paras 3.141–3.143). |
| Health authority |
2.59. |
National or international referral guidelines should be used as an important tool in the application of the process of justification of medical exposure for an individual patient. The health authority should support the relevant professional bodies in developing and implementing evidence based referral guidelines (see also para. 2.65).
|
| Health authority |
2.60. |
The health authority should also encourage the development of, and promote the implementation of, practice guidelines and technical standards developed by professional bodies. |
| Professional bodies |
2.61. |
Professional bodies is the collective term used in GSR Part 3 [3] and in this Safety Guide to include the various organizations and groups of health professionals. These include societies, colleges and associations of health professionals, often for a particular specialty. Examples of professional bodies with direct involvement in the use of ionizing radiation include societies, colleges and associations of radiologists, radiation oncologists, nuclear medicine physicians, medical physicists, medical radiation technologists and dentists. In large States, such professional bodies might be regional within the State. Conversely, there can be regional professional bodies covering several States. There are also professional bodies in the wider medical arena that still influence some aspects of radiation use. Examples of these include societies, associations and colleges representing specialties such as cardiology, gastroenterology, urology, vascular surgery, orthopaedic surgery and neurology, who may use radiation, and other organizations, such as those that represent general practitioners and primary care physicians. |
| Professional bodies |
2.62. |
Professional bodies, as stated in para. 2.30, represent the collective expertise of the given health profession and specialty and, as such, they should also play a role in contributing to radiation protection and safety in medical uses of ionizing radiation. This includes setting standards for education, training, qualifications and competence for a given specialty, and setting technical standards and giving guidance on practice. Further guidance on education, training, qualifications and competence is given in paras 2.119–2.133. |
| Professional bodies |
2.63. |
Relevant professional bodies, in partnership with the health authority and the radiation protection regulatory body, have a role with respect to the establishment of DRLs, dose constraints for carers and comforters and for volunteers in biomedical research, and criteria and guidance for the release of patients after radionuclide therapy, as is described in paras 2.42, 2.47–2.50 and 2.51, respectively.
|
| Professional bodies |
2.64. |
The role of the relevant professional bodies with respect to the application of the requirements for justification is described in paras 2.56–2.60. |
| Professional bodies |
2.65. |
Professional bodies should take the lead in the development of referral guidelines (also called appropriateness criteria in some States) for use in justification of medical exposure for an individual patient (para. 2.59). It might not be possible for every State to develop its own referral guidelines. The significant work of a number of professional bodies around the world could be utilized by many other States through adoption or adaptation by the local professional bodies (see also paras 3.143 and 4.160). |
| Professional bodies |
2.66. |
With respect to medical imaging, the process of optimization of radiation protection and safety should aim at achieving adequate image quality — not the best possible image quality, but certainly sufficient to ensure that diagnosis or treatment is not compromised. From an operational perspective, there are many factors that influence the relationship between image quality and patient dose. Having standards or norms that specify acceptable image quality is clearly advantageous, and relevant professional bodies have a role in establishing and promoting such criteria. |
| Professional bodies |
2.67. |
For the optimization of radiation protection and safety, a comprehensive programme of quality assurance for medical exposure is required. Such programmes should be part of the wider management system of the medical radiation facility (see para. 2.140). Nonetheless, there is considerable benefit in making use of resource material and standards established by professional bodies for particular areas of the programme of quality assurance. For example, many medical physics professional bodies have developed detailed guidance on performance testing aspects of a programme of quality assurance. Where such material or standards are lacking in a State, the relevant professional body could adopt or adapt such resources from outside the State. |
| Professional bodies |
2.68. |
Professional bodies should encourage their members to perform proactive risk assessment, especially in radiotherapy. They can also play an active role by encouraging their members to contribute to relevant international or national anonymous and voluntary safety reporting and learning systems, and by contributing to developing of such systems. Such databases provide a wealth of information that can help to minimize unintended and accidental medical exposures. Examples of international safety reporting systems are the IAEA safety reporting systems Safety in Radiation Oncology (SAFRON) and Safety in Radiological Procedures (SAFRAD), and the Radiation Oncology Safety Education and Information System (ROSEIS).
|
| Professional bodies |
2.69. |
Professional bodies have a role in disseminating information on standards and guidance relevant to radiation protection and safety. |
| Regulatory body |
2.70. |
The radiation protection regulatory body should fulfil its regulatory functions, such as establishing requirements and guidelines, authorizing and inspecting facilities and activities, and enforcing legislative and regulatory provisions. Detailed requirements specifying these roles and responsibilities are given in GSR Part 3 [3] and GSR Part 1 (Rev. 1) [13], and further general guidance is provided in IAEA Safety Standards Series No. GS-G-1.5, Regulatory Control of Radiation Sources [22]. Guidance on general regulatory body roles and responsibilities with respect to occupational radiation protection and radiation protection of the public are given in IAEA Safety Standards Series Nos GSG-7, Occupational Radiation Protection [23], and GSG-8, Radiation Protection of the Public and the Environment [24]. A prerequisite for the regulatory body being able to perform its regulatory functions effectively is having staff with appropriate specialist expertise. This is covered in detail in GSR Part 3 [3], GSR Part 1 (Rev. 1) [13] and GS-G-1.5 [22], and applies in the context of medical uses of ionizing radiation. The regulatory controls should be applied knowledgeably and not just as an administrative exercise. |
| Authorization of medical radiation facilities |
2.71. |
The graded approach to medical uses of ionizing radiation has particular significance for regulatory bodies because, as described in paras 2.23–2.27, there is a wide variation in the complexity of medical radiation facilities. Regulatory bodies should consider which form of authorization is appropriate for a given type of medical radiation facility. Coupled with the type of authorization is the level of complexity of the documentation that should be submitted to the regulatory body prior to the authorization. This includes the degree of detail in the safety assessment (see paras 2.150–2.154). The duration for which the authorization is granted is another consideration for the regulatory body; more complex facilities would warrant a more frequent renewal process. |
| Authorization of medical radiation facilities |
2.72. |
Typical practices that are amenable to registration are those for which: (i) safety can largely be ensured by the design of the facilities and equipment; (ii) the operating procedures are simple to follow; (iii) the safety training requirements are minimal; and (iv) historically, there have been few problems with safety in operations. Registration is best suited to those practices for which operations do not vary significantly. These conditions are generally not met in medical uses of ionizing radiation for the following three reasons: patient exposure depends on human performance; radiation protection and safety is not largely ensured by design; and the amount of training required is significant. Medical radiation facilities are, in principle, better candidates for individualized licensing than for registration. It would be expected that licensing would be used for radiation therapy facilities, nuclear medicine facilities, facilities performing image guided interventional procedures and for most diagnostic radiology facilities. For some simple forms of diagnostic radiology, such as dental radiography (without CBCT) and DXA, authorization through registration may be acceptable. For both forms of authorization, the regulatory body should develop standardized forms or templates that help to ensure that the correct information is submitted to the regulatory body (see also paras 2.150–2.154 on safety assessment). |
| Authorization of medical radiation facilities |
2.73. |
No matter which form of authorization is used for a medical radiation facility, a crucial step prior to the granting of it is that the regulatory body ascertains the credentials of key personnel with responsibilities for radiation protection and safety, including radiological medical practitioners, medical radiation technologists, medical physicists and RPOs. This step cannot be overemphasized, as all aspects of radiation protection and safety in medical uses of ionizing radiation depend ultimately on the competence of the personnel involved (see also paras 2.119–2.137). |
| Authorization of medical radiation facilities |
2.74. |
Setting up a medical radiation facility may involve the construction of facilities that are difficult to modify at a later time. Regulatory bodies may choose a two stage process of authorization; that is, to require an initial application to build a facility to be submitted before construction begins. At this stage, the regulatory body should review the intended medical uses of ionizing radiation, the facility’s design, including structural shielding plans, and the planned equipment. This is followed at a later stage by the full review and assessment by the regulatory body, leading to the granting of the authorization. For more complex medical radiation facilities, such as a radiation therapy facility, this latter process should include an inspection by the regulatory body or authorized party. |
| Authorization of medical radiation facilities |
2.75. |
Subsequent, substantial modifications of a medical radiation facility, including its medical radiological equipment and its procedures, may have safety implications. The regulatory body may require an application for an amendment to the authorization. |
| Authorization of medical radiation facilities |
2.76. |
The regulatory body should require the renewal of an authorization after a set time interval. This allows a review of the findings of inspections and of other information on the safety performance of the medical radiation facility. The frequency of renewal should be based on radiation protection and safety criteria, with consideration given to the frequency of inspections by the regulatory body and the safety record associated with a given type of practice in general or with a particular medical radiation facility. A renewal cycle longer than five years would normally not be appropriate for medical radiation facilities. |
| Authorization of medical radiation facilities |
2.77. |
The authorization of a medical radiation facility to use ionizing radiation for medical purposes is a separate exercise to the authorization of the same facility, or the wider medical facility of which it is part, by the health authority to carry out medicine practice and health care (see para. 2.52). Meeting radiation safety requirements is a condition that is necessary but not sufficient to obtain an authorization to practice medicine. Coordination and collaboration between the radiation protection regulatory body and the health authority should take place to ensure radiation protection and overall safety of the medical facility. |
| Inspection of medical radiation facilities |
2.78. |
On-site inspection by the regulatory body is often the principal means for face-to-face contact with personnel in the medical radiation facility. The regulatory body should establish a system for prioritization and frequency of inspections, based on the risk and complexity associated with the particular medical uses of ionizing radiation. The inspection by the regulatory body of medical radiation facilities should be performed by staff with the specialist expertise to be able to assess competently the compliance of the facility with the radiation protection regulations and authorization conditions. Further guidance on inspections is given in GS-G-1.5 [22]. |
| Particular considerations for the regulatory body with respect to medical exposure, occupational exposure and public exposure |
2.79. |
The regulatory body should ensure that all the requirements of GSR Part 3 [3] with respect to medical exposure, occupational exposure and public exposure are applied in authorized medical radiation facilities, as described in detail in the relevant subsections of Sections 3–5. To help medical radiation facilities fulfil their obligations, there are some particular areas for which the regulatory body should provide specific guidance. |
| Particular considerations for the regulatory body with respect to medical exposure, occupational exposure and public exposure |
2.80. |
Arrangements for the calibration of sources giving rise to medical exposure are required to be in place to ensure radiation protection and safety in medical uses of ionizing radiation, as established in para. 3.167 of GSR Part 3 [3], and detailed guidance is given in Sections 3–5. The regulatory body should specify frequencies for re-calibration of equipment and, in doing so, should make use of applicable guidance given by professional bodies of medical physics. |
| Particular considerations for the regulatory body with respect to medical exposure, occupational exposure and public exposure |
2.81. |
In the case of the calibration of radiation therapy units, independent verification prior to clinical use is required to be assured (para. 3.167(c) of GSR Part 3 [3]). The regulatory body should be aware of the limitations on local resources in their State. An ‘ideal’ independent verification — for example by independent medical physicist using different dosimetry equipment — might not be feasible. The regulatory body has the responsibility to ensure that the radiation safety of the radiation therapy unit is not compromised and at the same time the facility is not unnecessarily closed down. The regulatory body should decide on acceptable alternatives, such as verification by a different medical physicist with the same equipment or verification by using a different set of equipment, or using a form of verification by postal dosimetry using thermoluminescent, optically stimulated luminescent dosimeters or equivalent. |
| Particular considerations for the regulatory body with respect to medical exposure, occupational exposure and public exposure |
2.82. |
Unintended and accidental medical exposures do occur, and the regulatory body is required to ensure that a system is put in place and all practical measures are taken to prevent such exposures, and, if such an exposure does occur, that it is properly investigated and corrective actions are taken (Requirement 41 of GSR Part 3 [3]). Arrangements should be put in place to respond promptly in order to mitigate any consequences. The regulatory body should require written records to be kept of all unintended and accidental medical exposures and should provide guidelines on what information is to be included in these reports. The more significant events are required to be reported to the regulatory body (para. 3.181(d) of GSR Part 3 [3]). The regulatory body should provide guidance on which events should be reported to them. One of the reasons for reporting to the regulatory body is to enable the regulatory body, in turn, to disseminate information on the event to relevant parties so that the recurrence of similar events can be minimized. In addition to mandatory reporting for regulatory purposes, anonymous and voluntary safety reporting and learning systems can significantly contribute to enhanced radiation protection and safety and quality in health care. The regulatory body should be proactive and encourage medical radiation facilities to participate in relevant international or national anonymous and voluntary safety reporting and learning systems, as stated in para. 2.68. Further guidance is given in Sections 3–5. |
| Particular considerations for the regulatory body with respect to medical exposure, occupational exposure and public exposure |
2.83. |
With respect to assessment of occupational exposure, the regulatory body should establish requirements and provide clear guidance on which form of monitoring should be in place. Paragraphs 3.99–3.102 of GSR Part 3 [3] require employers, registrants and licensees to make arrangements for assessment of occupational exposure, and provide broad criteria for when individual monitoring should be arranged and when workplace monitoring may be sufficient. Occupational exposures vary widely in medical uses of ionizing radiation, ranging from uses where it is quite clear that individual monitoring should be undertaken, to uses where workplace monitoring would suffice. It is where uses fall between these two situations that specific direction should be provided by the regulatory body. Further guidance is given in Sections 3–5. |
| Particular considerations for the regulatory body with respect to medical exposure, occupational exposure and public exposure |
2.84. |
The regulatory body has a role as the custodian of public radiation protection. Because a member of the public can be subject to exposure arising from any number of authorized medical radiation facilities (or indeed other facilities and activities using radiation), the regulatory body has an oversight role to ensure that the cumulative effect of these multiple exposure pathways does not lead to public exposure greater than the dose limits (see Box 1). Part of this role includes setting dose constraints and ensuring that safety assessments include considerations of public exposure and potential public exposure. |
| Particular considerations for the regulatory body with respect to medical exposure, occupational exposure and public exposure |
2.85. |
GSR Part 3 [3] establishes many requirements for registrants, licensees and employers with respect to occupational radiation protection to maintain and make available records on a wide range of matters. GSR Part 3 [3] requires that: |
| Authorization for the installation, maintenance and servicing of medical radiological equipment |
2.86. |
The regulatory body should ensure that the activities to install, maintain or service medical radiological equipment are appropriately authorized (see also paras 2.103–2.111 on responsibilities for suppliers of sources, equipment and software, paras 2.112–2.114 maintenance and servicing organizations, and para. 2.135 on education, training, qualification and competence of servicing engineers and technicians). |
| Authorization of other practices relating to medical uses of ionizing radiation |
2.87. |
The regulatory body may also require authorization for other activities relating to medical uses of ionizing radiation, including: the import, distribution, assembly, sale, transfer and transport of radioactive sources or medical radiological equipment; decommissioning; and disposal of radioactive sources and waste. The requirements to carry out these practices should be established by regulations, and complementary regulatory guidance documents should be provided. |
| Dissemination of information |
2.88. |
Paragraph 2.33 of GSR Part 3 [3] requires that the regulatory body ensures that mechanisms are in place for the timely dissemination of information, in the context of this Safety Guide, to medical radiation facilities, manufacturers and suppliers, the health authority and professional bodies, on lessons for radiation protection and safety resulting from regulatory experience and operating experience, and from incidents, including accidents, and related findings. Information should be exchanged through the publication of newsletters and the periodic mailing of notices, by presentations at scientific meetings and meetings of professional associations, by establishing a web site, or by co-sponsoring educational seminars and workshops with professional and scientific associations. More rapid actions should be considered in response to actual or potential problems that may result in significant consequences. |
| Medical radiation facility |
2.89. |
In medical uses of ionizing radiation, the prime responsibility for radiation protection and safety rests with the person or organization responsible for the medical radiation facility, normally referred to as the registrant or licensee. Almost all the requirements of GSR Part 3 [3] applicable to a medical radiation facility for ensuring radiation protection and safety in medical uses of ionizing radiation place the responsibility on the registrant or licensee (and on the employer, in the case of occupational radiation protection). |
| Medical radiation facility |
2.90. |
However, medical uses of ionizing radiation involve a multidisciplinary team led by a health professional who often is not the registrant or licensee of the authorized medical radiation facility. Because of the medical setting in which such exposures occur, primary responsibility for radiation protection and safety for patients lies with the health professional responsible for the radiological procedure, who is referred to in GSR Part 3 [3] and in this Safety Guide as the radiological medical practitioner. The term ‘radiological medical practitioner’ is the generic term that GSR Part 3 [3] uses to refer to a health professional with specialist education and training in medical uses of radiation, who is competent to perform independently or to oversee procedures involving medical exposure in a given specialty. Health professionals that could take on the role of the radiological medical practitioner, depending on the particular use of radiation and on the laws and regulations in a State, include radiologists, nuclear medicine physicians, radiation oncologists, cardiologists, orthopaedic surgeons, other specialist physicians, dentists, chiropractors and podiatrists. More guidance on the health professionals who could be radiological medical practitioners is given in Sections 3–5 and in paras 2.124 and 2.125 on education and training. |
| Medical radiation facility |
2.91. |
The net effect of paras 2.89 and 2.90 is that, for medical exposure, the registrant or licensee should ensure all requirements are applied. This normally requires that the radiological medical practitioner ensure a given set of actions take place, usually with the involvement of further health professionals, mainly medical radiation technologists and medical physicists (see paras 2.92 and 2.93, respectively). The medical exposure subsections of Sections 3–5 provide guidance on meeting the many requirements that come under the responsibility of the radiological medical practitioner. |
| Medical radiation facility |
2.92 |
The term ‘medical radiation technologist’ is used in GSR Part 3 [3] and this Safety Guide as the generic term for a second group of health professionals. A wide variety of terms are used throughout the world for such health professionals, such as radiographer, radiological technologist, nuclear medicine technologist and radiation therapist. In GSR Part 3 [3], a medical radiation technologist is a health professional with specialist education and training in medical radiation technology, competent to perform radiological procedures, on delegation from the radiological medical practitioner, in one or more of the specialties of medical radiation technology (e.g. diagnostic radiology, radiation therapy and nuclear medicine). The medical radiation technologist is usually the interface between the radiological medical practitioner and the patient, and his or her skill and care in the choice of techniques and parameters determines to a large extent the practical realization of the optimization of radiation protection and safety for a given patient’s exposure in many modalities. The medical radiation technologists may also have a role in education and training. More guidance on the roles and responsibilities of medical radiation technologists is given in Sections 3–5 and in paras 2.126 and 2.127 on education and training. |
| Medical radiation facility |
2.93 |
In GSR Part 3 [3], a medical physicist is a health professional with specialist education and training in the concepts and techniques of applying physics in medicine and competent to practise independently in one or more of the subfields (specialties) of medical physics (e.g. diagnostic radiology, radiation therapy and nuclear medicine). The medical physicist provides specialist expertise with respect to radiation protection of the patient. The medical physicist has responsibilities in the optimization of radiation protection and safety in medical exposures, including source calibration, clinical dosimetry, image quality and patient dose assessment, and physical aspects of the programme of quality assurance, including medical radiological equipment acceptance and commissioning. The medical physicist is also likely to have responsibilities in providing radiation protection and safety training for health professionals. In addition, he or she may also perform the role of the RPO, whose responsibilities are primarily in occupational and public radiation protection. More guidance on the roles and responsibilities of medical physicists is given in Sections 3–5, in Ref. [26], and in paras 2.128 and 2.129 on education and training. |
| Medical radiation facility |
2.94. |
There are other health professionals with responsibilities for radiation protection of the patient. These include, for example, radiopharmacists, radiochemists, dosimetrists and biomedical or clinical engineers. Detailed guidance is given in Sections 3–5. |
| Medical radiation facility |
2.95. |
For a medical radiation facility, the radiation protection and safety responsibilities outlined above for the radiological medical practitioner, the medical radiation technologist, the medical physicist and other health professionals with responsibilities for patient radiation protection should be assigned through an authorization (or other regulatory means) issued by the radiation protection regulatory body in that State. |
| Medical radiation facility |
2.96. |
The RPO is: “A person technically competent in radiation protection matters relevant for a given type of practice who is designated by the registrant, licensee or employer to oversee the application of regulatory requirements” [3]. For a medical radiation facility, the RPO oversees the application of requirements for occupational and public radiation protection, and may provide general radiation protection advice to the registrant or licensee. The RPO has no direct responsibilities or roles with respect to patient radiation protection. An RPO, unless he or she has recognized competence in medical physics, cannot perform the role of a medical physicist with respect to medical exposure. |
| Medical radiation facility |
2.97. |
In addition, all health professionals involved in medical uses of ionizing radiation have responsibilities with respect to occupational and public radiation protection. (See the occupational and public radiation protection subsections in Sections 3–5). |
| Medical radiation facility |
2.98 |
Medical radiation facilities, as they increasingly utilize digital technologies, should ensure access to an IT specialist who, through specialized training and experience, has competence in the maintenance and quality control of IT software and hardware. The correct functioning of these systems is crucial for radiation protection and safety. |
| Ethics committee |
2.99. |
Participants in a programme of biomedical research may be either patients, with some disease or ailment, or they may be healthy individuals. Regardless, they should be volunteers. The ethics committee has a particular responsibility with respect to justification of medical exposure of volunteers exposed as part of a programme of biomedical research (para. 3.161 of GSR Part 3 [3]). The first part of this responsibility is to decide whether to approve the programme of biomedical research, including the proposed use of radiation. The use of radiation in a programme of biomedical research can include: The use of a diagnostic radiological procedure to assess the efficacy of the treatment under investigation (e.g. ranging from a DXA scan to measure bone mineral density before, during and after a given treatment regime, to a CT or a positron emission tomography (PET)–CT examination to assess some clinical indicators, again performed before, during and after the treatment);
Trials being performed to assess a new radiopharmaceutical (i.e. the radiation itself is part of the research, rather than a tool for assessment);
Trials being performed to assess a new radiotherapy protocol alone or in combination with other therapeutic modalities;
Trials being performed to compare radiological procedures, for example specificities and sensitivities of different imaging procedures or efficacy of different treatments;
Trials being performed to assess physiological and/or biochemical processes in healthy individuals. In making its decision, the ethics committee should be presented with correct information on the expected doses and estimates of the radiation risks based on the age, sex and health status of the participants. The ethics committee should also obtain information on who will perform the radiological procedures and how. The dose estimates and the associated radiation risks should be assessed by a medical physicist. This information should be then considered by the ethics committee together with the information on the other risks and benefits of the programme.
|
| Ethics committee |
2.100. |
The ethics committee has the responsibility to specify any dose constraints that are to be applied to the doses incurred as part of the approved programme of biomedical research. Such dose constraints would be guided by nationally or regionally established dose constraints (see para. 2.50). Dose constraints should be adjusted to the expected benefit of the programme of biomedical research: the lower the benefit to society, the more stringent the dose constraint. The ICRP stratifies doses incurred in biomedical research according to radiation risk [27] and in Ref. [4] assigns numerical values of dose constraints ranging from less than 0.1 mSv to greater than 10 mSv, as the benefit to society ranged from minor through to substantial. Less stringent dose constraints may be applied for participants with short life expectancy (e.g. see Ref. [28]). Particular attention should be given to setting dose constraints for healthy volunteers who repeatedly take part in biomedical research programmes that expose them to increased risks. |
| Ethics committee |
2.101. |
Ethics committees might not be aware of these responsibilities. Therefore, the radiation protection regulatory body should act as a facilitator in promoting systems so that the ethics committee knows about its responsibilities when a proposal for a programme of biomedical research that includes radiation exposure is submitted to the ethics committee. Such a system may include a standardized proposal form that includes the question ‘Will ionizing radiation be used as part of this programme of biomedical research?’ If the answer is yes, the form should then request information on radiation doses and risks to be provided, having been first assessed and signed off by a medical physicist. |
| Ethics committee |
2.102. |
In parallel, the regulatory body should inform the registrants and licensees that radiological procedures requested as part of a programme of biomedical research are justified only if that programme has been approved by the ethics committee, and that such an approval is subject to dose constraints, which would then influence how the procedure would be performed. |
| Suppliers of sources, equipment and software |
2.103. |
Suppliers of medical radiological equipment and developers of software that could influence the delivery of the medical exposure have responsibilities with respect to design and performance. Generic requirements are established in para. 3.49 of GSR Part 3 [3] and specific requirements in para. 3.162 of GSR Part 3 [3]. |
| Suppliers of sources, equipment and software |
2.104. |
A particular issue with medical radiological equipment and software in medical uses of ionizing radiation is that of the language, terminology and icons used on control panels, on software screens and in instruction manuals. English and other widely spoken languages dominate. The person using the equipment or software should fully understand the options being presented, and translation into a local language is strongly recommended. It is not appropriate to assume that partial knowledge of other languages is sufficient; there are documented instances of unintended or accidental medical exposures arising from incorrect understanding of the displayed language (e.g. see Ref. [29]). |
| Suppliers of sources, equipment and software |
2.105. |
Many items of medical radiological equipment can be configured and supplied with different options. For example, protective tools may be an optional extra, with a higher price. Basic model versions of a given piece of equipment should include as a default all the relevant protective tools and the features that provide the greatest control over patient radiation protection. Paring the price back by removing radiation protection and safety options in order to gain a sale is not acceptable. Facility management should not be placed in a position of saving money at the expense of compromising radiation protection and safety. |
| Suppliers of sources, equipment and software |
2.106. |
When medical radiological equipment and software are to be part of a digital network, suppliers should facilitate interconnectivity with other relevant systems. |
| Suppliers of sources, equipment and software |
2.107. |
After installation of medical radiological equipment or software, the supplier should go through a formal handover to the medical radiation facility’s registrant or licensee. This should include acceptance testing, described in more detail in Sections 3–5. |
| Suppliers of sources, equipment and software |
2.108. |
Specific training in the use of the equipment or software should be given to the staff of the medical radiation facility, including the radiological medical practitioners, the medical radiation technologists, the medical physicists and the local maintenance engineers. The features of the equipment or software should be fully understood, including their implications for radiation protection of patients and personnel. |
| Suppliers of sources, equipment and software |
2.109. |
The radiation protection and safety responsibilities of suppliers of refurbished medical radiological equipment should be no different to the responsibilities for the supply of new equipment. Further guidance on refurbished equipment is given in Refs [30, 31]. |
| Suppliers of sources, equipment and software |
2.110. |
The radiation protection and safety responsibilities for donors of medical radiological equipment should be no different to those of commercial suppliers for such equipment. Further guidance on donated equipment is given in Refs [32, 33].
|
| Suppliers of sources, equipment and software |
2.111. |
Regulatory control of engineers and technicians who install medical radiological equipment varies around the world. In many States, they will be licensed to perform installation and servicing and a prerequisite to obtaining such a licence should be that they have had appropriate radiation protection and safety training. Guidance on education, training, qualification and competence of installation and servicing personnel is given in para. 2.135. |
| Maintenance and servicing organizations |
2.112. |
Maintenance and servicing of medical radiological equipment is usually performed by an engineer or technician employed either by a company offering such services (who may also be the manufacturer and/or the vendor) or by the medical facility itself (e.g. as part of an engineering, biomedical or clinical engineering, or service department). In either case, when the medical radiological equipment is being serviced, the equipment should not be used for medical exposures; patients should not be imaged or treated until service and hand back is completed (see para. 2.113). The engineer or technician should follow both the radiation protection and safety rules and procedures established by his or her employer and the relevant rules and procedures of the medical radiation facility, including rules and procedures on how to ensure a safe working environment for the service and how to ensure restricted access to the area where the servicing is taking place. Further guidance on good practice in maintenance is given in Ref. [34]. |
| Maintenance and servicing organizations |
2.113. |
Maintenance and servicing continues until the medical radiological equipment is ready to be handed back to the medical radiation facility’s registrant or licensee. The handover to the registrant or licensee should be formalized. Depending on the maintenance or servicing that has taken place, there may be a need for quality control tests to be performed by a medical physicist before the handover is complete (see paras 3.49, 4.59 and 5.91). The engineering service should collaborate with medical physicists, medical radiation technologists and radiological medical practitioners in ensuring optimal performance of the equipment. The engineer or technician should also inform the registrant or licensee of any changes with respect to the medical radiological equipment that may have implications for radiation protection and safety. At this stage, the equipment is available for medical use. Pressures to hand medical radiological equipment back for medical use should not be allowed to compromise radiation protection and safety; for example, equipment should not be used clinically while it is still in a ‘service mode’. |
| Maintenance and servicing organizations |
2.114. |
Regulatory control of servicing engineers and technicians varies around the world. In many States, they will be licensed to perform servicing and a prerequisite to obtaining such a licence should be that they have had appropriate education and training in radiation protection and safety. Guidance on education, training, qualification and competence of servicing engineers and technicians is given in para. 2.135. |
| Referring medical practitioners |
2.115. |
The health care of the patient is the responsibility of the physician or health professional managing the patient. This physician or health professional may decide that the patient needs to undergo a radiological procedure, at which point a referral to an appropriate medical radiation facility is initiated. Referring medical practitioner is the generic term used in GSR Part 3 [3] for the health professional who may refer individuals for a radiological medical procedure. There may be different requirements in different States about who can act in the role of a referring medical practitioner. The referring medical practitioner has a joint responsibility with the radiological medical practitioner to decide on the justification of the proposed radiological procedure. More detailed guidance is given in Sections 3–5. |
| Referring medical practitioners |
2.116. |
Usually the roles of the referring medical practitioner and the radiological medical practitioner are performed by two different people. However, there are some instances in which both roles are performed by the same person, often called self-referral. A very common example is a dentist, who decides whether an X ray examination is necessary and, if so, performs the examination. Dental professional bodies in many States have established guidelines for when dental X ray examinations are appropriate or not, and use of these guidelines should help the dentist to fulfil both roles acceptably. In other situations, typically involving medical imaging, there may be very strong financial incentives for self-referral because the performance of the radiological procedure generates significant income. Again there is a clear role for professional body guidelines to help to minimize potential misuses of self-referral. |
| Patients |
2.117. |
Patients are increasingly being involved in the decision making processes concerning their own health care, and this includes medical uses of ionizing radiation. Paragraph 3.151(d) of GSR Part 3 [3] requires that the registrant or licensee for the medical radiation facility ensure that the patient be informed, as appropriate, of both the potential benefit of the radiological procedure and the radiation risks. Information should be provided in an understandable format (e.g. verbally, leaflets, posters and web sites) and in a timely manner. The level of information should be commensurate with the complexity, dose and associated risks; and for some radiological procedures, informed consent may be required, either written or verbal. Female patients of reproductive capacity should be informed about the risk to the embryo or fetus from radiological procedures for either diagnosis or therapy. |
| Patients |
2.118. |
‘Self-presenting’ patients are individuals demanding a particular radiological procedure on the basis that they believe that this procedure is needed, for example, to detect cancer or heart disease in its early stages before symptoms become manifest. These individuals should be handled in the same way as any other patient, namely through an appropriate referral and the ensuing justification. |
| Patients |
2.119. |
Medical uses of ionizing radiation involve a number of health professionals performing radiological procedures such as diagnostic examinations, interventional procedures and treatment. In each case, the radiation protection and safety associated with the radiological procedure depends greatly on the skills and expertise of those health professionals involved, as the patient is necessarily and deliberately exposed to radiation. In other words, the education, training, qualification and competence of the respective health professionals underpin radiation protection and safety in medical uses of ionizing radiation. |
| Patients |
2.120. |
GSR Part 3 [3] places great emphasis on education and training for all persons engaged in activities relevant to protection and safety, with the responsibility placed on government to ensure that requirements for education, training, qualification and competence are established and that arrangements are in place for the provision of the necessary education and training. The development and implementation of a national strategy for education and training (see Ref. [35]) that is based on a national needs assessment can be useful in this context. Furthermore, the regulatory body is required to ensure the application of the requirements for education, training, qualification and competence in radiation protection. Such verification should take place when an application for an authorization has been submitted to the regulatory body and during the periodic inspections of the medical radiation facility. Finally, the registrant or licensee of the medical radiation facility has the responsibility to ensure that all
the health professionals in that facility with responsibilities for protection and safety have appropriate education, training, qualification and competence. |
| Patients |
2.121. |
In medical uses of ionizing radiation, medical exposure occurs and occupational and public exposure might occur. For the health professionals involved, it is their education, training, qualification and competence in the medical exposure aspects that are the most critical. To this end, the requirements of GSR Part 3 [3] for the health professionals involved in performing radiological procedures are quite stringent. For each of the key roles of the radiological medical practitioner, the medical radiation technologist, the medical physicist and the radiopharmacist, the definition in GSR Part 3 [3] takes the same form, namely: that the person is a health professional, that they have specialist education and training in the particular discipline (including radiation protection and safety), and that they have been assessed as being competent to carry out that particular role (see Definitions in GSR Part 3 [3] for complete descriptions). The competence of a person is normally assessed by the State through a formal mechanism for registration, accreditation or certification of the particular specialized health professional. States that have yet to develop such a mechanism should assess the education, training and competence of an individual proposed by a licensee to act as a specialized health professional and to decide, on the basis either of international standards or standards of a State where such a system exists, whether the individual can be considered competent. |
| Patients |
2.122. |
A health professional intending to act in any of the roles of radiological medical practitioner, medical radiation technologist, medical physicist or radiopharmacist can do so only if he or she has the requisite education, training, qualification and competence. It is the responsibility of the registrants and licensees to ensure that their staff meet these requirements, and it is the responsibility of the regulatory body to use the authorization, inspection and enforcement processes to ensure that registrants and licensees discharge their responsibilities in this respect. |
| Patients |
2.123. |
The institutes and organizations that provide education and training in radiation protection to health professionals should use GSR Part 3 [3] and this Safety Guide as resources on the requirements for radiation protection and safety in medical uses of radiation. |
| Radiological medical practitioners |
2.124. |
The term ‘radiological medical practitioner’ is applied to a number of health professionals who independently perform or oversee radiological
procedures within a given specialty (see also para. 2.90). Some radiological medical practitioners belong to a specialty with a very long association with medical uses of ionizing radiation, such as radiology, nuclear medicine, radiation therapy and dentistry. In States where there are well established processes in place for education, training, qualification and competence in these specialties, such education, training, qualification and competence includes subjects not only in the specialty itself but also with respect to radiation protection (patient protection and occupational protection). Radiological medical practitioners would typically become registered with the national medical or dental registration board (or a body with a similar function), and competence in the specialty should include competence in radiation protection and safety. The regulatory body and the relevant professional body should periodically review the radiation protection and safety aspects of the education and training to ensure that it is still up to date and relevant. In States where there is a lack of infrastructure for education and training in these specialties, a prospective radiological medical practitioner should gain the necessary education, training and qualification outside the State, both in the specialty itself and in radiation protection and safety. The competence of radiological medical practitioners trained outside the State should be assessed. In this situation the regulatory body should seek advice from the health authority and the relevant professional body (if it exists) with respect to the adequacy of the specialization of the individual and assessment of the individual’s competence with respect to radiation protection and safety may need to be performed by the regulatory body. In time, this approach should develop into a standardized process for dealing with competence assessments. |
| Radiological medical practitioners |
2.125. |
Other specialties, such as orthopaedic surgery and cardiology, have also had a long association with medical uses of ionizing radiation, but radiation protection and safety might not traditionally have been part of the processes for education, training, qualification and competence in the specialty. Still other specialties have a more recent association with medical uses of ionizing radiation, especially with respect to image guided interventional procedures. Radiation protection (patient protection and occupational protection) is often not included in the curriculum for education, training, qualification and competence in these specialties. For specialists from these two groups, additional or separate education and training and credentialing in radiation protection and safety, as it applies to their specialty, may need to be arranged. The relevant professional bodies and the regulatory body should work together in establishing acceptable criteria on education and training in radiation protection and safety, and the means for recognition of competence in radiation protection. The preferred approach is for the relevant professional body to administer the process and to maintain a register of specialists and their radiation protection and safety credentials. Another possibility is the regulatory body taking on the role of overseeing the radiation protection and safety training and recognition processes. A medical radiation facility can adopt a ‘credentialing and privileging’ approach to cover education, training, qualification and competence in radiation protection and safety [36]. In this approach, the prospective radiological medical practitioner would present all their relevant data on training and experience (including in radiation protection and safety), and apply for permission to perform certain medical procedures involving radiological procedures. Detailed guidance on appropriate education and training in radiation protection and safety for various specialties involved in medical use of ionizing radiation is given in Refs [37, 38].
|
| Medical radiation technologists |
2.126. |
The programme of education and training in medical radiation technology usually includes significant components of radiation protection (patient protection and occupational protection). On completion of the programme, the medical radiation technologist would typically become registered with the national registration board (or a body with a similar function), and his or her competence in medical radiation technology should include competence in radiation protection and safety. |
| Medical radiation technologists |
2.127. |
Medical radiation technologists may be specialized in various fields and subfields. The approach to specialties and subspecialties vary significantly among States. In many States, the medical radiation technologist undergoes a programme of education and training specific to diagnostic radiology, nuclear medicine or radiation therapy and hence his or her competence would be in that specialty only. Within these specialties, there may be specific subspecialties for which the general programme of education and training does not necessarily confer competence. For example, the diagnostic radiology programme in a State might not cover CT or image guided interventional procedures to the depth needed for competence. Additional education and training should be arranged to achieve competency in the subspecialty. The regulatory body, in terms of reviewing an application for an authorization and during its periodic inspections, needs to be aware of issues of specialization and subspecialization and ensure that only persons with the correct credentials can work in the particular roles. Similarly, the registrant or licensee should ensure that only persons that have the requisite competence are employed. |
| Medical physicists |
2.128. |
Even though the International Labour Organization has stated that medical physicists working in clinical practice can be considered health professionals [39], medical physicists are not well recognized as a specialist group of health professionals. In some States, there are well established processes for education, training and qualification and achieving competence in medical physics, with academic training in medical physics at a university (typically a postgraduate programme), clinical training in a hospital or facility, and finally an assessment of competence. In some States, the professional body administers this whole process, with approved universities for the academic component, approved hospitals or facilities for the clinical placement, and a professional standards board for the competence assessment. More details on education, training, qualification and competence of medical physicists is given by the IAEA [26, 40–43]. There are also national and regional requirements and guidance on education, training and recognition of medical physics experts [44]. GSR Part 3 [3] requires specialization for the medical physicist, so, for example, a medical physicist with competence only in diagnostic radiology or image guided interventional procedures cannot act in the role of a medical physicist in radiation therapy, and vice versa. |
| Medical physicists |
2.129. |
It is more difficult where either the State does not recognize medical physics as a distinct health profession or where there is no infrastructure in place for the education and training of medical physicists. In both cases, there is likely to be little in the way of infrastructure for medical physics in the State. The problem is similar to that described in the second half of para. 2.124 for radiological medical practitioners. The assessment of education, training, qualification and competence of a person seeking to act in the role of a medical physicist should still take place. Regardless of the educational process, the final competence assessment for medical physicists should be specialty specific, as required by para. 3.150 of GSR Part 3 [3]. |
| Radiopharmacists |
2.130. |
A radiopharmacist is a health professional, usually a pharmacist, who has received additional specialist education and training, and has competency in the preparation and dispensing of radiopharmaceuticals. Postgraduate courses in radiopharmacy are available in some States. A few States have a radiopharmacy professional body, or a radiopharmacy can be a specialist subgroup within the national nuclear medicine professional body or a pharmacy professional body. More details on education, training, qualification and competence of persons working in a radiopharmacy are given in Ref. [45]. Even in the absence of a formal infrastructure, the assessment of education, training, qualification and competence of a person seeking to act in the role of a radiopharmacist should still take place. |
| Other health professionals in the medical radiation facility |
2.131. |
Other health professionals are involved in the medical uses of ionizing radiation. However, a distinction should be made between those who have specific responsibilities for patient radiation protection and those whose responsibilities (in terms of radiation protection) are for occupational radiation protection only. A health professional who falls into the former group, and who is not a radiological medical practitioner, a medical radiation technologist, a medical physicist or a radiopharmacist, should still have appropriate specialization (as it applies to the particular use of radiation) and the respective radiation protection and safety education, training, qualification and competence. The guidance given in paras 2.124, 2.127, 2.129 and 2.130 for health professionals in States where infrastructure is lacking would again be applicable. |
| Other health professionals in the medical radiation facility |
2.132. |
The latter group of health professionals and other professionals involved in medical uses of ionizing radiation includes specialist nurses (working in a cardiac investigation suite or theatre), specialist physicians (such as anaesthetists providing support to a patient undergoing an interventional procedure), biomedical engineers, clinical engineers and radiochemists providing support to the performance of the radiological procedure, either directly or indirectly. All these persons should have formal education and training on radiation protection. An example of such training for radiation oncology nurses is given in Ref. [46]. |
| Referring medical practitioners |
2.133. |
The referring medical practitioner has a crucial role in the justification of a given radiological procedure for a given patient. The referring medical practitioner will be more effective in this role if he or she has a good understanding of radiation protection and safety as it applies to medical uses of ionizing radiation. Formal processes to require such education and training under a radiation protection and safety framework are difficult to put in place. Instead, a more general approach may be adopted of promoting education and training in radiation protection and safety as part of the general medicine degree curriculum, especially at the time when clinical rotations begin, or as part of the corresponding specialty education and training programme. |
| Radiation protection officers |
2.134. |
The RPO should be competent in radiation protection and safety matters with respect to occupational and public radiation protection, relevant for given medical uses of ionizing radiation. The RPO’s technical expertise could come from a range of backgrounds, often in science, engineering or health. The additional education and training required for the RPO role will depend on the complexity of the technology and practice of the medical radiation facility. In some facilities, the RPO may lead a team, all of whom should have the requisite education and training. Similar to other health professionals, in the absence of a process for recognition by a third party, the regulatory body should liaise with the relevant professional body (if it exists) to set standards to enable assessment of persons seeking authorization to act in the role of RPO. The International Labour Organization recognizes the radiation protection expert as an “environmental and occupational health and hygiene professional” [39]. |
| Suppliers, installation, maintenance and servicing personnel |
2.135. |
Persons who work as engineers or technicians for the supply, installation, maintenance and servicing of radiological medical equipment and software should be qualified and competent in such work. Often, they will have been trained by their employer specifically for this role. Another aspect of their training should be in the area of radiation protection and safety, not only for their own occupational radiation protection and radiation protection of the staff of the medical radiation facility where they are working, but they should also have a good working knowledge of patient radiation protection in the context of the types of medical radiological equipment and software they are servicing. For the latter, this particularly includes understanding the radiation protection and safety implications of the various features of the equipment or software, and how that changes when the features undergo adjustments or revisions. Regulatory control of servicing engineers and technicians varies around the world. In some States, a licence may be required to perform servicing and a prerequisite to obtaining such a licence should be that such engineers or technicians have had appropriate radiation protection and safety training. |
| Maintaining competence |
2.136. |
Paragraphs 2.119–2.133 provide guidance on the processes for the initial education, training, qualification and competence assessment of health professionals. Health professionals should maintain their core competencies, including radiation protection and safety, and should keep abreast of new developments in medical uses of radiation. One way to achieve this is through formal continuing medical education or continuing professional development programmes. In many States, the professional bodies administer such programmes, and maintenance of certification of competence in a specialty is dependent on satisfactory participation in the programme. Registrants, licensees and the regulatory body can use these programmes as evidence of continuing competence. |
| Specific training on equipment and software |
2.137. |
Specific training should take place using the actual medical radiological equipment and software used in the medical radiation facility. This applies in particular to radiological medical practitioners and the medical radiation technologists, who work directly with the equipment and software during radiological procedures, and the medical physicist. They should understand how the equipment and software function, including the available options and how to customize these, and their implications for patient radiation protection. Practical training should take place in the medical radiation facility when new equipment or software is installed and when significant modifications are made (see also paras 2.104 and 2.108). From the vendors’ side, the servicing engineer, the applications specialist and the IT specialist have a role in providing specific training for the medical radiation facility. It is important to ensure that equipment and software specific training is given in a manner that can be readily understood by local staff. |
| Specific training on equipment and software |
2.138. |
The use of radiation in medicine is just one aspect of medical practice. The application of the radiation protection and safety requirements of GSR Part 3 [3] should complement the wider set of requirements that ensure good medical practice. In particular, the medical radiation facility and its management should ensure complementarity between the requirements for radiation protection and safety and other health care delivery requirements within the medical facility. This is achieved through an appropriate management structure and management system. |
| Specific training on equipment and software |
2.139. |
Requirement 5 of GSR Part 3 [3] establishes a specific requirement for radiation protection and safety to be effectively integrated into the overall management system of a given organization. In this Safety Guide, this applies to the medical radiation facility. Paragraphs 2.47–2.52 of GSR Part 3 [3] establish additional detailed requirements on the protection and safety elements of the management system, for promoting a safety culture and for taking into account human factors. Further detailed requirements for facilities and activities in general are established in IAEA Safety Standards Series No. GSR Part 2, Leadership and Management for Safety [47], and elaborated in GS-G-3.1 [25]. The requirements for quality management are established in those safety standards and will not be discussed further in this Safety Guide, other than to emphasize that effective management for radiation protection and safety requires commitment from the highest level of management in the medical radiation facility, including the provision of all the required resources. The guidance in paras 2.140–2.149 is limited to a few particular components of the management system relating to radiation protection and safety. |
| Specific training on equipment and software |
2.140. |
Paragraphs 2.42 and 2.43 of GSR Part 3 [3] establish a requirement for a “protection and safety programme”, in general, and Requirement 24 of GSRPart 3 [3] establishes arrangements under a “radiation protection programme” specifically for occupational exposure. In addition, paras 3.170–3.172 of GSR Part 3 [3] establish requirements for a “comprehensive programme of quality assurance for medical exposures”. All three of these programmes should be part of the overall management system of the medical radiation facility. Detailed guidance on the radiation protection programme for occupational exposure and the programme of quality assurance for medical exposures is given in Sections 3–5.
|
| Specific training on equipment and software |
2.141. |
Depending on the size of the medical radiation facility, committees might be formed to help the implementation of the aspects of the management system pertaining to the radiation protection and safety programme. One such committee might be a radiation safety committee, with the function of advising on safe operation and compliance with radiation protection and safety regulatory requirements. The members of the committee should be at the senior level and would typically include an administrator representing the management, a radiological medical practitioner, a medical radiation technologist, a medical physicist and the RPO. The RPO should carry out day to day oversight of the radiation protection programme and should report to the radiation safety committee. The licensee should ensure that the RPO is provided with the resources required to oversee the programme, as well as the authority to communicate with the committee on a periodic basis. The RPO should be able to communicate directly with the licensee, and with the regulatory body as needed, such as in the case of breaches of compliance that may compromise safety. |
| Specific training on equipment and software |
2.142. |
Another committee might be a quality assurance committee, with oversight of the programme of quality assurance for medical exposures within the medical radiation facility. The committee would determine policy and give direction to the programme, ensure proper documentation is being maintained and review the effectiveness of the programme. The radiation safety committee and the quality assurance committee have some functions in common, especially with regard to medical exposure, and the representation of health professionals on each is likely to be the same. The work of both committees should be harmonized to avoid either the duplication or the inadvertent omission of some functions. |
| Specific training on equipment and software |
2.143. |
The management system should promote continuous improvement, which implies a commitment by staff to strive for continuous improvement in medical uses of ionizing radiation. Feedback from operational experience and from lessons identified from accidental exposures or near misses should be applied systematically, as part of the process of continuous improvement. |
| Specific training on equipment and software |
2.144. |
Paragraph 2.50 of GSR Part 3 [3] requires that the medical radiation facility “be able to demonstrate the effective fulfilment of the requirements for protection and safety in the management system.” This will include monitoring, performed to verify compliance with the requirements for protection and safety (Requirement 14 and paras 3.37 and 3.38 of GSR Part 3 [3]). |
| Specific training on equipment and software |
2.145. |
There are requirements for records to be kept, and made available as needed, in many sections of GSR Part 3 [3]. The management system of the medical radiation facility should provide for such record keeping and access. Details on what should be provided are described in Sections 3–5. |
| Specific training on equipment and software |
2.146. |
Digital information systems are becoming increasingly available to provide various support functions to the management system of the medical radiation facility, including the handling of requests for radiological procedures, the scheduling of radiological procedures, the tracking of patients, and the processing, storage and transmission of information pertaining to the patient. Furthermore, digital information systems can be used for viewing imaging studies and obtaining reports of study interpretations. Example of systems with some or all of these functions include picture archiving and communication systems (PACSs), radiology information systems (RISs), HISs, electronic health records (EHRs) and any other commercially available dose management systems. These systems should operate independently, but they can also interconnect with each other. Imaging devices and other medical radiological equipment can be interconnected by computer networks and can exchange information in accordance with standards such as the Transmission Control Protocol/Internet Protocol (TCP/IP or the Internet protocol suite), Digital Imaging and Communication in Medicine (DICOM), Health Level Seven (HL7) and Integrating the Healthcare Enterprise (IHE). These information systems are complex, and users should ensure that they are expertly implemented and supported. Digital information systems when used appropriately can have a positive effect on the practice of radiation protection and safety in medical uses of ionizing radiation. For example, use of these systems can help to avoid the performance of unnecessary or inappropriate studies and repeat studies by making patient information available to multiple users. Furthermore, connected digital systems should minimize the need for multiple manual data entry, with its associated risks, such as in radiation therapy. These systems can also help in monitoring doses to patients and image receptors, and monitoring image retakes; the information from such monitoring can help in the optimization of protection and safety for imaging procedures. |
| Specific training on equipment and software |
2.147. |
Such digital information systems and the procedures for their use should be designed to protect against data loss, which in the context of the medical radiation facility might compromise radiation protection and safety by, for example, necessitating repeat examinations. It is the responsibility of the medical radiation facility to meet the requirements of the relevant State authorities for the retention, security, privacy and retrieval of records. |
| Specific training on equipment and software |
2.148. |
The management system should include a review cycle. The general principles for audits and reviews are well established (see GS-G-3.1 [25] and GSR Part 2 [47]). For a medical radiation facility, a possible tool for this is the clinical audit. Clinical audits can be considered as a systematic and critical analysis of the quality of clinical care, including the procedures used for diagnosis and treatment, the associated use of resources and the effect of care on the outcome and quality of life for the patient. A clinical audit looks beyond a strict radiation protection and safety focus, and seeks to assess the quality and efficacy of the medical practice offered in the facility, ultimately the patient health outcome. This should include the radiation protection and safety aspects of medical uses of ionizing radiation and, importantly, should keep these aspects in the context of medical practice, ensuring a common goal. Thus, while GSR Part 3 [3] does not require a clinical audit, its use can be seen as fulfilling both the radiation protection and safety and the medical aspects of the medical radiation facility’s management system. More detailed guidance on clinical audits is given in Refs [48–50]. |
| Specific training on equipment and software |
2.149. |
GSR Part 3 [3], in the context of medical exposure, requires the performance of a radiological review and this should be incorporated into the medical radiation facility’s management system (see para. 3.182 of GSR Part 3 [3]). At its simplest, the radiological review includes an investigation and critical review of the current practical application of the requirements for justification and optimization of radiation protection and safety for the radiological procedures that are being performed in the medical radiation facility. The radiological review involves at least the radiological medical practitioners, the medical radiation technologists and the medical physicists at the medical radiation facility. |
| Specific training on equipment and software |
2.150. |
In the context of medical uses of ionizing radiation, a safety assessment means an assessment of all relevant aspects of radiation protection and safety for a medical radiation facility, including the siting, design and operation of the facility. The safety assessment can occur before a facility is operational or when a major change in operation is contemplated. As noted in para. 2.70, the regulatory body has the responsibility to establish requirements for safety assessments and, once the safety assessment has been submitted, to review and evaluate it prior to granting an authorization (see Requirement 13 and para. 3.29 of GSR Part 3 [3]). |
| Specific training on equipment and software |
2.151. |
Paragraphs 3.30–3.35 of GSR Part 3 [3] establish requirements on what a safety assessment is to include, what the registrant or licensee is to take into account, its documentation and placement in the management system, and when additional reviews of the safety assessment are to take place. More detailed requirements on safety assessment (for all facilities and activities) are given in IAEA Safety Standards Series No. GSR Part 4 (Rev. 1), Safety Assessment for Facilities and Activities [51]. For medical radiation facilities, the safety assessment should include not only considerations of occupational and public exposure but also medical exposure and the possibility of unintended or accidental medical exposures. |
| Specific training on equipment and software |
2.152. |
GSR Part 3 [3] specifies two types of safety assessment: generic and specific to the practice or source. A generic safety assessment is usually sufficient for types of source with a high degree of uniformity in design. A specific safety assessment is usually required in other cases; however, the specific safety assessment need not include those aspects covered by a generic safety assessment if a generic safety assessment has been conducted for the source. The safety assessments for medical uses of ionizing radiation will range in complexity, but even if the source itself is covered by a generic safety assessment, its placement in the medical radiation facility will nearly always require some form of specific safety assessment. It is very useful if the regulatory body develops a set of templates to be used by medical radiation facilities for safety assessments for the various modalities and specialties in medical uses of ionizing radiation [13, 51]. |
| Specific training on equipment and software |
2.153. |
GSR Part 3 [3] requires that potential exposure be considered in the safety assessment of a new facility being planned or a planned modification to an existing facility. Potential exposure refers to prospective exposure that might occur, but could result from an accident or from an event or a sequence of events that might occur. As stated in Requirement 15 of GSR Part 3 [3]: “Registrants and licensees…shall take all practicable measures to prevent accidents and to mitigate the consequences of those accidents that do occur.” |
| Specific training on equipment and software |
2.154. |
Paragraph 3.43 of GSR Part 3 [3] states that: |
| Specific training on equipment and software |
3.1. |
This section covers radiographic and fluoroscopic diagnostic procedures, image guided interventional procedures, and imaging studies using X ray radiation that are part of the processes of radiation therapy or nuclear medicine. These radiological procedures usually take place in facilities that are in a fixed location, but they can also take place in mobile facilities. |
| Specific training on equipment and software |
3.2. |
The radiographic procedures aim to image or quantify a particular organ or tissue in two, three or four dimensions, and include general radiography, CT, CBCT, mammography, tomosynthesis, dental radiography (intraoral, panoramic and CBCT) and bone densitometry (DXA). |
| Specific training on equipment and software |
3.3. |
Fluoroscopic diagnostic procedures aim to provide real time assessment of the anatomy and pathology of a system or organ. Examples include cardiac, gastrointestinal, urological and gynaecological examinations. |
| Specific training on equipment and software |
3.4. |
During image guided interventional procedures, fluoroscopy (primarily) or CT is used as an imaging tool to facilitate the diagnosis and treatment of vascular and non-vascular diseases. Examples of vascular procedures include coronary angiography or angioplasty, uterine artery embolization, aortic valve implantation and aortic endografts. Common non-vascular procedures include, for example, biliary drainage or stenting, and injecting cytostatic agents into the liver. Fluoroscopically guided intraoperative procedures include, for example, intramedullary nailing and vertebroplasty. Some image guided interventional procedures involve the use of sealed or unsealed radiation sources, for example in intracoronary radiation therapy to prevent coronary artery restenosis. |
| Specific training on equipment and software |
3.5. |
The generic term medical radiation facility is used widely in Section 2 to mean any medical facility where radiological procedures are performed. In Section 3, the narrower term radiology facility is used to cover any medical radiation facility where diagnostic radiology and/or image guided interventional procedures are performed. Radiology facilities include: a traditional radiology department in a hospital or medical centre; a stand alone X ray imaging facility; an interventional cardiology (or other specialty) department, unit or facility, either stand alone or as part of a larger entity; and a dental practice. |
| Specific training on equipment and software |
3.6. |
Different health professionals can take on the role of the radiological medical practitioner (see para. 2.90) in diagnostic radiology and image guided interventional procedures, depending, inter alia, on national laws and regulations. They typically include radiologists, cardiologists, orthopaedic surgeons, neurosurgeons, plastic surgeons, vascular surgeons, gastroenterologists, urologists, respiratory and other specialist physicians and surgeons, dentists, chiropractors, osteopaths and podiatrists. |
| Specific training on equipment and software |
3.7. |
As stated in para. 2.92, the term ‘medical radiation technologist’ is used in GSR Part 3 [3] and this Safety Guide as a generic term for the health professional known by several different terms in different States; such terms include radiographer, radiological technologist and others. Clearly, each State will use its own term in its own jurisdiction. |
| Specific training on equipment and software |
3.8. |
Section 2 of this Safety Guide provides general guidance on the framework for radiation protection and safety in medical uses of radiation, including roles and responsibilities, education, training, qualification and competence, and the management system for protection and safety. This guidance is relevant to diagnostic radiology and image guided interventional procedures, and reference to Section 2 should be made as necessary. |
| Fixed facilities: Design of X ray rooms |
3.9. |
Paragraph 3.51 of GSR Part 3 [3] establishes the broad requirements to be met when choosing a location to use a radiation generator, and these are relevant to the design of a radiology facility. Provisions for the incorporation of radiation protection and safety features are best made at the facility design stage (e.g. for X ray rooms and other related rooms). The siting and layout should take into account the types of radiological procedure, workload and patient flow, both within the radiology facility and, in cases where the radiology facility is part of a larger hospital or medical centre, within other departments of the facility. Guidance on setting up diagnostic radiology and interventional radiology facilities is given in Refs [52–55]. |
| Fixed facilities: Design of X ray rooms |
3.10. |
The three factors relevant to dose reduction (time, distance and shielding) should be combined in the design to optimize occupational radiation protection and public radiation protection. Larger rooms are preferable to allow easy access for patients on bed trolleys. At the same time, they allow for easier patient positioning and facilitate both equipment and patient movement during the procedure, which, in the case of fluoroscopy and image guided interventional procedures, helps to reduce time and exposure. Larger rooms will also reduce the levels of secondary radiation (due to scattering and leakage) potentially reaching areas occupied by staff and public areas, typically reducing the level of shielding required. |
| Fixed facilities: Design of X ray rooms |
3.11. |
Shielding requirements should be tailored to meet any national requirements and to suit the practice requirements based on the intended patient workload and the types of examination to be performed. Further assessments should be undertaken when the intended use of a room changes, X ray equipment is upgraded, underlying procedures or patient workload changes, or the surrounding room occupancy is altered. |
| Fixed facilities: Design of X ray rooms |
3.12. |
At the design stage, the use of both structural and ancillary protective barriers to provide shielding should be considered. In rooms using fluoroscopy with staff working close to the patients, such as rooms for image guided interventional procedures, ceiling mounted protective screens and table mounted leaded curtains should be installed. Such ancillary protective barriers for image guided interventional procedures should be part of the initial facility plan, and should be designed so as not to interfere with the medical procedure (e.g. sterility requirements). Wall shielding should be at least 2 m high, and any doors and viewing windows in walls or doors should have at least the same lead equivalence as the minimum shielding specifications for the shielded wall or barrier in which they are located. Due consideration should be given to the provision of floor and ceiling shielding when rooms immediately below and above the X ray installation are occupied. All penetrations and joints in shielding should be arranged so that they are equally as effective in shielding radiation. More details with respect to structural shielding are given in paras 3.18–3.24. |
| Fixed facilities: Design of X ray rooms |
3.13. |
General safety features of radiography, mammography, CT and fluoroscopy rooms include the following: A barrier should be placed at the control console to shield staff to the extent that they do not need to wear protective clothing while at the console. This is particularly important in mammography, where structural shielding in walls, ceiling and floor might not be deemed necessary.
In radiography, all possible intended directions of the X ray beam should be taken into consideration in the room design so that the X ray beam cannot be directed at any area that is not shielded and which could lead to potentially unacceptable doses being received in this area.
The doors should provide protective shielding for secondary radiation and should be shut when the X ray beam is on. In radiography, the X ray room should be designed so as to avoid the direct incidence of the X ray beam on the access doors.
The medical radiation technologist should be able to clearly observe and communicate with the patient at all times during an X ray diagnostic procedure.
|
| Fixed facilities: Design of X ray rooms |
3.14. |
Signs and warning lights, preferably positioned at eye level, should be used at the entrances of controlled areas and supervised areas to prevent inadvertent entry (see also paras 3.279 and 3.280 on control of access). For controlled areas, para. 3.90(c) of GSR Part 3 [3] requires the use of the basic ionizing radiation symbol recommended by the International Organization for Standardization (ISO) [56]. The signs should be clear and easily understandable. Warning lights, such as illuminated or flashing signs, as appropriate, should be activated when radiation is being produced inside the controlled area or supervised area. Door interlocks are not appropriate in X ray diagnostic radiological procedures because if the X ray beam is stopped, the medical procedure may have to be repeated. |
| Fixed facilities: Design of X ray rooms |
3.15. |
A stable power supply should be available. An emergency diesel power generator might not be sufficiently stable to power a CT or interventional radiology suite and should not be relied upon. An uninterruptible power supply or battery backup systems should be installed to capture the active information at the time of the outage and to shut down all software in a controlled manner. Servers should be programmed to shut down automatically when the power supply is interrupted. |
| Fixed facilities: Design of X ray rooms |
3.16. |
The design of the facility should include an air conditioning system sufficient to maintain the temperature in the examination room (and sometimes in areas with computer equipment and detectors) within the parameters defined by the equipment manufacturers, but consistent with health and safety requirements for temperature and humidity. |
| Mobile facilities |
3.17. |
Mammography and CT vans are commonly used in areas where fixed facilities are not available. Other modalities may also be offered via a mobile facility. General safety features of mobile facilities include the following: Mobile facilities should be built so that protection is optimized mainly through shielding (in all relevant directions during use), as providing protection through distance is often limited and exposure time is determined by the procedure being performed.
An appropriate power supply should be available with reliable connections.
Entrance to the mobile facility should be under the control of the mobile facility personnel.
Waiting areas, if they exist, should be appropriately shielded to afford levels of protection consistent with public exposure limits. Waiting areas are common for mobile mammography facilities but not for mobile CT facilities.
To facilitate the imaging procedure, including patient flow, mobile CT facilities are usually operated adjacent to a hospital or clinic, from where they can draw water and electricity, and where patients can use the toilets, waiting rooms and changing rooms and have access to physician offices. Similarly, mobile mammography facilities may also utilize hospital or clinic facilities.
|
| Shielding calculations |
3.18. |
Two widely used methodologies for shielding calculations are given in Refs [57, 58], but other methodologies are also available and used (e.g. see Refs [55, 59]), as well as specific shielding calculations for the WHIS-RAD X ray unit [60]. The nominal design dose in an occupied area is derived by the process of constrained optimization (i.e. selection of a source related dose constraint), with the condition that each individual dose from all relevant sources is well below the dose limit for a person occupying the area to be shielded. Nominal design doses are levels of air kerma used in the design calculations and evaluation of barriers for the protection of individuals, at a reference point beyond the barrier. Specifications for shielding are calculated on the basis of the attenuation that the shielding needs to provide to ensure that the nominal design doses are met. |
| Shielding calculations |
3.19. |
The shielding thickness is obtained from the attenuation factor required to reduce the dose that would be received by staff and the public if shielding were not present to a dose value considered acceptable. This nominal design dose should be derived by a process of optimization: The dose that would be received without shielding is calculated by using workload values, use factors for a given beam direction (the fraction of the total amount of radiation emitted in that direction) and occupancy factors (the fraction of the total exposure that will actually affect individuals at a place, by virtue of the time spent by an individual in that place). For secondary barriers, the use factor is always unity, since scatter and leakage radiation is propagated in all directions all the time. If tabulated figures are used, care should be taken that they reflect the actual usage in the facility and not generic national scenarios. Potential changes in practice and increases in workload should be considered as part of the calculations.
Once the dose that would be received without shielding is known, attenuation should be calculated to reduce this dose to a design level that meets national regulations and that can be considered optimized protection; that is, a dose below which additional cost and effort in shielding is not warranted by the dose being averted. This may require successive calculations to determine where this level lies.
|
| Shielding calculations |
3.20. |
When a shielding methodology is applied to optimize occupational and public radiation protection, decisions will need to be made about many factors that can greatly influence the final results for the shielding specification. Those decisions may be based on conservative assumptions, which together may lead to an unduly over-conservative specification of the shielding. Realistic assumptions should be used as much as possible, with some allowance for future changes in use. Adequacy of the shielding specification should be ensured as corrective actions after building has been completed will invariably be difficult and expensive. Furthermore, it is likely that the building materials used to provide the shielding will be supplied in specific discrete thicknesses or densities and this can be used to provide a safety margin over the calculated shielding values. If a material other than lead is to be used, tabulated values should be used only for materials that match those being considered (in terms of their chemical composition, density and homogeneity) as closely as possible. The following are some assumptions that would each lead to conservatism in the shielding specification: For primary barriers, the attenuation by the patient and image receptor is not considered.
Workload, use and occupancy factors are overestimated.
Staff members are always in the most exposed place of the room.
Distances are always the minimum possible.
Leakage radiation is the maximum all the time.
Field sizes used for the calculation of scatter radiation are overestimated.
Attenuation of the materials is usually considered for the maximum beam quality used.
The numerical value of calculated air kerma (in mGy) is directly compared with dose limits or dose constraints (in mSv), which are given in terms of effective dose. However, the actual effective dose to personnel or members of the public is substantially lower than the air kerma, given the dose distribution within the body for the beam qualities used in diagnostic and interventional radiology.
|
| Shielding calculations |
3.21. |
Particular attention should be given to hybrid imaging systems, where the shielding should be calculated for each modality and combined as appropriate [54, 61, 62] (see also paras 4.32–4.35). |
| Shielding calculations |
3.22. |
Consideration should be given in the design stage to making sure that radiosensitive equipment and consumables, for example computed radiography (CR) cassettes and X ray films, are appropriately shielded. Where used, darkrooms for film processing may require extra shielding to prevent film fogging |
| Shielding calculations |
3.23. |
Specification of shielding, including calculations, should be performed by a medical physicist or a qualified expert in radiation protection. In some States, there may be a requirement for shielding plans to be submitted to the regulatory body for review or approval prior to any construction (see also para. 2.74). |
| Shielding calculations |
3.24. |
The adequacy of the shielding should be verified, preferably during construction, and certainly before the room is placed in clinical use, and similarly after any future structural modifications. Clearly, requirements of the regulatory body should be met (para. 2.74). |
| Design of display and interpretation (reading) rooms |
3.25. |
To facilitate their interpretation by the radiological medical practitioner, images should be displayed in rooms specifically designed for such purposes. A low level of ambient light in the viewing room should be ensured (see also paras 3.45 and 3.46 on image display devices and view boxes). |
| Design of display and interpretation (reading) rooms |
3.26. |
Viewing rooms with workstations for viewing digital images should be ergonomically designed to facilitate image processing and manipulation so that reporting can be performed accurately. The viewing monitors of the workstations should meet applicable standards (see para. 3.46). |
| Medical radiological equipment, software and ancillary equipment |
3.27. |
This subsection considers medical radiological equipment, including its software, used in diagnostic radiology and image guided interventional procedures, including radiography, fluoroscopy and angiography, CT, CBCT, mammography, dental radiology, bone mineral densitometry (e.g. DXA) and tomography (including tomosynthesis). It is also applicable to the X ray based component of hybrid imaging modalities, including PET–CT, single photon emission computed tomography (SPECT)–CT, and PET–mammography, and the X ray based component of image guided radiation therapy (IGRT) systems. Some of this equipment might be used in a nuclear medicine facility or in a radiation therapy facility, rather than a radiology facility. |
| Medical radiological equipment, software and ancillary equipment |
3.28. |
The requirements for medical radiological equipment and its software are established in paras 3.49 and 3.162 of GSR Part 3 [3]. The International Electrotechnical Commission (IEC) has published international standards applicable to medical radiological equipment. Current IEC standards relevant to X ray imaging include Refs [63–103] (for those relevant to the radiopharmaceutical based component of hybrid imaging, see para. 4.41). It is recommended that the IEC web site be visited to view the most up to date list of standards. ISO publishes international standards applicable to medical radiological equipment. It is recommended that the ISO web site be visited to view the most up to date list of standards. |
| Medical radiological equipment, software and ancillary equipment |
3.29. |
As licensees take responsibility for the radiation safety of medical radiological equipment they use, they should impose purchasing specifications that include conditions to meet relevant international standards of the IEC and ISO or equivalent national standards. In some States, there may be an agency with responsibilities for medical devices or a similar organization that gives type approval to particular makes and models of medical radiological equipment. |
| Medical radiological equipment, software and ancillary equipment |
3.30. |
Displays, gauges and instructions on operating consoles of medical radiological equipment, and accompanying instruction and safety manuals, might be used by staff who do not understand, or who have a poor understanding of, the manufacturer’s original language. In such cases, the accompanying documents should comply with IEC and ISO standards and should be translated into the local language or into a language acceptable to the local staff. The software should be designed so that it can be easily converted into the local language, resulting in displays, symbols and instructions that will be understood by the staff. The translations should be subject to a quality assurance process to ensure proper understanding and to avoid operating errors. The same applies to maintenance and service manuals and instructions for maintenance and service engineers and technicians who do not have an adequate understanding of the original language (see also paras 2.104 and 2.137). |
| Medical radiological equipment, software and ancillary equipment |
3.31. |
All medical radiological equipment should be supplied with all appropriate radiation protection tools as a default rather than as optional extras. This applies to both patient radiation protection and occupational radiation protection (see also para. 2.105). |
| Design features for medical radiological equipment |
3.32. |
The design of medical radiological equipment should be such that its performance is always reproducible, accurate and predictable, and that it has features that facilitate the appropriate personnel in meeting the requirement of para. 3.163(b) of GSR Part 3 [3] for operational optimization of patient protection, namely that it provides “Appropriate techniques and parameters to deliver a medical exposure of the patient that is the minimum necessary to fulfil the clinical purpose of the radiological procedure, with account taken of relevant norms of acceptable image quality….” Many design features contribute to the performance of medical radiological equipment and should be considered when purchasing such equipment (see paras 3.33–3.41). Further details on design features and performance standards of medical radiological equipment used in diagnostic radiology and image guided interventional procedures are given in Refs [67–74, 76, 78–83, 98–108] (see also paras 3.232–3.246 on quality assurance and acceptance testing, in particular para. 3.236). |
| Design features for medical radiological equipment |
3.33. |
General design features for medical radiological equipment used in diagnostic radiology and image guided interventional procedures should include the following:Means to detect immediately any malfunction of a single component of the system that may lead to an inadvertent underexposure or overexposure of the patient or exposure of staff so that the risk of any unintended or accidental medical exposure is minimized.
Means to minimize the frequency of human error and its impact on the delivery of unintended or accidental medical exposure.
Hardware and software controls that minimize the likelihood of unintended or accidental medical exposures.
Operating parameters for radiation generators, such as the generating tube potential, filtration, focal spot position and size, source to image receptor distance, field size indication and either tube current and time or their product, that are clearly and accurately shown.
Radiation beam control mechanisms, including devices that indicate clearly (visually and/or audibly) and in a fail-safe manner when the beam is on.
X ray tubes with inherent and added filtration adequate to remove low energy components of the X ray beam which do not provide diagnostic information.
Collimating devices to define the radiation beam; in the case of a light beam diaphragm, the light field should align with the radiation field.
With the exception of mammography, dental X ray and CT equipment, diagnostic and interventional X ray equipment that is fitted with continuously adjustable beam collimating devices. Such devices allow the operator to limit the area being imaged to the size of the selected image receptor or the region of interest, whichever is the smaller.
When preset protocols are provided, technique factors that are readily accessible and modifiable by adequately trained personnel.
Design of the X ray tube to keep radiation leakage as low as reasonably achievable and not exceeding 1 mGy in an hour measured at 1 m from the focal spot, and less than maximum levels specified in international standards or in local regulations.
|
| Design features for medical radiological equipment |
3.34. |
Specific design features for medical radiological equipment used in radiography should include the following: The provision of devices that automatically terminate the irradiation after a preset time, tube current–exposure time product, or dose to the automatic exposure control (AEC) detector, or when the ‘dead man’ hand switch is released.
The incorporation of AEC systems in radiographic units, where practicable. Such AEC systems should be able to compensate for energy dependence, patient thickness and dose rate, for the expected range of clinical imaging conditions, and should be suited to the type of image receptor being used, whether film–screen or digital.
Indications or displays of the air kerma–area product and/or incident air kerma.
|
| Design features for medical radiological equipment |
3.35. |
Specific design features for medical radiological equipment used for dental radiography should include the following: A minimum tube potential of 60 kVp;
For intraoral dental systems, an open-ended (preferably rectangular) collimator providing a focus to skin distance of at least 20 cm and a field size at the collimator end of no more than 4 cm × 5 cm if rectangular or 6 cm in diameter if cylindrical, and limitation of field size to the dimensions of the image receptor;
For panoramic dental systems, limitation of field size to the area required for diagnosis by means of programmed field size trimming and the ‘child imaging mode’;
For dental CBCT, adjustable X ray tube potential and tube current–exposure time product, and a choice of volume sizes and voxel sizes.
|
| Design features for medical radiological equipment |
3.36. |
Specific design features for medical radiological equipment used for CT should include the following: Console display of all CT parameters that directly influence the image acquisition (these can be displayed over a number of screens);
Console display of estimated volume CT air kerma index and CT air kerma–length product for the procedure or image acquisition;
Operator alert if exposure factors are set too high (usually expressed in terms of the volume CT air kerma index and/or the CT air kerma–length product);
Means for dose modulation (rotational and z-axis), and means for selection of noise index or equivalent;
A comprehensive range of beam widths and pitches and other ancillary devices (e.g. dynamic collimation) to ensure ‘over ranging’ in CT is kept as low as reasonably achievable by facilitating the appropriate choice of beam width and pitch to limit patient dose while maintaining diagnostic image quality;
Reconstruction algorithms that result in dose reduction without compromising image quality, such as iterative reconstruction algorithms;
A range of selectable tube potentials, tube current–exposure time products, and filters to facilitate the optimization of protocols, especially for children.
|
| Design features for medical radiological equipment |
3.37. |
Specific design features for medical radiological equipment used for mammography (both digital systems and film–screen systems) should include the following:
Various anode and filter combinations;
Compression and immobilization capabilities;
Magnification views;
Display on the console of a dose index, for example incident air kerma or mean glandular dose;
An image receptor or image receptors to accommodate all breast sizes.
|
| Design features for medical radiological equipment |
3.38. |
Specific design features for medical radiological equipment used for fluoroscopy should include the following: The provision of a device that energizes the X ray tube only when continuously depressed (such as an exposure foot switch or ‘dead man’ switch);
Indications or display (both at the control console and on monitors) of the elapsed time, air kerma–area product, and cumulative reference air kerma;
Automatic brightness control (ABC) or automatic dose rate control (ADRC);
Pulsed fluoroscopy and pulsed image acquisition modes;
The capture and display of the last acquired frame (last image hold);
Interlocks that prevent inadvertent energizing of the X ray beam when the image detector is removed from the imaging chain;
The capability to deactivate the exposure foot switch between cases;
The provision of a timer and an alarm that sounds at the end of a pre-set interval (typically 5 min).
|
| Design features for medical radiological equipment |
3.39. |
In addition to those listed in para. 3.38, design features for medical radiological equipment used for image guided interventional procedures should include the following: X ray tubes that have high heat capacities to enable operation at high tube currents and short times.
A radiation generator with a capability of at least 80 kW.
A radiation generator with a large dynamic range of tube current and tube potential (to minimize the pulse width necessary to accommodate differences in patient attenuation).
For paediatric work:
A radiation generator that supports an X ray tube with a minimum of three focal spots;
An anti-scatter grid that is removable;
An image acquisition frame rate that extends up to at least 60 frames per second for small children.
A real time display of air kerma–area product and cumulative reference air kerma.
Imaging detectors that allow different fields of view (magnification) to improve spatial resolution.
Automatic collimation.
Dual-shape collimators incorporating both circular and elliptical shutters to be used to modify the field for collimation along cardiac contours.
System specific variable filtration in the X ray beam that is applied according to patient attenuation (often as part of the ADRC system).
Selectable dose per pulse and selectable number of pulses per second.
Wedge filters that move automatically into the field of view to attenuate the beam in areas where there is no tissue and thus no need for imaging.
Possible means for manipulation of diaphragms while in ‘last image hold’.
The option of the automatic display of the last acquired image run.
Display and recording in a dose report in digital format of the following parameters:
Reference air kerma rate;
Cumulative reference air kerma;
Cumulative air kerma–area product;
Cumulative time of fluoroscopy;
Cumulative number of image acquisitions (acquisition runs and frames per run);
Integrated reference air kerma;
Option for digital subtraction angiography;
Road mapping, which is a technique used for navigation of the catheter or wire in endovascular procedures.
|
| Design features for medical radiological equipment |
3.40. |
All digital medical radiological equipment should have the following additional features: Real time dose display and end-of-case dose report (radiation dose structured report, DICOM object), including export of dose metrics for the purpose of DRLs and individual patient dose calculation;
Connectivity to RIS and to PACS.
|
| Design features for medical radiological equipment |
3.41. |
For medical radiological equipment used for performing diagnostic and interventional radiology procedures on children, there should be additional design features that both facilitate successful radiological procedures on patients who may be uncooperative and suit the imaging of very small patients. Such features include the following: Capability of very short exposure times for radiography;
Specifically designed AEC systems;
Provision of ‘paediatric modes’ for the automatic brightness and/or dose rate control systems in fluoroscopy and image guided interventional procedures;
Paediatric protocols for CT;
Child imaging mode for dental panoramic and CBCT equipment.
|
| Other equipment |
3.42. |
For radiology facilities where film is being used as an image receptor, film processing plays a crucial role in ensuring the medical exposure results in an acceptable diagnostic image. Automatic film processors should meet appropriate standards. Film–screen based mammography should have dedicated film processors with extended processing cycles. If manual processing is being performed, specially designed developer, fixer and washing tanks should be used, with processing times based on the developer temperature. The darkroom for processing should meet relevant international and national standards for light tightness and should be equipped with an appropriately filtered safe-light, compatible with the film being used. Further details are given in Refs [79, 109–114]. |
| Other equipment |
3.43. |
For radiology facilities where film is the medium from which the image is read (e.g. a printed digital image), the printing process plays a crucial role in ensuring the medical exposure delivered results in a diagnostic image. The resolution of the printer should not be less than the resolution of the detector, so that the image quality of the final image is not limited or compromised. |
| Other equipment |
3.44. |
The characteristics of image receptors (film–screen, phosphor plates for CR or flat detectors for digital radiography (DR)) should be appropriate for the diagnostic imaging task. For example, high resolution is needed for breast imaging, and high sensitivity detectors are needed for paediatric imaging. |
| Other equipment |
3.45. |
View boxes, for viewing films, should have sufficient uniform brightness to facilitate diagnosis, and the colour of view boxes should be matched through the complete set of view boxes. Means should be available (masks) to restrict the illuminated area of the radiograph to avoid dazzling. View boxes used for mammography should have higher luminance. Detailed guidance is given in Refs[109–114] (see paras 3.25 and 3.26 for guidance on display and interpretation rooms). |
| Other equipment |
3.46. |
All equipment used for digital image display should meet appropriate international and national standards, for example meeting the performance specifications in Ref. [115]. |
| Maintenance |
3.47. |
Paragraphs 3.15(i) and 3.41 of GSR Part 3 [3] establish requirements for maintenance to ensure that sources meet their design requirements for protection and safety throughout their lifetime and to prevent accidents as far as reasonably practicable. The registrant or licensee is required to ensure that adequate maintenance (preventive maintenance and corrective maintenance) is performed as necessary to ensure that medical radiological equipment retains, or improves through appropriate hardware and software upgrades, its design specifications for image quality and radiation protection and safety for its useful life. The registrant or licensee should, therefore, establish the necessary arrangements and coordination with the manufacturer or installer before initial operation and on an ongoing basis. |
| Maintenance |
3.48. |
All maintenance procedures should be included in the comprehensive programme of quality assurance and should be carried out at the frequency recommended by the manufacturer of the equipment and relevant professional bodies. Servicing should include a report describing the equipment fault, the work done and the parts replaced and adjustments made, which should be filed as part of the programme of quality assurance. A record of maintenance carried out should be kept for each item of equipment. This should include information on any defects found by users (a fault log), remedial actions taken (both interim repairs and subsequent repairs) and the results of testing before equipment is reintroduced to clinical use. |
| Maintenance |
3.49. |
In line with the guidance provided in para. 2.113, after any modifications or maintenance, the person responsible for maintenance should immediately inform the licensee of the medical radiation facility before the equipment is returned to clinical use. The person responsible for the use of the equipment, in conjunction with the medical physicist, the medical radiation technologist and other appropriate professionals, should decide whether quality control tests are needed with regard to radiation protection, including image quality, and whether changes to protocols are needed. |
| Maintenance |
3.50. |
The electrical safety and mechanical safety aspects of the medical radiological equipment are an important part of the maintenance programme, as these can have direct or indirect effects on radiation protection and safety. Authorized persons who understand the specifications of the medical radiological equipment should perform this work (see also paras 2.112–2.114). Electrical and mechanical maintenance should be included in the programme of quality assurance and should be performed, preferably by the manufacturer of the medical radiological equipment or an authorized agent, at a frequency recommended by the manufacturer. Servicing should include a written report describing the findings. These reports and follow-up corrective actions should be archived as part of the programme of quality assurance. |
| Maintenance |
3.51. |
In the diagnostic imaging procedures described in paras 3.1–3.4, occupationally exposed individuals are usually the medical radiation technologists and the radiological medical practitioners (e.g. including radiologists and, in dental practices, dentists operating X ray machines). In a trauma centre, other health professionals such as nurses, emergency department physicians and anaesthetists who may have to be present when portable or fixed X ray machines, including C-arm fluoroscopes, are used or who may have to be present in the CT room when the unit is operating may also be considered occupationally exposed. |
| Maintenance |
3.52. |
In image guided interventional procedures and during surgery, as described in para. 3.4, the occupationally exposed individuals are the radiological medical practitioners who perform the interventions (including, but not limited to, radiologists, cardiologists, vascular surgeons, orthopaedic surgeons, neurosurgeons, urologists, anaesthetists, respiratory physicians and gastroenterologists), medical radiation technologists and other health professionals who are present and part of the interventional team, including the anaesthetist, nurses, and technicians who monitor the physiological parameters of the patient. Some complex and lengthy procedures may require more than one interventionist. |
| Maintenance |
3.53. |
Additional occupationally exposed personnel may include medical physicists, biomedical, clinical and service engineers and some contractors, depending on their role. |
| Maintenance |
3.54. |
Other radiology facility workers, such as ward nurses, imaging staff who work exclusively with imaging modalities without ionizing radiation (ultrasound or magnetic resonance imaging (MRI)), patient porters, orderlies, assistants, cleaners and other service support personnel, for whom radiation sources are not required by, or directly related to, their work, are required to have the same level of protection as members of the public, as established in para. 3.78 of GSR Part 3 [3]. Consequently, the recommendations provided in paras 3.277–3.280 are also applicable in respect of such workers. Rules should be established for these workers, especially with regard to access to controlled areas and supervised areas. |
| Maintenance |
3.55. |
This subsection contains guidance very specific to diagnostic radiology and image guided interventional procedures. More general and comprehensive guidance on occupational radiation protection is given in GSG-7 [23], including guidance on radiation protection programmes, assessment of occupational exposure and providers of dosimetry services, applicable to all areas of radiation use (including non-medical uses). |
| Classification of areas |
3.56. |
Various areas and rooms in a radiology facility should be classified as controlled areas or supervised areas, in line with the requirements established in paras 3.88–3.92 of GSR Part 3 [3]. All other rooms and areas that are not so designated are considered as being in the public domain, and levels of radiation in these areas should be low enough to ensure compliance with the dose limits for public exposure. Paragraphs 3.57–3.59 give general guidance, and it would be expected that final decisions by the licensee for a given medical radiation facility would be based on the expert advice of the medical physicist, a qualified expert in radiation protection or the RPO. |
| Classification of areas |
3.57. |
All X ray rooms should be designated as controlled areas; in addition, areas where mobile X ray units are used can also be categorized as controlled areas during the time in which radiological procedures are being carried out. Open plan emergency departments (i.e. areas without fixed walls where curtains are used to create cubicles), with either fixed or mobile X ray units, can also be categorized as controlled areas during the time in which radiological procedures are being carried out. In order to avoid uncertainties about the extent of controlled areas, the boundaries should, when possible, be walls and doors. |
| Classification of areas |
3.58. |
Supervised areas may involve areas surrounding X ray rooms. A typical design of a radiology department includes two basic areas: one for patient circulation, which includes the reception, waiting rooms and corridors from which the X ray rooms can be accessed through the dressing cabinets; and another for staff circulation, which includes dark rooms, film and workstation reading rooms and internal corridors. Most of the staff area may be classified as a supervised area, not primarily because of the exposure level, which can be kept very low, but rather as a ‘buffer zone’ owing to the potential for other individuals to enter the X ray rooms inadvertently and be exposed. |
| Classification of areas |
3.59. |
The control console may be inside the X ray room, separated by structural shielding, or outside the X ray room in the staff area, with visual control of the X ray room and with patient communication. Access of unauthorized individuals to control console areas should be restricted to avoid the distraction of the operator, which might lead to unnecessary or repeated exposures. Control panel areas are not in the public domain and therefore should be classified as either controlled areas or supervised areas. |
| Local rules and procedures |
3.60. |
Paragraph 3.93 of GSR Part 3 [3] establishes a hierarchy of preventive measures for protection and safety with engineered controls, including structured and ancillary shielding, being supported by administrative controls and personal protective equipment. To this end, and as established in para. 3.94 of GSR Part 3 [3], local rules and procedures are required to be established in writing in any radiology facility. Their purpose is to ensure protection and safety for workers and other persons. Such local rules and procedures should include measures to minimize occupational radiation exposure both for normal work and in unusual events. The local rules and procedures should also cover the wearing, handling and storing of personal dosimeters, and should specify investigation levels and ensuing follow-up actions (see paras 3.104–3.129). |
| Local rules and procedures |
3.61. |
Since all personnel involved in using radiation in a radiology facility need to know and follow the local rules and procedures, the development and review of these local rules and procedures should involve representatives of all health professionals involved in diagnostic radiology and image guided interventional procedures. |
| Local rules and procedures |
3.62. |
Equipment (both hardware and software) should be operated in a manner that ensures satisfactory performance at all times with respect to both the tasks to be accomplished and radiation protection and safety. The manufacturer’s operating manual is an important resource in this respect, but additional procedures are likely to be needed. The final documented set of operational procedures should be subject to approval by the licensee of the radiology facility, and should be incorporated into the facility’s management system (see paras 2.138–2.149). |
| Local rules and procedures |
3.63. |
Radiology facility staff should understand the documented procedures for their work with radiation and for the operation of the equipment with which they work, including the safety features, and should be trained, with periodic refresher training, in what to do if things go wrong. Additional training should be conducted when new medical radiological equipment is brought into use in the radiology facility. |
| Local rules and procedures |
3.64. |
Many local rules and procedures address some or all aspects of occupational radiation protection, patient radiation protection and public radiation protection, either directly or indirectly, as well as providing for a successful diagnostic examination or intervention. Paragraphs 3.65–3.88 give recommendations that should be incorporated into the radiology facility’s local rules and procedures. They are placed in this section on occupational radiation protection because they are to be followed by workers, but they will often also have significance for patient and public radiation protection. |
| Local rules and procedures |
3.65. |
For those radiological procedures where there is no need for staff to be in the room during an exposure, all attending staff should position themselves in the appropriately shielded areas. |
| Local rules and procedures |
3.66. |
In general, there should be no need for occupationally exposed staff to hold, or have close contact with, patients during a radiological procedure. If such holding or contact is indeed necessary, then the person to be used in that role should be considered a carer or comforter of the patient, and should be afforded the appropriate radiation protection described in paras 3.247–3.251. |
| Local rules and procedures |
3.67. |
Immobilization devices (e.g. a CT head cradle) should be used whenever possible and as appropriate to minimize exposure of the patient, the staff member or the carer or comforter. Immobilization of patients should not be performed by staff and, if possible, not by any person. If immobilization requires the use of a person, then this should be someone such as a relative of the patient who has agreed to be a carer or comforter and is afforded radiation protection accordingly (see paras 3.247–3.251). |
| Local rules and procedures |
3.68. |
For general radiography: The X ray tube should not be pointed at the control console area.
Given that the patient is the source of scatter radiation, care should be taken to ensure that the position of the patient is as far from the control console as is feasible, with account taken of the room configuration and accessories, and preferably more than 1 m distant from the console.
|
| Local rules and procedures |
3.69. |
For mobile radiography: Operators should wear lead aprons and should maintain as much distance as possible between themselves and the patient (to minimize exposure to scatter radiation), whilst still maintaining good visual supervision of the patient and being able to communicate verbally with him or her.
Other staff (e.g. nursing, medical and ancillary staff) are not considered as occupationally exposed workers and hence should be afforded protection as a member of the public. This is achieved by ensuring such persons are as far away from the patient as possible during the exposure (typically at least 3 m) or are behind appropriate barriers.
In situations in which a member of staff needs to be close to the patient, protective aprons should be worn (e.g. an anaesthetist with a ventilated patient or a nurse with an unstable patient).
Verbal warning of an imminent exposure should be given.
Consideration should be given to other patients nearby (see also para. 3.276 on public radiation protection).
|
| Local rules and procedures |
3.70. |
In many emergency departments, ceiling suspended X ray equipment provides a versatile environment for performing rapid trauma radiography. Appropriate occupational radiation protection can be afforded through the following: Lead aprons should be worn by staff members who need to be adjacent to the patient being exposed.
The primary beam should be directed away from staff and other patients whenever possible.
Staff should keep as far away as possible from the patient during exposure, whilst still maintaining good visual supervision of the patient.
Where available, mobile shields should be used.
Any pregnant staff member (other than radiology staff) should be asked by the medical radiation technologist to leave the vicinity during exposure.
Verbal warning of imminent exposure should be given.
|
| Local rules and procedures |
3.71. |
For CT, when staff need to be in the room during exposures, additional measures should be taken: In the case of CT interventions, the interventionist should use appropriate personal protective equipment (a protective apron, a thyroid shield and protective eyewear). In addition, care should be exercised to avoid the placing of hands in the primary beam and immediate notification to the interventionist should be given if this happens.
In the case of persons providing medical support (e.g. anaesthetists), a protective apron should be worn and the person should position themselves as far from the gantry as possible, whilst still maintaining good visual supervision of the patient.
|
| Local rules and procedures |
3.72. |
For diagnostic fluoroscopic procedures, when staff need to be in the room, the following measures should be taken: The staff member performing the procedure should use personal protective equipment (a protective apron, a thyroid shield, protective eyewear and gloves). In addition, care should be exercised to avoid the placing of hands in the primary beam and immediate notification to the fluoroscopist should be given if this happens.
In the case of persons providing medical support (e.g. anaesthetists), a protective apron should be worn and the person should position themselves as far from the patient as possible during exposure.
|
| Local rules and procedures |
3.73. |
For radiological procedures performed with mobile fluoroscopic units (C-arm systems), the following measures should be taken: The staff member performing the procedure should use personal protective equipment (a protective apron, a thyroid shield, protective eyewear and gloves). In addition, care should be exercised to avoid the placing of hands in the primary beam and immediate notification to the fluoroscopist should be given if this happens.
Only essential staff should remain in the room. All such staff are considered occupationally exposed workers.
In situations in which a member of staff needs to be close to the patient, protective aprons should be worn (e.g. an anaesthetist with a ventilated patient or a nurse with an unstable patient). At no time should a pregnant staff member take on this role.
|
| Local rules and procedures |
3.74. |
For mammography, the medical radiation technologist should stand behind the protective barrier attached to the mammography unit when making the exposure. |
| Local rules and procedures |
3.75. |
For dental facilities with intraoral and panoramic equipment, the following measures should be taken: Personal protective equipment is not usually needed. Radiation protection is afforded through the use of distance from the patient. Typically, a distance of at least 2 m is recommended.
The operator should not hold the image receptor during the exposure.
Handheld portable X ray equipment for intraoral radiography should be used only for examinations where it is impractical or not medically acceptable to transfer patients to a fixed unit or to use a mobile unit (e.g. in nursing homes, residential care facilities or homes for persons with disabilities; in forensic odontology; or for military operations abroad without dental facilities) [116].
|
| Local rules and procedures |
3.76. |
CBCT is used in some dental facilities, and should be housed in a room that has been designed and shielded accordingly. Staff should be positioned behind the protective barrier at the control console when exposures are made. |
| Local rules and procedures |
3.77. |
For DXA, the radiation levels around the unit are very low, and there are no specific precautions that should be taken with respect to occupational radiation protection. Typically, the operator can be in the room with the patient when the machine is operating. The operator’s desk should be positioned at least 1 m away from a pencil beam, and at least 2 m from a fan beam system. In the case of fan beam and cone beam configurations or if the distances above cannot be accommodated, the use of protective screens should be considered. |
| Local rules and procedures |
3.78. |
Local rules for pregnant workers and persons under the age of 18 should reflect the guidance given in paras 3.133–3.135 and 3.136, respectively. |
| Specific local rules and procedures for image guided interventional procedures |
3.79. |
Image guided interventional procedures, performed either in fluoroscopy rooms or dedicated interventional rooms, tend to be complex and are performed on patients who can be very ill or have a life threatening condition. As a consequence, more staff will be needed in the room to attend to the patients’ individual medical needs (e.g. interventionists, anaesthetists, medical radiation technologists, nurses and other specialists). Not only will more staff be exposed during interventional procedures, but they may also be standing close to the patient, where dose rates from radiation scattered by the patient are high. |
| Specific local rules and procedures for image guided interventional procedures |
3.80. |
Interventional procedures require specifically designed and dedicated equipment. The dose rate in the vicinity of the patient is lower on the beam exit side of the patient. For a vertical orientation, an under-couch X ray tube with an over-couch image receptor has lower levels of scatter radiation in the area of the operator’s trunk and head than an over-couch X ray tube with an under-couch image receptor. A similar situation exists with lateral projections, where the maximum scatter radiation is on the X ray tube side of the patient. Staff should, where practicable, always stand on the image receptor side of the patient during lateral or oblique projections. |
| Specific local rules and procedures for image guided interventional procedures |
3.81. |
There are simple methods of reducing exposure of staff by means of operational factors, including choosing where to stand in the room. Since the patient is the main source of scatter radiation, staff members should remain as far away as practicable from the patient when exposures take place to reduce exposure of staff. For the interventionist, taking a step or even half a step back during image acquisition will result in a significant reduction in occupational dose. As stated in para. 3.80, the orientation and positioning of the X ray tube will determine where it is best to stand in order to be in an area subject to relatively low amounts of scatter radiation. Automatic contrast media injectors should be used when feasible to allow personnel to move away from the patient, ideally behind a shield. |
| Specific local rules and procedures for image guided interventional procedures |
3.82. |
Staff should never be subject to direct beam exposure. This includes avoiding the placing of hands in the beam whenever possible. When the hands of the operator are close to the direct beam, an under-couch X ray tube with an over-couch image receptor should be used because the dose rate is lower on the beam exit side of the patient and the exposure of the operator’s hands is significantly reduced. |
| Specific local rules and procedures for image guided interventional procedures |
3.83. |
There are many operational factors that affect patient dose during image guided interventional procedures, and these factors in turn affect staff dose because the dose to the patient determines the amount of scatter radiation being produced. Methods to reduce patient dose are described in paras 3.189–3.195, and should always be used to reduce both patient and staff doses. |
| Specific local rules and procedures for image guided interventional procedures |
3.84. |
Medical radiological equipment specifically designed for image guided interventional procedures often incorporates protective devices, such as ceiling suspended, lead acrylic viewing screens, and under-table and lateral shielding attachments to the X ray couch, and personal mobile shields. Alternatively, such devices can be purchased separately. These devices can afford individuals significant degree of radiation protection, but they can sometimes be cumbersome to use. However, the appropriate use of these devices will result in a significant reduction in staff doses. |
| Specific local rules and procedures for image guided interventional procedures |
3.85. |
A higher incidence of radiation injuries to the lens of the eye has been reported for interventionists and nurses performing image guided interventional procedures [117]. For this reason interventionists, and other staff who routinely work close to the patient, should always use ceiling mounted screens or protective eyewear. This is further reinforced by the relatively low dose limit (20 mSv per year) for the lens of the eye (see para. 2.22 and Box 1). It is quite likely that the dose limit would be exceeded for an interventionist performing several hundred image guided interventional procedures in a year if that person did not use any protection for the eyes. Protective shielding devices are effective only when they are interposed between the source of radiation and the eye. Care should be taken in the proper positioning of the imaging displays to ensure optimum benefit is derived from the use of screens and protective eyewear. |
| Specific local rules and procedures for image guided interventional procedures |
3.86. |
Further specific guidance on interventional radiology and interventional cardiology, endorsed by several regional professional societies, can be found in Refs [117, 118]. |
| Specific local rules and procedures for image guided interventional procedures |
3.87. |
Some image guided interventional procedures are performed using CT, and the guidance given in para. 3.71 applies. |
| Specific local rules and procedures for image guided interventional procedures |
3.88. |
For image guided interventional procedures involving intracoronary implantation of unsealed and sealed radiation sources, reference should be made to the guidance, where appropriate, in paras 4.75–4.89 and paras 5.117–5.145, respectively. |
| Personal and in-room protective devices |
3.89. |
Paragraphs 3.93 and 3.95 of GSR Part 3 [3] require that personal protective equipment and in-room protective devices be available and used when structural shielding and administrative controls alone cannot afford the required level of occupational radiation protection. This typically arises when staff are required to be in the room during radiological procedures, such as with image guided interventional procedures and fluoroscopy, and with mobile radiography. The need for this protective equipment should be established by the RPO or the medical physicist at the radiology facility. |
| Personal and in-room protective devices |
3.90. |
Personal protective equipment is worn on the person and includes protective aprons, thyroid shields, protective eyewear and protective gloves. Protective aprons are available in many shapes, configurations, materials and lead equivalence, and should be chosen to best suit the intended use. Some aprons require using fully overlapping panels to provide complete coverage. Expert advice on personal protective equipment should be sought from the RPO or medical physicist. |
| Personal and in-room protective devices |
3.91. |
For image guided interventional procedures, wrap around aprons, preferably consisting of vests and skirts to spread the weight, should be used. They should cover: From the neck down to at least 10 cm below the knees;
The entire breast bone (sternum) and shoulders;
The sides of the body from not more than 10 cm below the armpits to at least halfway down the thighs;
The back from the shoulders down to and including the buttocks.
|
| Personal and in-room protective devices |
3.92. |
Protective gloves are useful for protecting the hands near the beam, but can produce the opposite effect during fluoroscopy with ABC or ADRC when the hands enter the area covered by the sensor of the ABC or ADRC, because this would drive the exposure to higher levels for both the staff and the patient and would be ineffective in protecting the hands. Even if the fluoroscopy system operates without ABC or ADRC, leaded gloves can prolong the procedure because they do not afford the necessary tactile sensitivity and thus their value is questionable. |
| Personal and in-room protective devices |
3.93. |
Protective eyewear, especially for use in image guided interventional procedures, should cover the entire orbit. This means that lateral protection should be provided by shielded sides and the glasses should be a close fit. |
| Personal and in-room protective devices |
3.94. |
The lead equivalence of personal protective equipment should be specified at the maximum operating X ray tube potential applicable for its intended use. |
| Personal and in-room protective devices |
3.95. |
Non-lead based personal protective equipment, incorporating shielding materials, such as tin, tungsten, bismuth and antimony, can be preferable if they are lighter and easier to use. Care should be taken in interpreting claimed lead equivalences for non-lead based protective equipment, and expert advice from the RPO or medical physicist should be sought. |
| Personal and in-room protective devices |
3.96. |
Protective equipment for pregnant workers should be carefully considered, as wrap around aprons may no longer provide adequate protection for the embryo or fetus (para. 3.114 of GSR Part 3 [3]). The RPO or medical physicist should be consulted as necessary. |
| Personal and in-room protective devices |
3.97. |
Items of personal protective equipment, in particular protective aprons, can lose their protective effectiveness if mistreated or not appropriately used or cared for. All personnel that use personal protective equipment have the responsibility for its appropriate use and care, for example by ensuring aprons are correctly hung and stored to minimize damage. |
| Personal and in-room protective devices |
3.98. |
Personal protective equipment should be examined under fluoroscopy or radiography periodically to confirm its shielding integrity.
|
| Personal and in-room protective devices |
3.99. |
Additional protective devices for use in fluoroscopy and image guided interventional procedures include: Ceiling suspended protective screens for protecting eyes and the thyroid while keeping visual contact with the patient. Technical advances with such screens include systems that move with the operator.
Protective lead curtains or drapes mounted on the patient table.
Mobile shields either attached to the table (lateral shields) or mounted on coasters (full body).
Disposable protective drapes for the patient.
|
| Workplace monitoring |
3.100. |
Paragraphs 3.96–3.98 of GSR Part 3 [3] establish the requirements and responsibilities for workplace monitoring. Workplace monitoring comprises measurements made in the working environment and the interpretation of the results. Workplace monitoring serves several purposes, including routine monitoring, special monitoring for specific occasions, activities or tasks, and confirmatory monitoring to check assumptions made about exposure conditions. Workplace monitoring can be used to verify the occupational doses of personnel whose work involves exposure to predictable low levels of radiation. It is particularly important for staff members who are not individually monitored. Further general guidance on workplace monitoring is given in GSG-7 [23]. |
| Workplace monitoring |
3.101. |
Workplace monitoring in areas around each item of medical radiological equipment in the radiology facility, when it is being operated, should be carried out when: The room and shielding construction has been completed, regardless of whether it is a new construction or a renovation, and before the room is first used clinically;
New or substantially refurbished equipment is commissioned (both direct and indirect radiation such as leakage and scatter radiation should be measured);
New software for the medical radiological equipment is installed or there is a significant upgrade;
New techniques are introduced;
Servicing of the medical radiological equipment has been performed, which could have an impact on the radiation delivered.
|
| Workplace monitoring |
3.102. |
Workplace monitoring should be performed and documented as part of the radiology facility’s radiation protection programme. The radiology facility’s RPO or medical physicist should provide specific advice on the workplace monitoring programme, including any investigations that are triggered when investigation levels are exceeded (see paras 3.121 and 3.122). |
| Workplace monitoring |
3.103. |
The survey meters used for radiation monitoring should be calibrated in terms of ambient dose equivalent. The calibration should be current, and should be traceable to a standards dosimetry laboratory. For diagnostic radiology and image guided interventional procedures, the quantity is the ambient dose equivalent, H*(10), and the unit is the sievert (Sv) and its submultiples (for more detailed guidance, see GSG-7 [23]). |
| Assessment of occupational exposure |
3.104. |
The purpose of monitoring and dose assessment is, inter alia, to provide information about the exposure of workers and to confirm good working practices and regulatory compliance. Paragraph 3.100 of GSR Part 3 [3] establishes the requirement of individual monitoring for “any worker who usually works in a controlled area, or who occasionally works in a controlled area and may receive a significant dose from occupational exposure”. Workers who may require individual monitoring include radiologists, cardiologists, gastroenterologists, endoscopists, urologists, orthopaedic surgeons, neurosurgeons, respiratory physicians, anaesthetists, medical physicists, biomedical and clinical engineers, medical radiation technologists, nurses and the RPO. |
| Assessment of occupational exposure |
3.105. |
Monitoring involves more than just measurement. It includes interpretation, assessment, investigation and reporting, which may lead to corrective measures, if necessary. Individual external doses can be assessed by using individual monitoring devices, which include thermoluminescent dosimeters, optical stimulated luminescent dosimeters, radiophotoluminiscent dosimeters, film badges and electronic dosimeters. When electronic dosimeters are used in pulsed X ray fields, care should be taken to ensure that they are functioning correctly. Individual monitoring devices should be calibrated and should be traceable to a standards dosimetry laboratory (for more detailed guidance, see GSG-7 [23]). |
| Assessment of occupational exposure |
3.106. |
Each dosimeter should be used for monitoring only the person to whom it is issued, for work performed at that radiology facility, and it should not be taken to other facilities where that person may also work. For example, if a person is issued with a dosimeter at hospital A, it should be worn only at hospital A and not at any other hospitals or medical centres where he or she also works. Monitoring results can then be interpreted for the person working in a specific radiology facility, and this will allow appropriate review of the effectiveness of the optimization of protection and safety for that individual in that facility. However, national regulatory requirements may differ from this advice, and they would need to be followed in those jurisdictions in which they apply (see also paras 3.123–3.125). |
| Assessment of occupational exposure |
3.107. |
The monitoring period (period of dosimeter deployment) specified by regulatory bodies in most States is typically in the range of one to three months. A one month monitoring period is usually used for persons performing procedures associated with higher occupational exposure, such as image guided interventional procedures. A longer monitoring period (two or three months) is more typical for personnel exposed to lower doses, as a one month cycle would usually mean that the actual occupational dose is less than the minimum detection level of the dosimeter, resulting in no detectable doses. With a longer cycle, it is more likely that a reading can be obtained. Dosimeters should be sent from the radiological facility to the dosimetry service provider, which should then process the dosimeters and return the dose reports, all in a timely manner. Some regulatory bodies may specify a performance criterion for timely reporting. |
| Assessment of occupational exposure |
3.108. |
The operational dosimetric quantity used is the personal dose equivalent Hp(d). For weakly penetrating radiation and strongly penetrating radiation, the recommended depths, d, are 0.07 mm and 10 mm, respectively. Radiation used in diagnostic radiology and image guided interventional procedures is usually relatively strongly penetrating, and therefore d = 10 mm for dosimeters being used to assess effective dose. Hp(10) is used to provide an estimate of effective dose that avoids both underestimation and excessive overestimation [23]. In diagnostic radiology and image guided interventional procedures, the overestimation is somewhat larger because of the lower photon penetration from X ray beams in the kV range [119, 120]. If a protective apron or thyroid shield is being worn, the relationship between Hp(10) and effective dose becomes more complex; additional guidance is given in para. 3.115. |
| Assessment of occupational exposure |
3.109. |
For monitoring the skin and extremities, a depth of 0.07 mm (d = 0.07) is recommended, and Hp(0.07) is used to provide an estimate of equivalent dose to the skin and extremities. |
| Assessment of occupational exposure |
3.110. |
For monitoring the lens of the eye, a depth of 3 mm (d = 3) is recommended, and Hp(3) is used to provide an estimate of equivalent dose to the lens of the eye. In practice, however, the use of Hp(3) has not been widely implemented for routine individual monitoring. In cases where eye doses are a concern, such as in image guided interventional procedures, Hp(0.07), and to a lesser extent Hp(10), can be considered as an acceptable surrogate operational quantity (see Ref. [121] for further information). |
| Assessment of occupational exposure |
3.111. |
There are three dose limits applicable to workers in diagnostic radiology and image guided interventional procedures: the limit for effective dose, and the limits for equivalent dose to the lens of the eye and to the skin and extremities. The dosimeter being worn will be used to estimate one or more of the quantities used for the dose limits. Depending on the work performed by the person being individually monitored, there may be a preferred position for wearing the dosimeter, and more than one dosimeter may be used. For image guided interventional procedures, two dosimeters should be worn. |
| Assessment of occupational exposure |
3.112. |
For individual monitoring with only one dosimeter in diagnostic radiology and image guided interventional procedures the following recommendations are made: If the monitored worker never wears a protective apron, the dosimeter should be worn on the front of the torso between the shoulders and the waist.
If the monitored worker sometimes wears a protective apron, the dosimeter should be worn on the front of the torso between the shoulders and the waist, and under the apron when it is being worn.
If the monitored worker always wears a protective apron, the dosimeter should be worn on the front of the torso at shoulder or collar level outside the apron (see also para. 3.113), except if national regulations require the dosimeter to be worn under the apron.
If the working situation is such that the radiation always or predominantly comes from one side of the person, such as in image guided interventional procedures, the dosimeter should be placed on the front of the torso on the side closest to the source of radiation; the guidance in (a) to (c) should also be followed in this case.
|
| Assessment of occupational exposure |
3.113. |
For individual monitoring with two dosimeters, such as in image guided interventional procedures, where the monitored worker always wears a protective apron, one dosimeter should be worn on the front of the torso at shoulder or collar level outside the apron on the side closest to the source of radiation. The other dosimeter should be worn on the front of the torso between the shoulders and the waist and under the apron, preferably on the side closest to the source of radiation. |
| Assessment of occupational exposure |
3.114. |
Specialized dosimeters, such as ring dosimeters for monitoring finger doses, will have their own specific wearing instructions, which should be followed. |
| Assessment of occupational exposure |
3.115. |
When a protective apron is being used, the assessment of effective dose might not be straightforward: A single dosimeter placed under the apron, reported in Hp(10), provides a good estimate of the contribution to the effective dose of the parts of the body protected by the apron, but underestimates the contribution of the unprotected parts of the body (the thyroid, the head and neck, and the extremities).
A single dosimeter worn outside the apron, reported in Hp(10), provides a significant overestimate of effective dose and should be corrected for the protection afforded by the apron by using an appropriate algorithm [120, 122, 123].
Where two dosimeters are worn, one under the apron and the other outside the apron, an algorithm should be applied to estimate the effective dose from the two reported values of Hp(10) [120, 122].
|
| Assessment of occupational exposure |
3.116. |
As noted in para. 3.110, dosimeters for reporting Hp(3) are not widely available. A dosimeter worn outside the apron at collar or neck level, reported in either Hp(0.07) or Hp(10), can provide a surrogate estimate for the equivalent dose to the lens of the eye. Whether or not protective eyewear was worn should be taken into account to interpret the dose estimate correctly. |
| Assessment of occupational exposure |
3.117. |
When not in use, individual dosimeters should be kept in a dedicated place and should be protected from damage or from irradiation. If an individual loses his or her dosimeter, the individual should inform the RPO, who should perform a dose assessment, record this evaluation of the dose and add it to the individual’s dose record. Where there is a national dose registry, it should be updated with the dose estimate in a timely manner. The most reliable method for estimating an individual’s dose is to use his or her recent dose history. In cases where the individual performs non-routine types of work, it may be better to use the doses of co-workers experiencing similar exposure conditions as the basis for the dose estimate. |
| Assessment of occupational exposure |
3.118. |
In some radiology facilities and for some individuals with a low level of occupational exposure (e.g. general dental practitioners), area dosimetry to estimate the level of dose per procedure can be an acceptable alternative to individual monitoring. With knowledge of the typical level of dose per procedure for positions where personnel are placed during exposures and the number of procedures per year, the RPO can estimate personnel doses. |
| Assessment of occupational exposure |
3.119. |
Similarly, occupational doses can be estimated from the results of workplace monitoring. The effective dose for personnel can be inferred from the measured ambient dose equivalent H*(10). The ICRP [119] provides conversion coefficients from ambient dose equivalent to effective dose for different types of radiation and energy. The conversion coefficients for photons are close to unity except for very low energy photons, such as photons scattered from a mammography X ray beam. |
| Assessment of occupational exposure |
3.120. |
An additional direct reading operational dosimeter, such as an appropriately calibrated electronic dosimeter, can also be used in image guided interventional procedures, as these devices can give the worker an instant indication of both the cumulative dose and the current dose rate and are a useful tool for the optimization of occupational radiation protection [23]. |
| Investigation levels for staff exposure |
3.121. |
Investigation levels are different from dose constraints and dose limits; they are a tool used to provide a warning of the need to review procedures and performance, to investigate what is not working as expected and to take timely corrective action. The exceeding of an investigation level should prompt such actions. For example, for diagnostic radiology and image guided interventional procedures, monthly values higher than 0.5 mSv (for a dosimeter worn under a protective apron) could be investigated. Values higher than 2 mSv per month [118] from an over-apron dosimeter might indicate that eye doses are of concern. Values higher than 15 mSv per month for hand or finger dosimeters should also be investigated [117, 118]. Abnormal conditions and events should also trigger an investigation. In all cases, the investigation should be carried out with a view to improving the optimization of occupational protection, and the results should be recorded. Investigation levels should also be set for workplace monitoring, with account taken of exposure scenarios and the predetermined values adopted for investigation levels for workers. Details on investigation levels are provided in GSG-7 [23]. |
| Investigation levels for staff exposure |
3.122. |
An investigation should be initiated as soon as possible following a trigger or event, and a written report should be prepared concerning the cause, including determination or verification of the dose, corrective or mitigatory actions, and instructions or recommendations to avoid recurrence. Such reports should be reviewed by the quality assurance committee and the radiation safety committee, as appropriate, and the licensee should be informed. In some cases, the regulatory body may also need to be informed. |
| Persons who work in more than one place |
3.123. |
Some individuals might work in more than one radiology facility. The facilities may be quite separate entities in terms of ownership and management, or they may have common ownership but separate management, or they may even have common ownership and management but be physically quite separate. Regardless of the ownership and management structure, the occupational radiation protection requirements for the particular radiology facility apply when the person is working in that facility. As described in para. 3.106, a dosimeter issued for individual monitoring should be worn only in the facility for which it is issued, as this facilitates the effective optimization of protection and safety in that facility. This approach is logistically more easily implemented, since each physical site has its own dosimeters, and so there is no need to transport dosimeters between facilities, with the risk of losing or forgetting them. In cases where the facilities are under common ownership, it may be seen as an unnecessary financial burden to provide more than one set of dosimeters for staff that work in more than one of its facilities. However, the radiation protection advantages of having the dosimeter results linked to a person’s work in only one radiology facility remain (see also para. 3.125). |
| Persons who work in more than one place |
3.124. |
There is, however, an important additional consideration, namely the need to ensure compliance with the occupational dose limits. Any person who works in more than one radiology facility should notify the licensee for each of those facilities. Each licensee, through its RPO, should establish formal contact with the licensees of the other radiology facilities and their RPOs, so that each facility has an arrangement to ensure that a personal dosimeter is available and that there is an ongoing record of the occupational doses for that person in all the facilities where he or she works. |
| Persons who work in more than one place |
3.125. |
Some individuals, such as consultant medical physicists or service engineers, might perform work in many radiology facilities and, in addition, in other medical radiation facilities. They can be employed by a company or be self-employed, providing contracted services to the radiology facility and the other facilities. In such cases, it is simpler for the company or the self-employed person to provide the dosimeters for individual monitoring. Therefore, in these cases, a worker uses the same dosimeter for work performed in all radiology facilities (and other medical radiation facilities) in the monitoring period. |
| Records of occupational exposure |
3.126. |
Paragraphs 3.103–3.107 of GSR Part 3 [3] establish the detailed requirements for records of occupational exposure and place obligations on employers, registrants and licensees. In addition to demonstrating compliance with legal requirements, records of occupational exposure should be used within the radiology facility for additional purposes, including assessing the effectiveness of the optimization of protection and safety at the facility and evaluating trends in exposure. National or local regulatory bodies might specify additional requirements for records of occupational exposure and for access to the information contained in those records. Employers are required to provide workers with access to records of their own occupational exposure (para. 3.106(a) of GSR Part 3 [3]). Further general guidance on records of occupational exposure is given in GSG-7 [23]. |
| Health surveillance for workers |
3.127. |
The primary purpose of health surveillance is to assess the initial and continuing fitness of employees for their intended tasks, and requirements are given in paras 3.108 and 3.109 of GSR Part 3 [3]. |
| Health surveillance for workers |
3.128. |
No specific health surveillance relating to exposure to ionizing radiation is necessary for staff involved in diagnostic radiology and image guided interventional procedures, with perhaps the possible exception of initial eye assessment and periodic eye assessments for visual acuity and contrast resolution for personnel performing significant numbers of image guided interventional procedures. Only in cases of overexposed workers, at doses much higher than the dose limits (e.g. a few hundred millisieverts or higher), would special investigations involving biological dosimetry and further extended diagnosis and medical treatment be necessary [23]. Under normal working conditions, the occupational doses incurred in diagnostic radiology and image guided interventional procedures are low, and no specific radiation related examinations are required for persons who are occupationally exposed to ionizing radiation, as there are no diagnostic tests that yield information relevant to normal exposure. It is, therefore, rare for considerations of occupational exposure arising from the working environment of a radiology facility to influence significantly the
decision about the fitness of a worker to undertake work with radiation or to influence the general conditions of service [23]. |
| Health surveillance for workers |
3.129. |
Counselling should be made available to workers who have or may have been exposed in excess of dose limits, and information, advice and, if indicated, counselling should be made available to workers who are concerned about their radiation exposure. In diagnostic radiology and image guided procedures, the latter group may include women who are or may be pregnant. Counselling should be given by appropriately experienced and qualified practitioners. Further guidance is given in GSG-7 [23]. |
| Information, instruction and training |
3.130. |
All staff involved in diagnostic radiology and image guided interventional procedures should meet the respective training and competence criteria described in paras 2.119–2.137. This will include general education, training, qualification and competence for occupational radiation protection. Radiological medical practitioners, medical radiation technologists and nurses working with hybrid units (such as PET–CT and SPECT–CT) may have trained exclusively in their original specialty. They should undertake radiation protection and safety training relevant to the additional imaging modality. |
| Information, instruction and training |
3.131. |
Paragraph 3.110 of GSR Part 3 [3] places responsibilities on the employer to provide adequate information, instruction and training for protection and safety as it pertains to the radiology facility. This is not only for new staff but also for all staff as part of their continuing professional development. Specific instruction and training should be provided when new medical radiological procedures, equipment, software and technologies are introduced. |
| Conditions of service and special arrangements |
3.132. |
Paragraph 3.111 of GSR Part 3 [3] requires that no special benefits be offered to staff because they are occupationally exposed. It is not acceptable to offer benefits as substitutes for measures for protection and safety. |
| Pregnant workers |
3.133. |
There is no requirement in GSR Part 3 [3] for a worker to notify the licensee that she is pregnant, but it is necessary that female workers understand the importance of making such notifications so that their working conditions can be modified accordingly. Paragraph 3.113(b) of GSR Part 3 [3] establishes the requirement that employers, in cooperation with registrants and licensees, provide female workers with appropriate information in this regard. |
| Pregnant workers |
3.134. |
Paragraph 3.114 of GSR Part 3 [3] states that: |
| Pregnant workers |
3.135. |
With regard to the dose limit of 1 mSv for the embryo or fetus, the reading of a dosimeter can overestimate the dose to the embryo or fetus by a factor of 10. If the reading corresponds to a dosimeter worn outside a lead apron, the overestimation can rise to a factor of 100 [124]. The dose to the embryo or fetus should be assessed using an appropriately positioned additional dosimeter (see also GSG-7 [23]). Information, advice and, if indicated, counselling for pregnant workers should be made available (see also para. 3.129). |
| Persons under 18 |
3.136. |
In many States, there is the possibility of students aged 16 or more, but under 18, commencing their studies and training to become a medical radiation technologist or other health professional that can involve occupational exposure to ionizing radiation. Paragraph 3.116 of GSR Part 3 [3] establishes the requirements for access to controlled areas and the dose limits for such persons are more restrictive (see Box 1 of this Safety Guide and Schedule III of GSR Part 3 [3]). |
| Persons under 18 |
3.137. |
This section covers radiation protection of patients, carers and comforters, and volunteers in biomedical research. The term ‘patient’, when used in the context of medical exposure, means the person undergoing the radiological procedure. Other patients in the radiology facility, including those who may be waiting for their own radiological procedure, are considered members of the public and their radiation protection is covered in paras 3.273–3.282. |
| Persons under 18 |
3.138. |
As described in para. 2.8, there are no dose limits for medical exposure, so it is very important that there is effective application of the requirements for justification and optimization. |
| Justification of medical exposure |
3.139. |
The requirements for justification of medical exposure (paras 3.155–3.161 of GSR Part 3 [3]) incorporate the three-level approach to justification (see para. 2.11) [4, 125, 126]. |
| Justification of medical exposure |
3.140. |
The roles of the health authority and professional bodies with respect to a level 2 or generic justification of radiological procedures, justification of health screening programmes, and justification of screening intended for the early detection of disease, but not as part of a health screening programme, are described in paras 2.55–2.60. |
| Justification of medical exposure for the individual patient |
3.141. |
GSR Part 3 [3] requires a joint approach to justification at the level of an individual patient, with a shared decision involving both the referring medical practitioner (who initiates the request for a radiological procedure) and the radiological medical practitioner. A referral should be regarded as a request for a professional consultation or opinion rather than an instruction or order to perform. The referring medical practitioner brings the knowledge of the medical context and the patient’s history to the decision process, while the radiological medical practitioner has specialist expertise on the radiological procedure. The efficacy, benefits and risks of alternative methods (both methods involving ionizing radiation and methods not involving ionizing radiation) should be considered. In all cases, the justification is required to take into account national or international referral guidelines (para. 3.158 of GSR Part 3 [3]). For examples of such guidelines, see Refs [127–133].The ultimate responsibility for justification will be specified in the individual State’s regulations. |
| Justification of medical exposure for the individual patient |
3.142. |
The patient should also be informed about the expected benefits, risks and limitations of the proposed radiological procedure, as well as the consequences of not undergoing the procedure. |
| Justification of medical exposure for the individual patient |
3.143. |
Justification, which is a principle of radiation protection, is implemented more effectively as part of the medical process of determining the ‘appropriateness’ of a radiological procedure. The process of determining appropriateness is an evidence based approach to choosing the best test for a given clinical scenario, with account taken of the diagnostic efficacy of the proposed radiological procedure as well as of alternative procedures that do not use ionizing radiation, for example, ultrasound, MRI or endoscopy. Useful tools to support this decision making process include national or international imaging referral guidelines developed by professional societies [127–133]. Imaging referral guidelines can be disseminated or utilized through electronic requesting systemsand clinical decision support tools or systems. It should be ensured that such systems correctly apply the regulatory requirements for justification, in particular with respect to roles and responsibilities. |
| Justification of medical exposure for the individual patient |
3.144. |
In determining the appropriateness of the radiological procedure for an individual patient, the following questions should be asked by the referring medical practitioner [132]: Has it already been done? A radiological procedure that has already been performed within a reasonable time period (depending on the procedure and clinical question) should not be repeated (unless the clinical scenario indicates the appropriateness of repeating the procedure). The results (images and reports) of previous examinations should be made available, not only at a given radiology facility but also for consultation at different facilities. Digital imaging modalities and electronic networks should facilitate this process. Individual patient exposure records should be used to facilitate the decision making process if available.
Is it needed? The anticipated outcome of the proposed radiological procedure (positive or negative) should influence the patient’s management.
Is it needed now? The timing of the proposed radiological procedure in relation to the progression of the suspected disease and the possibilities for treatment should all be considered as a whole.
Is this the best investigation to answer the clinical question? Advances in imaging techniques are taking place continually, and the referring medical practitioner may need to discuss with the radiological medical practitioner what is currently available for a given problem.
Has the clinical problem been explained to the radiological medical practitioner? The medical context for the requested radiological procedure is crucial for ensuring the correct technique is performed with the correct focus.
|
| Justification of medical exposure for the individual patient |
3.145. |
For some radiological procedures, primarily ‘well established’ procedures and low dose procedures, the practical implementation of justification in many States is carried out by the medical radiation technologist, who is effectively representing the radiological medical practitioner with the formal understanding that, if there is uncertainty, the radiological medical practitioner is contacted and the final decision is taken by the radiological medical practitioner in consultation with the referring medical practitioner. Such justification is guided by national or international referral guidelines. It should be noted that, in all cases, the responsibility for justification lies with the radiological medical practitioner and the referring medical practitioner. |
| Justification of medical exposure for the individual patient |
3.146. |
For a small percentage of radiological procedures, primarily because of a combination of complexity, difficult medical context and higher dose, the justification is likely to be led by the radiological medical practitioner, with the referring medical practitioner providing any necessary further clarification on the medical context. Again, the justification should take into account national or international referral guidelines. |
| Justification of medical exposure for the individual patient |
3.147. |
Two particular groups of patients identified in para. 3.157 of GSR Part 3 [3] for special consideration with respect to justification are patients who are pregnant or are paediatric. Owing to the higher radiosensitivity of the embryo or fetus, it should be ascertained whether a female patient is pregnant before an X ray examination for diagnosis or an image guided interventional procedure is performed. Paragraph 3.176 of GSR Part 3 [3] requires that procedures be “in place for ascertaining the pregnancy status of a female patient of reproductive capacity before the performance of any radiological procedure that could result in a significant dose to the embryo or fetus”. Pregnancy would then be a factor in the justification process and might influence the timing of the proposed radiological procedure or a decision as to whether another approach to treatment is more appropriate. Confirmation of pregnancy could occur after the initial justification and before the radiological procedure is performed. Repeat justification is then necessary, with account taken of the additional sensitivity of the pregnant patient and embryo or fetus.
As children are at greater risk of incurring radiation induced stochastic effects, paediatric examinations necessitate special consideration in the justification process.
|
| Justification of medical exposure for the individual patient |
3.148. |
Review of the justification may need to take place if circumstances change; for example, if the performance of a low dose procedure has been justified but, at the time of performing the examination, a high dose protocol is needed. Such a case might be a justification for low dose CT for renal colic that would have to be reviewed if high dose enhanced CT urography is actually necessary to answer the clinical question. |
| Justification of medical exposure for the individual patient |
3.149. |
A ‘self-referral’ occurs when a health professional undertakes a radiological procedure for patients as a result of justification on the basis of his or her own clinical assessment. Examples of acceptable self-referral practice occur in dentistry, cardiology, orthopaedics, vascular surgery, urology and gastroenterology. Relevant professional bodies in many States develop appropriate guidance for their specialty, for example dental associations [134]. |
| Justification of medical exposure for the individual patient |
3.150. |
‘Self-presentation’ occurs when a member of the public asks for a radiological procedure without a referral from a health professional. This may have been prompted by media reports or advertising. Examples include ‘individual health assessments’ which often involves CT procedures in asymptomatic individuals for early detection of cancer (e.g. whole body CT, lung CT or colon CT) and quantification of coronary artery calcification (coronary artery CT). Justification is required, as for all radiological procedures. Relevant professional bodies have an important role in considering evidence for developing guidance when new practices are proposed, as for example in the case of CT [135]. States may choose to incorporate such guidance into legislation [136]. |
| Justification of medical exposure for the individual patient |
3.151. |
Means to improve awareness, appropriateness and auditing should be developed to support the application of the requirement for justification of medical exposure. Awareness of the need for justification underpins the whole process of justification. Means for promoting awareness include traditional education and training, such as at medical school or during specialty training, Internet based learning or learning ‘on the job’ (e.g. junior doctors in an emergency department), and the use of feedback in the reporting process. Appropriateness is described in paras 3.143 and 3.144, and the audit process is used for monitoring and feedback to improve both awareness and appropriateness. |
| Justification of medical exposure for biomedical research volunteers |
3.152. |
The role of the ethics committee in the justification of medical exposure of volunteers exposed as part of a programme of biomedical research is described in para. 2.99. |
| Justification of medical exposure for carers and comforters |
3.153. |
The three-level approach to justification is not applicable for carers and comforters. Instead, para. 3.155 of GSR Part 3 [3] establishes the requirement to ensure that there be some net benefit arising from the exposure, for example the successful performance of a diagnostic procedure on a child. The crucial component in the justification of medical exposure of carers and comforters is their knowledge and understanding about radiation protection and the radiation risks for the procedure being considered. To this end, the radiological medical practitioner or medical radiation technologist involved in the radiological procedure, prior to the performance of the procedure, has the responsibility to ensure that the carer or comforter is correctly informed about radiation protection and the radiation risks involved, and that the carer or comforter understands this information and consequently agrees to take on the role of carer or comforter. |
| Optimization of protection and safety |
3.154. |
In medical exposure, optimization of protection and safety has several components, some applicable directly to the radiological procedure about to be performed and others providing the support or framework for the other components. These components of optimization of protection and safety are described in paras 3.155–3.252. Key personnel in the optimization process are the radiological medical practitioner, the medical radiation technologist and the medical physicist. |
| Design considerations |
3.155. |
The use of appropriate and well designed medical radiological equipment and associated software underpins any radiological procedure in diagnostic radiology or any image guided interventional procedure. X ray generators and their accessories should be designed and manufactured so as to facilitate the keeping of doses in medical exposure as low as reasonably achievable consistent with obtaining adequate diagnostic information or guidance for the intervention. Guidance on design considerations is given in the subsection on medical radiological equipment in paras 3.32–3.41. This guidance is applicable to both stand alone and hybrid systems. Ultimately, as established in para. 3.162 of GSR Part 3 [3], it is the responsibility of the licensee of the radiology facility to ensure that the facility uses only medical radiological equipment and software that meets applicable international or national standards. |
| Operational considerations: General |
3.156. |
Following justification, the diagnostic radiological procedure or image guided interventional procedure is required to be performed in such a way as to optimize patient protection (para. 3.163 of GSR Part 3 [3]). The level of image quality sufficient for diagnosis is determined by the radiological medical practitioner and is based on the clinical question posed and the anatomical structures imaged (e.g. the diagnosis of the pattern of sinusitis on CT requires only a low dose procedure as high contrast structures, namely air and bone, be imaged). With image guided interventional procedures, the level of image quality should be sufficient to guide the intervention. |
| Operational considerations: General |
3.157. |
The following points apply to all diagnostic radiological procedures or image guided interventional procedures: There should be an effective system for correct identification of patients, with at least two, preferably three, forms of verification, for example name, date of birth, address and medical record number.
Patient details should be correctly recorded, such as age, sex, body mass, height, pregnancy status, current medications and allergies.
The clinical history of the patient should be reviewed.
|
| Operational considerations: General |
3.158. |
The first step in operational considerations of optimization is selection of the appropriate medical radiological equipment. For example, a chest X ray should be performed using dedicated equipment with a radiation generator producing high output enabling the use of a long source to image receptor distance (typically 1.8 m) and a short exposure time to ensure a reproducible image of diagnostic quality by minimizing patient respiratory motion and cardiac motion. |
| Operational considerations: General |
3.159 |
The volume (area) of the patient that is exposed should be strictly limited to that of clinical interest. This is achieved through collimation in radiography, mammography, fluoroscopy and image guided interventional procedures, and through the choice of scan parameters in CT. For diagnostic radiology, image cropping performed after the exposure does not achieve any reduction in the exposed volume. |
| Operational considerations: General |
3.160. |
Cooperation of the patient should be ensured to achieve an image of diagnostic quality. This is particularly relevant when imaging children. Good communication helps to achieve this. Verbal interaction between the medical radiological technologist or the medical radiological practitioner and the patient should take place before, during and after the procedure. |
| Operational considerations: General |
3.161. |
Optimization of protection and safety for a woman undergoing a radiological procedure during pregnancy should take into account the woman and the embryo or fetus. Routine diagnostic CT examinations of the pelvic region with and without contrast injection can lead to a dose of 50 mSv to the uterus, which is assumed to be the same as the dose that would be received by the fetus in early pregnancy. When CT scanning is indicated for a pregnant patient, low dose CT protocols should be used and the scanning area should be reduced to a minimum (see also paras 3.176–3.185). |
| Operational considerations: General |
3.162. |
Shielding of radiosensitive organs, such as the gonads, the lens of the eye, the breast and the thyroid, should be used when appropriate. Care should be taken in the anatomical placement of such shields, the impact of shielding on image quality (artefacts), and the use of AEC devices and the consequences for patient dose. |
| Operational considerations: General |
3.163. |
For each modality, there are a number of factors that can be adjusted to influence the relationship between image quality and patient dose. Written protocols that specify the operating parameters to be used for common diagnostic radiological procedures should be developed, adopted and applied in each radiology facility. Such protocol ‘technique charts’ should be posted adjacent to each X ray generator and should be specific for each piece of equipment. The protocols should take into account the anatomical region, as well as patient mass and size. The protocols should be developed using guidelines from national or international professional bodies, and hence should reflect current best practices (e.g. see Refs [137–147]). For modern digital equipment, many of the factors are automated through the menu driven selection of options on the console. Nevertheless, in setting up these options, significant scope exists for the optimization of protection and safety through the appropriate selection of values for the various technical parameters, thereby effectively creating an electronic technique chart. |
| Operational considerations: General |
3.164. |
Size specific written protocols should be developed for children, from neonates to teenagers, and should include additional operational considerations, such as the use of additional filtration or the removal of grids when appropriate [143, 145, 146]. |
| Operational considerations: General |
3.165. |
Paragraph 3.166(b) of GSR Part 3 [3] establishes a special requirement for the optimization of protection and safety for individuals subject to medical exposure as part of an approved health screening programme. All aspects of protection should be considered before the approval of the programme and during its implementation, such as the selection of X ray equipment suitable for the particular screening and parameters settings. A dedicated, comprehensive programme of quality assurance should be implemented to meet screening objectives, as described in more detail in paras 3.232–3.246. It should set requirements for the education and training of the medical professionals involved in the health screening programme, for adequate quality management for the whole screening chain and for documentation and evaluation of the results. |
| Operational considerations: Radiography |
3.166. |
In developing protocols for radiography, many technique factors should be considered, which can influence the image quality and the patient dose for the radiographic projection. Detailed guidance on appropriate choices for those factors is widely available (see Refs [137, 142, 143, 148–153]). Such factors include: the tube potential; current; exposure time; focal spot size; filtration; source to image receptor distance; choice of anti-scatter grids or Bucky device; collimation; image receptor size; positioning, immobilization and compression of the patient; the number of projections needed (e.g. a posterior–anterior chest X ray rather than posterior–anterior and lateral X rays); and organ shielding where appropriate (e.g. testicular shielding for pelvic radiographs in male patients). |
| Operational considerations: Radiography |
3.167. |
Suitably calibrated and maintained AEC systems should be used when available and appropriate. Particular attention should be given in paediatric radiography to ensuring that AEC sensors are within the radiation field [152]. AEC systems are calibrated on the basis of the radiation exposure at the detector required to produce the desired level of optical density for film–screen systems or a predetermined acceptable level of signal to noise ratio, or surrogate, for digital systems. The value for the signal to noise ratio should be established as part of setting up the protocols for radiographic projections for each particular X ray unit. In determining technique factors when AEC is not available, consideration should be given to the patient’s size and the thickness of the body part to be imaged. |
| Operational considerations: Radiography |
3.168. |
For digital systems, users should understand how the selection of the ‘exposure index’ (or other exposure indicator) affects the patient dose. For some systems, increasing the index lowers the dose; for others, it increases it [154]. |
| Operational considerations: Radiography |
3.169. |
For film based image acquisition systems, additional factors include the type (speed and spectral response) of film–screen combination and the film processing conditions (e.g. the chemicals used and developing time and temperature). |
| Operational considerations: Radiography |
3.170. |
Mobile and portable radiographic equipment usually produce images of lower quality compared with fixed units, and should only be used for examinations where it is impractical or not medically acceptable to transfer patients to a fixed unit. |
| Operational considerations: Radiography |
3.171. |
The patient should be properly positioned and immobilized. In addition, instructions should be clear and in the language understood by the patient. |
| Operational considerations: Mammography |
3.172. |
In developing protocols for mammography, consideration of radiographic technique factors should be made as for radiography (see para. 3.166). Additional factors that should be considered include: adequate compression of the breast; tissue composition (e.g. dense glandular breasts identified on previous mammograms); and correct choice of anode and filters. Detailed guidance on appropriate choices for technique factors and additional factors is available (see Refs [111–114, 139, 155, 156]). |
| Operational considerations: Mammography |
3.173. |
For film based mammographic systems, additional factors include the type of film–screen combination and the film processing conditions (e.g. the chemicals used and developing time and temperature), as described in Refs [111–113]. |
| Operational considerations: Mammography |
3.174. |
Breast tomosynthesis is an evolving technique for which guidance for optimization is likely to become available as the modality matures. A review of features that influence image acquisition has been made in Refs [157, 158].
|
| Operational considerations: Mammography |
3.175. |
Viewing conditions are of paramount importance for both digital and film based mammography systems, and the operational performance should be meet the conditions described in paras 3.25, 3.26 and 3.45. Poor viewing conditions not only compromise the reporting of a good quality image, but they may, in a mistaken attempt to compensate for the poor viewing conditions, also lead to changes in technique factors that actually result in suboptimal image quality. For example, the use of low luminance viewing boxes may lead to radiographs being produced that have a low density with insufficient diagnostic content. Although the dose may have been reduced, there might be an unacceptable loss of diagnostic information. |
| Operational considerations: Computed tomography |
3.176. |
In developing protocols for CT, many technique factors and features should be considered which can influence the image quality and the patient dose for the examination, including: tube potential; tube current; tube current modulation with noise index; pitch; beam width; and total scan length, over ranging and over beaming for the scan. These and other factors may be optimized through the AEC system where available. The choice of protocol will be determined by the clinical question to be answered (e.g. for cardiac CT, a low dose protocol is sufficient for stratifying risk in patients with intermediate probability of coronary artery disease; whereas a higher dose contrast enhanced protocol is necessary for patients with suspected coronary artery disease). Detailed guidance on appropriate choices for these factors and features is available (see Refs [19, 62, 138, 144, 145, 147, 150, 152, 159–163]). |
| Operational considerations: Computed tomography |
3.177. |
Careful consideration should be made as to the need for multiple phase studies to answer the clinical question (e.g. in abdominal CT imaging for routine detection of liver metastases, and the use of portal venous phase acquisitions only, rather than triple phase acquisitions, namely arterial, portal venous and delayed phase acquisitions). Protocols for optimized CT procedures for common clinical conditions should be agreed, put in place and used. |
| Operational considerations: Computed tomography |
3.178. |
Consideration of use of a spiral or axial technique will depend on the indication and will have implications for image quality and dose (e.g. for diffuse lung disease a non-contiguous single slice protocol is preferred for high resolution lung CT, and it also delivers a lower patient dose). |
| Operational considerations: Computed tomography |
3.179. |
Special attention should be given to developing protocols for children adapted to body size and age [19, 145, 152]. The use of adult protocols for scanning children is inappropriate.
|
| Operational considerations: Computed tomography |
3.180. |
Improved image presentation, reconstruction algorithms and post-processing features to reduce image noise can potentially result in a protocol with reduced patient dose. An example is the use of iterative reconstruction algorithms. Care should be taken with the introduction of such algorithms to ensure that the radiation protection of the patient is optimized. |
| Operational considerations: Computed tomography |
3.181. |
Proper positioning of the patient and proper setting of the scanned anatomical area of interest should be achieved, for example CT of the thorax with both arms raised and CT of the wrist in the ‘superman position’ (i.e. with the patient lying prone with the affected arm stretched out above the head) are of considerable advantage to avoid artefacts and to reduce dose. Immobilizing devices may be used where appropriate. Special attention should be made for proper immobilization of paediatric patients by use of straps, swaddling blankets, plastic holders for the head or body, foam pads, sponges, sand bags, pillows or other objects. |
| Operational considerations: Computed tomography |
3.182. |
Irradiating the lens of the eye within the primary beam should be avoided. This may be achieved in brain scans by using a head cradle or, in some cases, tilting the gantry. |
| Operational considerations: Computed tomography |
3.183. |
For CT angiography, the use of software to detect the arrival of the contrast medium in the relevant vessel to trigger the volume acquisition has image quality advantages and avoids repeat acquisitions (e.g. detection of the contrast medium in the pulmonary artery in CT pulmonary angiography). |
| Operational considerations: Computed tomography |
3.184. |
For cardiac CT and CT angiography, the use of software to control acquisition with respect to the electrocardiograph of the patient (ECG gated or ECG triggered studies) should be considered, when appropriate, to reduce radiation dose. |
| Operational considerations: Computed tomography |
3.185. |
For hybrid imaging with CT (e.g. PET–CT and SPECT–CT), consideration should be given to the use of a low dose CT protocol to correct for PET or SPECT attenuation, which may necessitate a second diagnostic procedure of the primary area of interest or a higher dose CT protocol (often contrast enhanced) as part of the hybrid procedure. |
| Operational considerations: Computed tomography |
3.186. |
CBCT, also known as flat panel CT, C-arm CT, cone beam volume CT and digital volume tomography, is used in medical applications (diagnostic and interventional radiology, and IGRT) and dental applications. Operational aspects with respect to optimization are still evolving. Guidance is available (see Refs [164, 165]), and factors that should be considered include: tube potential; tube current–exposure time product; field of view; voxel size; and the number of projections. |
| Operational considerations: Dentistry |
3.187. |
In developing protocols for conventional intraoral radiography, factors that can influence the image quality and the patient dose include: tube potential; current; exposure time; collimation; focus to skin distance; and, for analogue systems, film speed and processing development time and temperature. Detailed guidance on appropriate choices for those factors is available (see Refs [166, 167]). |
| Operational considerations: Dentistry |
3.188. |
In developing protocols for panoramic imaging, additional factors that can influence the image quality and the patient dose include: patient positioning (e.g. jaw open or closed); collimation (e.g. for examinations of the temporomandibular joint, only those areas should be included); and for analogue systems, film speed or screen speed, and processing development time and temperature. Detailed guidance on appropriate choices for those factors is available (see Refs [166, 167]). |
| Operational considerations: Image guided interventional procedures |
3.189. |
The choice of imaging modality for guidance of interventional procedures will depend on the clinical scenario (e.g. fluoroscopic guidance for percutaneous coronary intervention and CT guidance for biopsy). Occasionally, more than one modality may be used in a single interventional procedure to improve effectiveness and safety. This may result in a lower dose when the second modality is non-ionizing (e.g. ultrasound is used to locate the renal pelvis in percutaneous nephrostomy before fluoroscopic placement of a catheter). Furthermore, the correct selection of equipment with appropriate size (and shape) of flat panel or image intensifier will improve the diagnostic image quality. |
| Operational considerations: Image guided interventional procedures |
3.190. |
Successful interventions are heavily reliant upon patient cooperation (e.g. movement may compromise the accuracy of roadmaps in the performance of aneurysm embolization in neuro-intervention). Patients should be briefed about the intervention prior to the commencement of the procedure so that they know what to expect and how to cooperate. |
| Operational considerations: Image guided interventional procedures |
3.191. |
In developing protocols for fluoroscopically guided interventional procedures, many technique factors and features should be considered, which can influence the image quality and the patient dose for the intervention, including: tube potential; tube current; use of pulsed fluoroscopy (hence pulse width and rate); dose rate mode (effectively the image intensifier or flat panel detector input air kerma rate); collimation, and collimation tracking with the distance from the focus to the detector; filtration (fixed and variable); use of magnification; total fluoroscopy time for the intervention; image acquisition dose mode (effectively input air kerma per frame for the image intensifier or flat panel detector); image acquisition frame rate; number of frames per run and the total number of acquisitions. Detailed guidance on appropriate choices for these factors and features is available (see Refs [19, 117, 140, 146, 150, 152, 168–171]). |
| Operational considerations: Image guided interventional procedures |
3.192. |
Many of the factors in para. 3.191 are automated through an algorithm driven ADRC system. Nevertheless, in setting up the algorithm, scope exists for the optimization of protection and safety through the selection of values for these parameters. For example, the input air kerma rates (for fluoroscopy) and input air kerma per frame (for image acquisition) for the image intensifier or flat panel detector are set during installation and adjusted thereafter during periodic maintenance and servicing. The values actually used for these settings can vary considerably. High rate dose modes in fluoroscopy should be used only during the minimum indispensable time necessary to the procedure. The use of magnification modes should be kept to a minimum consistent with a successful intervention. |
| Operational considerations: Image guided interventional procedures |
3.193. |
In the course of the intervention, the tube orientation and position may need to be changed. For long procedures, the area of skin upon which the X ray beam is incident should be changed during the procedure to avoid deterministic skin effects. As a default from a radiation protection perspective, it is preferable to have the X ray tube under the patient (i.e. ‘under-couch’). Steep oblique projections should be avoided. The distance between the X ray tube and patient should always be maximized to reduce patient dose. Typically, this is achieved for a vertical beam by having the table as high as possible for the primary operator. In conjunction with this, the image intensifier or flat panel detector should be positioned as close to the patient as possible. |
| Operational considerations: Image guided interventional procedures |
3.194. |
Particular paediatric considerations include: the use of special filtration; removal of the grid; and gonad protection. |
| Operational considerations: Image guided interventional procedures |
3.195. |
In developing protocols for CT guided interventional procedures, technique factors that should be considered, which can influence the image quality and the patient dose for the intervention, include: tube potential, tube current and beam width. The number of image acquisitions (tube rotations) should be kept to a minimum consistent with a successful intervention. |
| Operational considerations: Fluoroscopy |
3.196. |
Recommendations in paras 3.190–3.194 also apply to fluoroscopy used in diagnostic radiology. |
| Operational considerations: Bone densitometry |
3.197. |
Selection of the appropriate site for densitometry will take into account both the anatomical area of clinical concern as well as the likelihood of non-representative images and measurements owing to artefacts (e.g. massive vertebral osteophytes may obviate the value of lumbar densitometry). Information on best practices is given in Ref. [172]. |
| Operational considerations: Emergency radiology |
3.198. |
Special considerations for the emergency department include: judicious patient positioning that takes into account the injury or disease (e.g. a lateral shoot through projection of the hip); and CT protocols with the minimum number of acquisitions (e.g. contrast enhanced CT for polytrauma, when one acquisition only is needed for diagnosis and expedience). |
| Calibration: General |
3.199. |
In accordance with para. 1.46 of GSR Part 3 [3], the dosimetric quantities and units of the ICRU are to be used for diagnostic radiology and image guided interventional procedures [10, 12]. Information on best practices in dosimetry in diagnostic radiology is given in Refs [11, 173, 174]. |
| Calibration: General |
3.200. |
Calibration requirements for medical radiological equipment and dosimetry equipment are established in para. 3.167 of GSR Part 3 [3]. Responsibility is assigned to the radiology facility’s medical physicist. After the initial calibration, the intervals for periodic calibrations might differ, depending on the complexity of the medical radiological equipment. Relating to calibrations are the constancy tests on equipment performance performed as quality control tests. These are described in paras 3.235, 3.237 and 3.238. |
| Calibration: Medical radiological equipment |
3.201. |
In diagnostic radiology, including the use of medical radiological equipment for simulation of radiation therapy, treatment verification systems and hybrid imaging systems, and for image guided interventional procedures, ‘source calibration’ is to be interpreted as the measurement of certain dosimetric quantities that are modality dependent and which should be carried out in reference conditions. |
| Calibration: Medical radiological equipment |
3.202. |
For diagnostic radiographic and fluoroscopic medical radiological equipment, including conventional radiation therapy simulators, the dosimetric quantities are: incident air kerma, in Gy; incident air kerma rate, in Gy·s-1; and air kerma–area product, in Gy·m2 (some manufacturers use μGy·m2 or mGy·cm2 or Gy·cm2 ). |
| Calibration: Medical radiological equipment |
3.203. |
In CT, the dosimetric quantities are (see also Refs [10–12, 173–176]): CT air kerma index, usually in mGy. In many States, the more colloquial term computed tomography dose index (CTDI) is used, and is accepted by the ICRU [12].
Weighted CT air kerma index, usually in mGy, which is the CT air kerma calculated from measurements at the centre and periphery of a standard polymethylmethacrylate CT head or body phantom. As in (a), this quantity is often simply called the weighted CTDI.
Volume CT air kerma index, usually in mGy, which takes into account the helical pitch or axial scan spacing. As in (a), this quantity is often simply called volume CTDI.
CT air kerma–length product, usually in mGy·cm. In many States, the more colloquial term dose–length product is used, and is accepted by the ICRU [12].
|
| Calibration: Medical radiological equipment |
3.204. |
In mammography, the three dosimetric quantities used are incident air kerma, entrance surface air kerma and mean glandular dose, usually in mGy [10, 11]. |
| Calibration: Medical radiological equipment |
3.205. |
Measurements of these dosimetric quantities, when being used to calibrate or characterize a given X ray, CT or mammography unit output or performance, should be made for a range of representative technique factors used clinically, and following recognized protocols such as those in Ref. [11]. |
| Calibration: Dosimetry instrumentation |
3.206. |
Dosimetry instrumentation used at a radiology facility should be calibrated at appropriate intervals. A period of not more than two years is recommended (see also para. 3.244 on quality assurance). |
| Calibration: Dosimetry instrumentation |
3.207. |
Paragraph 3.167(d) of GSR Part 3 [3] requires that the calibration of dosimetry instrumentation be traceable to a standards dosimetry laboratory. Ideally, this would be the national standards dosimetry laboratory (primary or secondary) in the State concerned, with access either directly or through a duly accredited calibration facility. However, it may be necessary for dosimetry instruments to be sent to another State or region if there is no national standards dosimetry laboratory in the State or region where the instruments are used. At present, only some of the secondary standards dosimetry laboratories of the IAEA/WHO Network of Secondary Standards Dosimetry Laboratories (SSDL Network) provide calibration services using diagnostic radiology spectra and dose rates representative of clinical practice. However, since dosimetry accuracy is not as critical in diagnostic radiology as in radiation therapy, calibrations with comparable radiation qualities should be sufficient. Alternatively, the regulatory body might accept instrument manufacturers’ calibrations as described in the ‘certificate of calibration’ issued by the instrument manufacturer, provided that the manufacturer operates or uses a calibration facility that is itself traceable to a standards dosimetry laboratory and appropriate calibration conditions have been used. This certificate should state the overall uncertainty of the calibration coefficient. |
| Calibration: Dosimetry instrumentation |
3.208. |
Records of calibration measurements and associated calculations, including uncertainty determinations (uncertainty budgets), should be maintained as described in para. 3.272. Information on best practices in performing uncertainty determinations for several modalities is given in Refs [11, 152]. |
| Calibration: Dosimetry instrumentation |
3.209. |
There is a role for cross-calibration of dosimeters, where the radiology facility’s dosimeters that have been officially calibrated are used to check or compare with other dosimeters. This is particularly important for field air kerma–area product meters, which should be calibrated (or cross-calibrated) against a reference air kerma–area product meter or air kerma dosimeter in situ in the clinical environment rather than in a standards dosimetry laboratory environment [11]. It might also be done when a radiology facility has many dosimeters, and to calibrate all dosimeters could be too costly. Cross-calibration can also be utilized as a constancy test as part of periodic quality control tests. |
| Dosimetry of patients: General |
3.210. |
Paragraph 3.168 of GSR Part 3 [3] requires that registrants and licensees of radiology facilities ensure that patient dosimetry be performed in diagnostic radiology and image guided interventional procedures and that typical doses to patients for radiological procedures be determined. Knowledge of the typical doses at a facility forms the basis for applying methods of dose reduction as part of optimization of protection and safety. It also enables the radiology facility to use DRLs (see paras 3.224–3.231) as another tool for the optimization of protection and safety. |
| Dosimetry of patients: General |
3.211. |
Clearly, the more radiological procedures at the radiology facility for which typical doses are known, the better the basis for the optimization of protection and safety. GSR Part 3 [3] requires determination of typical doses for common radiological procedures in radiology facilities. The procedures that are considered to fall into this category will vary from facility to facility, and State to State, but common core examinations generally include the following: Radiography: head, chest, abdomen and pelvis.
CT: head, chest, abdomen and pelvis, for specified clinical indications.
Fluoroscopy: barium swallow and barium enema.
Mammography: craniocaudal and mediolateral oblique.
Dentistry: intraoral, panoramic and CBCT.
Bone densitometry (DXA): spine and hip.
|
| Dosimetry of patients: General |
3.212. |
For image guided interventional procedures, typical doses for the broad types of procedure performed at the facility should be ascertained. For example, an interventional cardiology facility would characterize typical doses for percutaneous coronary interventions, including percutaneous transluminal coronary angioplasty. A facility performing neurological procedures might characterize typical doses for diagnostic cerebral angiograms and for embolization interventions. Other image guided interventional procedures might include endoscopic retrograde cholangiopancreatography and transjugular intrahepatic portosystemic shunt. |
| Dosimetry of patients: General |
3.213. |
The term ‘typical dose’, as used in para. 3.168 of GSR Part 3 [3], is the median or average dose for a representative sample of normal size patients, at clinically acceptable image quality. Patient size has a large influence on dose, so some selection or grouping of patients is recommended. Such groupings include ‘standard adult’, often based on an average mass of 70 kg with a range of ±20 kg. Groupings for children have sometimes been based on age, such as newborn (0 years), infant (1 year), small child (5 years), child (10 years) and teenager (15 years), but more recently size specific groupings are being recommended and used, for example by using body mass intervals [14]. Patient size groupings should be adopted that correspond to the groupings used for the DRLs in the State or region. The sample size used for each patient grouping and radiological procedure should be of sufficient size to assure confidence in the determination of the typical dose. A representative sample of 10–20 patients per procedure type is needed for non-complex examinations such as radiography and CT, preferably 20–30 patients for complex procedures such as fluoroscopy and fluoroscopically guided procedures, and 50 patients for mammography [14] (see also paras 2.39–2.41). |
| Dosimetry of patients: General |
3.214. |
The dose in the term ‘typical dose’, as used in para. 3.168 of GSR Part 3 [3], means, for the given radiological procedure, an accepted dosimetric quantity as described in paras 2.40 and 3.202–3.204. For particular reasons (e.g. for risk estimation or for collective dose estimation), the dose to a particular organ or the effective dose can be estimated from the typical dose. |
| Dosimetry of patients: General |
3.215. |
Patient dosimetry to determine typical doses should be carried out in conjunction with an assessment of the diagnostic image quality. Exposure alone is not meaningful if it does not correspond to images that are adequate for an accurate diagnosis. Therefore, patients included in the sample used for determining typical doses should only be those whose radiological procedure resulted in acceptable image quality. |
| Dosimetry of patients: General |
3.216. |
The results of the surveys used to determine typical doses at the radiology facility should be used as part of the ongoing review of the optimization of protection and safety at the facility, and should be used for comparison with established DRLs (see paras 2.34, 2.45 and 3.224–3.231). The results should also be submitted to the organization in the State or region that is responsible for establishing and reviewing national or regional DRLs. Patient dosimetry surveys, required by GSR Part 3 [3], should take place at intervals of no more than five years and preferably no more than three years. Another trigger for a survey would be the introduction of new equipment or technology into the radiology facility or when significant changes have been made to the protocols or the equipment. |
| Dosimetry of patients: General |
3.217. |
Sometimes, patient dosimetry in diagnostic radiology or image guided interventional procedures may be required for specific individual patients, either through measurements or calculations. Reasons might include an unintended or accidental medical exposure, where an estimation of patient doses is required as part of the investigation and report (see para. 3.265), or because there is a need to estimate the dose to an embryo or fetus (see para. 3.161). |
| Dosimetry of patients: General |
3.218. |
There are several indirect and direct methods to estimate patient dose in diagnostic radiology and image guided interventional procedures. Methodologies for these determinations are explained in detail in Refs [10–12, 171, 173–178] and are summarized in the following: Estimations based on incident air kerma or entrance surface air kerma measurements corrected for the techniques used (e.g. X ray tube potential, current and time, and source–skin distance). This approach can be used in radiography (medical and dental), fluoroscopy and mammography.
Estimations based on measured air kerma–area product. This approach can be used in radiography (medical and dental), fluoroscopy and CBCT.
Estimations based on measurements of CT air kerma index and CT air kerma–length product. This approach can be used for CT.
Reported values of dose quantities from DICOM headers or the DICOM radiation dose structured reports. The accuracy of the reported dose quantities should have been validated in acceptance testing and commissioning and by means of quality assurance procedures as explained in para. 3.244. This approach is applicable to all digital modalities.
Direct measurements for selected organs, such as the skin for interventional procedures. For this, thermoluminescent dosimeters and optical stimulated luminescent dosimeters as well as radiochromic or silver halide film can be used.
In the case of CT, size specific dose estimates can be made, where CT air kerma index values are corrected by taking into consideration the size of the patient using linear dimensions measured on the patient or patient images [12, 177].
|
| Dosimetry of patients: General |
3.219. |
When necessary, organ doses can be derived from the quantities mentioned in para. 3.218 by using conversion coefficients derived from Monte Carlo codes applied to anatomical models. Methods for doing this are described in Ref. [11]. |
| Dosimetry of patients: Specific considerations for image guided interventional procedures |
3.220. |
For interventional procedures using X rays, in addition to the quantities that relate to stochastic effects, such as air kerma–area product, the cumulative doses to the most exposed areas of skin should be monitored because of the potential for reaching the threshold for tissue effects in complicated cases [179, 180]. |
| Dosimetry of patients: Specific considerations for image guided interventional procedures |
3.221. |
The determination of the dose to the most exposed area of skin is not straightforward, since exposure parameters and projection angles change during the procedure and the most exposed area cannot always be anticipated. This makes knowledge of the distribution of the dose over the skin (sometimes called ‘dose mapping’ over the skin) necessary. A comprehensive review of approaches to dose mapping and to determining the most exposed area of the skin is given in Ref. [171]. |
| Dosimetry of patients: Specific considerations for image guided interventional procedures |
3.222. |
An established method for dose mapping uses low sensitivity X ray films, such as films used in radiation therapy and radiochromic films. However, determination of the dose is only possible after the procedure. |
| Dosimetry of patients: Specific considerations for image guided interventional procedures |
3.223. |
The cumulative reference air kerma at the patient entrance reference point, defined as the kerma in air at 15 cm from the isocentre in the direction of the X ray tube [69], either displayed during the procedure or obtained from the DICOM header, may be used as a conservative estimate for peak skin dose. The degree of overestimation depends on several factors, including how often the beam projection was changed. The cumulative reference air kerma gives the least overestimation when most of the radiation is delivered in just one beam projection. The accuracy of the reported cumulative reference air kerma should have been validated in acceptance testing and commissioning and by means of quality assurance procedures, as explained in para. 3.244.
|
| Diagnostic reference levels |
3.224. |
Paragraphs 3.168 and 3.169 of GSR Part 3 [3] require that patient dosimetry surveys be performed for the diagnostic procedures at a radiology facility, as described in paras 3.210–3.219, and that these results be compared with the established DRLs for the State or region. The purpose is to ascertain whether or not the typical dose for the facility for a given radiological procedure compares favourably with the value of the DRL for that radiological procedure. Guidance on establishing national or regional DRLs is given in paras 2.34–2.45. |
| Diagnostic reference levels |
3.225. |
A review of optimization of protection and safety for that particular radiological procedure is triggered if the comparison shows that the typical dose for the facility exceeds the DRL, or that the typical dose for the facility is substantially below the DRL and it is evident that the exposures are not producing images of diagnostic usefulness or are not yielding the expected medical benefit to the patient. |
| Diagnostic reference levels |
3.226. |
Given the uncertainties in determining the typical dose for a facility (see paras 3.213 and 3.214), questions can arise over whether or not a DRL has really been exceeded. Some States adopt an algorithmic approach, for example where the typical dose for the facility, minus two times its standard error, should be greater than the value of the DRL [16]. A simpler approach, based purely on the
typical value for the facility, may be sufficient, as the purpose is to identify the need for a review. |
| Diagnostic reference levels |
3.227. |
No individual patient’s dose should be compared with a DRL. It is the typical dose for the facility, as determined by the representative patient sample, which should be compared. |
| Diagnostic reference levels |
3.228. |
Furthermore, the comparison should not simply determine whether the radiology facility complies with the DRL. DRLs are not dose limits. DRLs should be used for the comparison exercise in the review process of optimization of protection and safety to identify practices that warrant further investigation. |
| Diagnostic reference levels |
3.229. |
The review of how the given radiological procedure is being performed and of the optimization of protection and safety, triggered by the DRL comparison, might conclude that there are valid reasons supported by sound clinical judgement why the radiology facility has a typical dose that exceeds the DRL. These reasons should be documented as part of the facility’s programme of quality assurance. Adequateness of image quality should always be taken into account. On the other hand, the review might identify areas for improvement resulting in revised protocols for that radiological procedure. The results of the DRL comparison and any ensuing review and actions should be documented as part of the facility’s programme of quality assurance. |
| Diagnostic reference levels |
3.230. |
The fact that the typical dose for a radiological procedure at a radiology facility is less than the DRL for that procedure does not necessarily mean that optimization of protection and safety for that radiological procedure has been fully achieved. DRLs are only one of the tools for optimization, and are aimed specifically at identifying the outliers in performance. |
| Diagnostic reference levels |
3.231. |
The regulatory body in a given State may specify frequencies for performing DRL comparisons. Otherwise, the general guidance for patient dosimetry, described in para. 3.216, would be applicable. |
| Quality assurance for medical exposures |
3.232. |
Paragraph 3.170 of GSR Part 3 [3] requires that radiology facilities have in place a comprehensive programme of quality assurance for medical exposures. General guidance on the management system is given in paras 2.138–2.149, and it is reiterated here that the programme of quality assurance for medical exposures should fit in with, and be part of, the wider management system at the facility.
|
| Quality assurance for medical exposures |
3.233. |
The purpose of the programme of quality assurance for medical exposures is to help to ensure successful optimization of protection and safety in the radiology facility and to minimize the occurrence of unintended and accidental medical exposures. |
| Quality assurance for medical exposures |
3.234. |
The complexity of the programme of quality assurance for medical exposures will depend on the type of facility. A dental practice with only intraoral radiography will have a simpler programme compared with a facility that offers all modalities of diagnostic radiology as well as image guided interventional procedures. Nonetheless, most of the elements of the programme are common, and it is more in the degree of application that there are differences. Paragraph 3.171 of GSR Part 3 [3] establishes the common elements of the programme. |
| Quality assurance for medical exposures |
3.235. |
Measurements on medical radiological equipment are one of the components of the comprehensive programme of quality assurance. Acceptance tests are required for new or significantly refurbished or repaired equipment, or after the installation of new software or modification of existing software that could affect protection and safety. The acceptance test should be followed immediately by commissioning, and then ongoing periodic quality control tests, including constancy tests. The purpose is to ensure that, at all times, all medical radiological equipment performs correctly, accurately, reproducibly and predictably. Acceptance and commissioning tests should be performed in the same way for equipment and software that has been donated. |
| Quality assurance for medical exposures |
3.236. |
Depending on the equipment purchase agreement, acceptance tests can be performed by the manufacturer in the presence of the local medical physicist and the radiological medical practitioner representing the user, or, if acceptable to the manufacturer and the purchaser, by a medical physicist jointly with the manufacturer. The process should involve verification of all specifications and features of the equipment. |
| Quality assurance for medical exposures |
3.237. |
After acceptance and before clinical use on patients, commissioning should be carried out by, or under the supervision of, the medical physicist. Commissioning should include measurements of all parameters and conditions of use that are expected in clinical use, including setting up and validating image acquisition protocols. For most modalities (CT, image guided interventional procedures, tomosynthesis, mammography, radiography and fluoroscopy), the medical physicist should be directly involved in the measurements, calculations and interpretation of data to characterize the equipment’s performance. For the least complex modalities (dental radiography and DXA), the medical physicist should provide documented advice on how the commissioning should be performed. During commissioning, the baseline for subsequent constancy tests is established. |
| Quality assurance for medical exposures |
3.238. |
In addition to the acceptance testing and commissioning, para. 3.171 of GSR Part 3 [3] requires, periodically and after any major maintenance procedure or upgrade, the measurement of physical parameters of medical radiological equipment. There are many published reports from international and national organizations and national and regional professional bodies giving detailed guidance on the performance tests and quality control tests that should be performed on the various modalities, including recommended frequencies (see Refs [104, 105, 109–114, 156, 161, 166, 167, 170–173, 181–201]). In addition, many of these organizations and professional bodies publish on their web sites new or updated publications on the topic. The regulatory body may have its own specific requirements for the tests that should be performed, their frequencies and the competence of the specialists involved. Such specific requirements should be established with consultation between the regulatory body and the relevant professional bodies. |
| Quality assurance for medical exposures |
3.239. |
While traditional approaches to constancy testing are based on measurements of technical parameters for the system or using test objects and phantoms, it is likely that in the future clinically derived data could be used in the monitoring of equipment and in ensuring consistency in clinical practice. For example, a particular region of an anatomical image could be analysed to produce an index of noise performance. |
| Quality assurance for medical exposures |
3.240. |
Quality control tests should also be performed on other equipment or devices that have an impact on the successful outcome of the radiological procedure. Such equipment and devices include, but are not limited to: film processors, darkrooms and cassettes for facilities using film based imaging; flat detectors for DR systems; CR imaging plates and CR readers for facilities with CR systems; and view boxes, workstations, and display and interpretation rooms. Many of the references given in para. 3.238 are applicable here. |
| Quality assurance for medical exposures |
3.241. |
The results of the quality control tests should be compared with established tolerance limits. These limits may have been established to ensure compliance with a regulatory requirement for the performance of particular physical parameters or they may be set on the basis of recommended values given in published reports, such as those referenced in para. 3.238. Paragraph 3.171(b) of GSR Part 3 [3] requires the implementation of corrective actions if the measured values fall outside established tolerance limits. Such corrective actions are likely to include maintenance or servicing of the equipment, and hence a preventive maintenance programme should be put in place at the radiology facility. In some cases, the equipment might be outside the tolerance limits by a significant amount and the equipment should be immediately taken out of clinical use and not returned until servicing has taken place and it has been ascertained that the equipment now meets the performance requirements. |
| Quality assurance for medical exposures |
3.242. |
The programme of quality assurance for medical exposures in the radiology facility should include the use of checks to ensure that the facility’s protocols and procedures for imaging and interventional procedures, including radiation protection and safety, are being followed. The periodic review of the protocols and procedures themselves is part of the radiological review at the facility (see paras 3.269–3.271). In addition, a review of imaging procedures may have been triggered by a comparison with DRLs (see paras 3.224–3.231). |
| Quality assurance for medical exposures |
3.243. |
As part of the programme of quality assurance for medical exposure, ‘repeat and reject analysis’ should be performed on a periodic basis. Further guidance is given in Refs [48, 111, 153]. |
| Quality assurance for medical exposures |
3.244. |
Paragraph 3.171(e) of GSR Part 3 [3] specifically requires that periodic checks of the calibration and conditions of operation of dosimetry equipment and monitoring equipment be part of the programme of quality assurance. This is to ensure that such instrumentation has a current calibration, typically conducted within the last two years (see para. 3.206), and that it is functioning correctly. The programme of quality assurance for medical exposures should establish a frequency for calibration for each instrument and a set of quality control checks on the operation of each instrument to be performed at set intervals. This applies to stand alone dosimetry equipment and to dosimeters integrated into the medical radiological equipment, such as air kerma–area product meters in fluoroscopic systems, and to software of the medical radiological equipment itself that calculates, displays and reports dose metrics such as CT air kerma index and air kerma–length product in CT and reference air kerma at the patient entrance reference point in image guided interventional procedures. Phantoms used in quality assurance and dosimetry should fulfil the requirements specified in the corresponding international standards. |
| Quality assurance for medical exposures |
3.245. |
Maintaining records is a crucial aspect of the programme of quality assurance for medical exposures. This includes the procedures used in the programme and the results of the quality control tests, the dosimetry surveys, the DRL comparisons, the corrective actions, and the investigations of unintended and accidental medical exposures. When planning and developing an effective programme of quality assurance, the licensee should recognize that it demands strong managerial commitment and support in the form of training and allocation of time, personnel and equipment resources. The regulatory body, in its inspections of a radiology facility, should review the records of the programme of quality assurance for medical exposures. |
| Quality assurance for medical exposures |
3.246. |
In line with standard practices for quality management, para. 3.172 of GSR Part 3 [3] requires that “regular and independent audits are made of the programme of quality assurance for medical exposures, and that their frequency is in accordance with the complexity of the radiological procedures being performed and the associated risks.” Such audits may be external audits or internal audits. Internal audits are usually logistically simpler to conduct, while an external audit generally has the advantage of bringing in an outside perspective. The audit of the programme of quality assurance for medical exposures can be incorporated into more comprehensive audits of the management system performed by the licensee. Furthermore, the results of the audit of the programme of quality assurance for medical exposures will be a major input into the radiological review performed at the facility (see paras 3.269–3.271). |
| Dose constraints: Carers and comforters |
3.247. |
Some diagnostic radiological procedures, particularly of children, can be better performed with the assistance of a carer or comforter, for example a relative in the case of a paediatric patient, or a relative or friend for a disabled or very elderly or very ill patient. In these circumstances, the carer or comforter will be exposed, usually to a low dose. |
| Dose constraints: Carers and comforters |
3.248. |
Paragraph 3.153 of GSR Part 3 [3] states that: |
| Dose constraints: Carers and comforters |
3.249. |
The radiation protection afforded the carer or comforter should be optimized, and, as part of this process, dose constraints are required to be applied (para. 3.173 of GSR Part 3 [3]). These are the dose constraints established by government, as a result of consultation with the health authority, relevant professional bodies and the regulatory body, as required by para. 3.149(a)(i) of GSR Part 3 [3] (see also paras 2.48 and 2.49). |
| Dose constraints: Carers and comforters |
3.250. |
Written protocols should be drawn up for implementing measures for the optimization of protection and safety for carers and comforters who hold patients during radiological procedures. The measures should utilize the basic methods for radiation protection (i.e. time, distance and shielding). The protocols should include the following: Methods to avoid the need for holding patients, for example the administration of sedatives (especially for long procedures such as CT examinations) and the use of infant restraints.
Criteria specifying which carers and comforters are allowed to hold patients, for example friends and relatives, provided that they are not pregnant, but not employees of the facility, such as porters and nurses (see also para. 2.49).
Methods for positioning and protecting the carer or comforter so that his or her exposure is as low as reasonably achievable, for example by ensuring that the carer or comforter is not in the direct beam of the radiation device and that appropriate personal protective equipment is used, for example a protective apron or ancillary shields of a specified lead equivalence.
The values of the dose constraints to be applied (see para. 2.49) depend on the radiological exam or intervention; a common value is 5 mSv per event, as stated in para. 2.49. Although it is unlikely that a child, such as a child closely related to the patient, would be a carer or comforter for a diagnostic radiological procedure, in cases where this is unavoidable, his or her dose should be constrained to less than 1 mSv.
|
| Dose constraints: Carers and comforters |
3.251. |
The licensee should be able to demonstrate that the effective dose to the carer or comforter, by applying the protocols, is unlikely to exceed the dose constraint. It is relatively straightforward to estimate effective doses to carers and comforters from measurements of the ambient dose equivalent rates at the positions where they will be situated. These determinations should be made in advance to ensure that dose constraint is not exceeded. Therefore, individual dose monitoring is normally not necessary. |
| Dose constraints: Volunteers in biomedical research |
3.252. |
Some individuals will undergo diagnostic radiological procedures as part of their voluntary participation in an approved programme of biomedical research (see para. 2.99). Part of the approval process for the biomedical research will have been the setting of dose constraints for the radiological procedures (see para. 2.100). When the volunteer presents himself or herself at the radiology facility, he or she is to be afforded the same radiation protection as if he or she were a patient ready to undergo a radiological procedure, but with the additional restriction that his or her exposure will be subject to a dose constraint, either a nationally established dose constraint or a dose constraint specified by the ethics committee that approved the biomedical research programme (see paras 2.50, 2.99 and 2.100). |
| Pregnant patients |
3.253. |
Patients who are pregnant form a special subgroup of patients that should be given particular consideration with respect to radiation protection. These considerations are described in para. 3.147(a) with respect to justification and para. 3.161 with respect to optimization. None of these considerations can take place if it is not known whether the patient is pregnant. Therefore, it is crucial, as is required in paras 3.175 and 3.176 of GSR Part 3 [3], for the radiology facility to have in place means for ensuring that the pregnancy status of patients is known. |
| Pregnant patients |
3.254. |
The first approach is through the posting of clear signs (possibly including a pictorial representation of pregnancy) in languages easily understood by the people using the radiology facility, posing the question ‘Are you pregnant or possibly pregnant?’ and ‘If so, please tell the staff’. Such signs should be posted widely in the facility, including in waiting rooms and cubicles. The second approach is to ask patients directly whether they are or might be pregnant. This might not always be so easy given social and cultural sensitivities, but it should be done when necessary. |
| Pregnant patients |
3.255. |
Neither of the approaches described in para. 3.254 will work if the patient does not know whether she is pregnant. For this reason, para. 3.176 of GSR Part 3 [3] has an additional requirement on facilities to “ensure that there are procedures in place for ascertaining the pregnancy status of a female patient of reproductive capacity before the performance of any radiological procedure that could result in a significant dose to the embryo or fetus”. Such radiological procedures would include those that involve primary beam irradiation of the abdomen or pelvis area delivering relatively high patient doses directly to the embryo or fetus, or to volumes near the uterus such that significant scatter radiation reaches the embryo or fetus. Cooperation with the referring medical practitioner, through standard requests for pregnancy status for specified procedures, is one approach. The referral form should include a ‘tick box’ for pregnancy status. In case of doubt, a pregnancy test or a determination of hormone levels to assess menopausal status can be carried out. |
| Prevention of unintended and accidental medical exposures |
3.256. |
Paragraph 3.179 of GSR Part 3 [3] states that: |
| Prevention of unintended and accidental medical exposures |
3.257. |
Minimization of the likelihood of unintended or accidental medical exposures in diagnostic radiology and image guided interventional procedures can be brought about by: The introduction of safety barriers at identified critical points in the process, with specific quality control checks at these points. Quality control should not be confined to physical tests or checks but can include actions such as the correct identification of the patient.
Actively encouraging a culture of always working with awareness and alertness.
Providing detailed protocols and procedures for each process.
Providing sufficient staff who are educated and trained to the appropriate level, and an effective organization, ensuring reasonable patient throughput.
Continuous professional development and practical training and training in applications for all staff involved in providing radiology services.
Clear definitions of the roles, responsibilities and functions of staff in the radiology facility that are understood by all staff.
|
| Prevention of unintended and accidental medical exposures |
3.258. |
Preventive measures should include reporting of incidents and near incidents, analysis and feedback, including lessons from international experience [123]. Preventive measures should also include checking of the robustness of the safety system of the facility against reported incidents (see Ref. [123] for a review of case histories from a collection of unintended and accidental medical exposures in image guided interventional procedures). |
| Prevention of unintended and accidental medical exposures |
3.259. |
In addition to the guidance in paras 3.256–3.258, the following three-step strategy (commonly called ‘prospective risk management’) can help to prevent unintended and accidental medical exposures in a radiology facility: Allocation of responsibilities to appropriately qualified health professionals only and ensuring that a management system is in place that includes radiation protection and safety;
Use of the lessons from unintended and accidental medical exposures to test whether the management system, including for radiation protection and safety, is robust enough against these types of event;
Identification of other latent risks by posing the questions ‘What else could go wrong?’ or ‘What other potential hazards might be present?’ in a systematic, anticipative manner for all steps in the diagnostic and image guided interventional radiology process.
|
| Investigation of unintended and accidental medical exposures |
3.260. |
The events that constitute unintended or accidental medical exposures are detailed in para. 3.180 of GSR Part 3 [3]. Unintended and accidental medical exposures can occur in all imaging procedures; however, the consequences in CT may be more severe and in image guided interventional procedures may be even more severe [123, 159, 160]. |
| Investigation of unintended and accidental medical exposures |
3.261. |
Exposure of the wrong patient or the wrong body part is always a possibility in a radiology facility. Many patients have similar names, for example, or patients might not have a clear understanding of what procedures are meant to take place. Procedures should be put in place that consist of several independent methods of patient identification, and verification of requisition of the examination and of the orientation of the patient. |
| Investigation of unintended and accidental medical exposures |
3.262. |
One of the events requiring investigation is when the exposure was substantially greater than was intended. This situation might occur when the radiological procedure did not go according to plan, for example: the AEC in radiography might not have terminated the exposure when expected because the wrong sensors had been selected or there had been a hardware malfunction; or one or more of the technique factors in the examination protocol, for example for a CT examination, had been incorrectly set, giving a much higher dose than intended. |
| Investigation of unintended and accidental medical exposures |
3.263. |
Another event that should be investigated is the inadvertent exposure of the embryo or fetus in the course of a radiological procedure, where at the time of the procedure it was not known that the woman was pregnant. |
| Investigation of unintended and accidental medical exposures |
3.264. |
Radiation injuries will continue to occur in image guided interventional procedures. A given procedure performed in accordance with the facility’s protocol still has the potential to result in tissue effects because of difficulties with the particular patient. However, most reported cases of severe radiation injuries involving ulceration and necrosis have been associated with unnecessary and extreme exposure conditions, such as: (i) a very short distance between the X ray source and the patient; (ii) the use of a high dose rate mode for much longer than necessary; (iii) a fixed projection exposing the same area of skin; and (iv) a malfunction of the AEC system. These situations cannot be considered to be normal, their occurrence can be avoided and their severity can be substantially reduced by optimization; they should be considered accidental medical exposures and should be investigated. Facilities at which image guided interventional procedures are performed should have systems in place for identifying patients who may be at risk of late radiation injuries, typically based on estimates of peak skin dose, cumulative reference air kerma or air kerma–area product, which take account of the fact that patients have different sensitivities to radiation. For these patients, information should be added to their medical records so that appropriate observation and follow-up is ensured. For example, it is recommended that patients with estimated skin doses of 3 Gy should be followed up 10–14 days after exposure [123]. Further information on trigger levels for patient follow-up are available on the SAFRAD web site. Any resulting radiation injury should receive appropriate medical attention. |
| Investigation of unintended and accidental medical exposures |
3.265. |
Paragraph 3.181 of GSR Part 3 [3] establishes what is required during the course of the investigation. This includes calculation or estimation of patient doses, which should be performed by a medical physicist, and notification of the event to the patient’s referring medical practitioner. A record of the calculation method and results should also be placed in the patient’s file. When required, counselling of the patient should be undertaken by an individual with appropriate experience and clinical knowledge. In the particular case of inadvertent exposure of the embryo or fetus, further detailed advice is given in Ref. [124]. |
| Investigation of unintended and accidental medical exposures |
3.266. |
The investigation of unintended and accidental medical exposures, as required by paras 3.180 and 3.181 of GSR Part 3 [3], has three main purposes. The first is to assess the consequences for the patients affected and to provide remedial and health care actions if necessary. The second is to establish what went wrong and how to prevent or minimize the likelihood of a recurrence in the radiology facility (i.e. the investigation is for the facility’s benefit and the patients’ benefit). The third purpose is to provide information to other persons or other radiology facilities. Dissemination of information about unintended and accidental medical exposures and radiation injuries (e.g. see Refs [123, 179, 202, 203]) has greatly contributed to increasing awareness and improving methods for minimizing the occurrence of radiation injuries. The regulatory body and/or the health authorities could disseminate information on significant events reported to them and on the corrective actions taken, so that other facilities might learn from these events. Independently from any legal requirement for reporting to the regulatory body, the implementation of voluntary and anonymous safety reporting and learning systems can significantly contribute to improving safety and safety culture in health care. This includes participation in voluntary international or national databases designed as educative tools. One such database for image guided interventional procedures is the SAFRAD reporting system. Facilities performing image guided interventional procedures should participate in SAFRAD or similar databases. |
| Investigation of unintended and accidental medical exposures |
3.267. |
Paragraph 3.181 of GSR Part 3 [3] establishes requirements for the reporting (in writing) of significant events to the regulatory body and, if appropriate, to the relevant health authority. The regulatory body may specify its own requirements for the reporting of events by registrants and licensees. It is difficult to quantify the term ‘significant’: specification of a numerical trigger value immediately creates an artificial distinction between values immediately below that value (and hence would not be reported) and those just above the value (which would be reported). However, the attributes of significant events can be elaborated, and events with one or more of these attributes should be reported to the regulatory body and the health authority. Such attributes would include the occurrence of, or the potential for, serious unintended or unexpected health effects due to radiation exposure, the likelihood of a similar event occurring in other radiology facilities, a large number of patients having been affected, and gross misconduct or negligence by the responsible health professionals. As stated in para. 3.266, one of the roles of the regulatory body for such a reported event is to disseminate information on the event and any lessons identified to all potentially affected parties, typically other radiology facilities and relevant professional bodies, but also in some cases manufacturers, suppliers and maintenance companies. |
| Investigation of unintended and accidental medical exposures |
3.268. |
Irrespective of whether the event is also reported to the regulatory body, feedback to staff should be provided in a timely fashion and, where changes are recommended, all staff should be involved in bringing about their implementation. |
| Radiological review |
3.269. |
Paragraph 3.182 of GSR Part 3 [3] requires that radiological reviews be performed periodically at the radiology facility. This involves considering both justification and optimization aspects of radiation protection. For the latter, the results of the programme of quality assurance for medical exposures, including the periodic independent audit, will be a significant input to the process. As described in paras 2.148 and 2.149, the wider clinical audit could include the radiological review with its assessment of the effective application of the requirements for justification and optimization in the facility for the radiological procedures being performed [48]. |
| Radiological review |
3.270. |
To facilitate compliance with para. 3.182 of GSR Part 3 [3] and to learn from periodic radiological reviews, the methodology used, the original physical, technical and clinical parameters considered and the conclusions reached should be documented and taken into account prior to any new review that may result in an update of the radiology facility’s policies and procedures. |
| Radiological review |
3.271. |
Radiological reviews should consider changes in patient management that result from the diagnostic or interventional procedure, the effect of introducing new technologies on efficiency and cost, and comparisons of different imaging modalities and of protocols for the same pathologies. |
| Records |
3.272. |
Records should be in place to demonstrate ongoing compliance with radiation protection requirements. Paragraphs 3.183–3.185 of GSR Part 3 [3] establish the requirements for maintaining personnel records, records of calibration, dosimetry and quality assurance, and records of medical exposure. These records are required to be kept for the period specified by the regulatory body. In the absence of such a requirement, a suggested period for keeping records is ten years. In the case of children, records should be kept for a longer time. |
| Records |
3.273. |
Public exposure can arise from the performance of diagnostic radiology and image guided interventional procedures for persons in and around the radiology facility. |
| Records |
3.274. |
The requirements for public protection established in paras 3.117–3.123, 3.125–3.129 and 3.135–3.137 of GSR Part 3 [3] apply to radiology facilities. This subsection contains guidance that is specific to radiology facilities. More general and comprehensive guidance on radiation protection of the public is given in GSG-8 [24]. |
| Records |
3.275. |
Persons who will be undergoing a radiological procedure are also considered members of the public during the time when the radiological procedure is not taking place, for example, while they are sitting in the waiting room. Similarly, for carers and comforters any exposure incurred other than during the radiological procedure in which they are involved will be public exposure. |
| Records |
3.276. |
Members of the public also include visitors, such as persons delivering goods or supplies, sales personnel, accompanying persons and other patients in the facility. |
| External exposure |
3.277. |
The primary means for protecting the public from external exposure is the shielding in place at the radiology facility (see paras 3.18–3.24), which should be sufficient so that public exposure resulting from being in any immediately adjacent areas, including accessible rooms above and below, is in compliance with the public dose limits, and preferably less than any dose constraint that the regulatory body may have applied (see paras 2.16 and 2.46). |
| External exposure |
3.278. |
Particular consideration should be given to persons in the radiology facility who are not undergoing a radiological procedure, but are in the vicinity when mobile radiography is being performed in their ward or area, or when fixed radiography is being performed in an open area, such as in an emergency department. In these cases, a combination of distance, placement of mobile shielding and careful control of the X ray beam direction should ensure that appropriate public radiation protection is being afforded. |
| Control of access |
3.279. |
Access to areas where radiation is being used should be controlled to ensure doses to visitors are below the dose limits and constraints for the public. Paragraph 3.128 of GSR Part 3 [3] requires that access of visitors to controlled areas or supervised areas be restricted. In exceptional cases, a visitor may be permitted to enter a controlled area, but he or she should be accompanied at all times by a staff member who knows the protection and safety measures for the area. Written procedures should be drawn up specifying when such exceptions can take place and who may accompany the visitor. Particular consideration, in all cases, should be given with respect to women who are or may be pregnant. |
| Control of access |
3.280. |
Controlled areas and supervised areas should be clearly identified to help to prevent inadvertent entry to areas where diagnostic radiology or image guided interventional procedures are being performed [56] (see also para. 3.14). Further control can be afforded by the use of keys (or passwords) to restrict access to the control panels of medical radiological equipment to authorized persons only. |
| Monitoring and reporting |
3.281. |
Requirement 32 and para. 3.137 of GSR Part 3 [3] establish the requirements to be met by the radiology facility with respect to monitoring and reporting. At the radiology facility, procedures are to be in place to ensure that: |
| Monitoring and reporting |
3.282. |
The programme for monitoring public exposure arising from diagnostic radiology and image guided interventional procedures should include dose assessment in the areas in and surrounding the radiology facility that are accessible to the public. Doses can be derived from the shielding calculations in the planning stage, combined with the results from area monitoring at the initial operation of the facility and periodically thereafter. Records of dose assessments should be kept for a period that meets any relevant regulatory requirements. In the absence of such requirements, a suggested period for keeping records is seven to ten years. |
| Safety assessments of potential exposure |
3.283. |
To comply with the requirements for safety assessments established in paras 3.29–3.36 of GSR Part 3 [3], the registrant or licensee is required to conduct a safety assessment applied to all stages of the design and operation of the radiology facility. Furthermore, para. 3.29 of GSR Part 3 [3] states that: “the responsible person or organization shall be required to submit a safety assessment, which shall be reviewed and assessed by the regulatory body.” Paragraphs 2.150–2.154 describe general considerations for facilities using ionizing radiation for medical purposes. |
| Safety assessments of potential exposure |
3.284. |
The safety assessment of potential exposure should be systematic, should identify unintended events that can lead to potential exposure, and should consider their likelihood and potential consequences (see Appendix I for a summary of typical causes and contributing factors to accidental exposures in diagnostic radiology and image guided interventional procedures). The safety assessment should cover not only these events, but should also aim at anticipating other events that have not previously been reported. Clearly, the safety assessment should be documented. |
| Safety assessments of potential exposure |
3.285. |
The safety assessment should be revised when: New or modified medical radiological equipment or accessories are introduced;
Operational changes occur, including changes in workload;
Operational experience or information on accidents or errors indicates that the safety assessment should be reviewed.
|
| Prevention of accidents |
3.286. |
Accident prevention is clearly the best means for avoiding potential exposure, and paras 3.39–3.42 of GSR Part 3 [3] establish the requirements for good engineering practice, defence in depth and facility based arrangements to achieve this. Design considerations for medical radiological equipment and the radiology facility are described in paras 3.9–3.50.
|
| Prevention of accidents |
3.287. |
The licensee should incorporate: Defence in depth measures to cope with events identified in the safety assessment, and evaluation of the reliability of the safety systems (including administrative and operational procedures, equipment and facility design).
Operational experience and lessons from accidents and errors. This information should be incorporated into the training, maintenance and quality assurance programmes.
|
| Prevention of accidents |
3.288. |
Potential exposure of the public from a radiation generator can occur if a person (e.g. a cleaner) enters an interventional or conventional fluoroscopy room in between cases and depresses the exposure foot switch (usually a foot pedal placed on the floor). To prevent such potential exposure, equipment should be provided with a special X ray interlock in the control panel to disconnect the exposure foot switch in between cases, as described in para. 3.38(g). |
| Prevention of accidents |
3.289. |
Inadvertent entry into the room when a patient is undergoing a radiological procedure is another way for potential public exposure to occur. Means for control of entry are addressed in paras 3.279 and 3.280. |
| Prevention of accidents |
3.290. |
Means for preventing or minimizing unintended and accidental medical exposures are described in paras 3.256–3.259, and the ensuing investigation and corrective actions are described in paras 3.260–3.268. |
| Mitigation of the consequences of accidents |
3.291. |
Because the radiation source in almost all cases is an X ray generator and tube, turning off the primary electrical source immediately stops any radiation being produced. All relevant staff should be adequately trained to be able to recognize when medical radiological equipment is not functioning correctly or, for example, when a programming error in the software is suspected. If there are implications for occupational protection and/or patient protection, and if medical considerations allow it, the radiological procedure should be discontinued and the X ray unit turned off. |
| Mitigation of the consequences of accidents |
3.292. |
Some interventional radiology facilities may use sealed or unsealed radioactive sources for implantation or administration as part of the image guided interventional procedure. Loss of a source, rupture of the encapsulation or spillage of radioactivity can lead to contamination. For use of unsealed sources, the relevant guidance in paras 4.290–4.301 applies; and for use of sealed sources, the relevant guidance in paras 5.306–5.323 applies. |
| Mitigation of the consequences of accidents |
4.1. |
This section covers nuclear medicine, the branch of clinical medicine in which unsealed radioactive materials are administered to patients for diagnosis or treatment of disease, or for clinical or pre-clinical research. Treatment using sealed sources is covered in Section 5. X ray imaging such as CT, which can occur in conjunction with a nuclear medicine procedure, such as in hybrid imaging, is mainly covered in Section 3, with appropriate cross-references. |
| Mitigation of the consequences of accidents |
4.2. |
All nuclear medicine procedures involve the administration of a radiopharmaceutical to the patient. For diagnostic nuclear medicine procedures, trace amounts of compounds are labelled with photon or positron emitters, forming what is called a radiopharmaceutical. For photon emitters, the distribution of the radiopharmaceutical in the human body can be imaged with different modalities, such as planar imaging (including whole body imaging) or SPECT. In the case of positron emitters, the detection of annihilation photons allows registering of the 3-D spatial distribution of the radiopharmaceutical using PET. In hybrid imaging, SPECT and PET are combined with an X ray based modality, such as in PET–CT and SPECT–CT, and more recently also with MRI, such as in PET–MRI. In addition, probes may be used for the intraoperative localization of tumours and lymph nodes or leaks, and for uptake measurements in specific organs, such as the thyroid or lungs. In therapeutic nuclear medicine, therapeutic activities of radiopharmaceuticals are administered that are usually labelled with beta and/or gamma emitting radionuclides, more recently also with alpha emitters; therapy with Auger electrons is mostly experimental. The nuclear medicine facility might also perform in vitro studies, although these are not a primary focus of this Safety Guide. Some nuclear medicine facilities might also have an associated cyclotron facility for on-site radionuclide production. Detailed guidance for such cyclotron facilities is beyond the scope of this Safety Guide. |
| Mitigation of the consequences of accidents |
4.3. |
The generic term ‘medical radiation facility’ is used widely in Section 2 to mean any medical facility where radiological procedures are performed. In Section 4, the narrower term ‘nuclear medicine facility’ is used to cover any medical radiation facility where nuclear medicine procedures are performed. A nuclear medicine facility may be a nuclear medicine department inside a larger hospital or medical centre, or it may be a stand alone facility providing nuclear medicine services. In some cases, the nuclear medicine facility may be a mobile facility. |
| Mitigation of the consequences of accidents |
4.4. |
The defined term ‘radiological procedure’ is used in GSR Part 3 [3] to cover all imaging and therapeutic procedures using ionizing radiation. In a nuclear medicine facility, both imaging and therapeutic radiological procedures may occur, and this needs to be borne in mind when reading the guidance in Section 4. In cases where the guidance is specific to one of either imaging or treatment, additional qualifiers, such as ‘imaging’, ‘diagnostic’, ‘therapy’ or ‘treatment’, are used. |
| Mitigation of the consequences of accidents |
4.5. |
Different health professionals can take on the role of the radiological medical practitioner (see para. 2.90) in nuclear medicine procedures, depending, inter alia, on national laws and regulations. They primarily include nuclear medicine physicians, but they may include other specialists such as radiologists, cardiologists and radiation oncologists. |
| Mitigation of the consequences of accidents |
4.6. |
As stated in para. 2.92, the term ‘medical radiation technologist’ is used in GSR Part 3 [3] and this Safety Guide as a generic term for the health professional known by several different terms in different States; such terms include radiographer, radiological technologist and others. Clearly, each State will use its own term in its own jurisdiction. |
| Mitigation of the consequences of accidents |
4.7. |
Section 2 of this Safety Guide provides general guidance on the framework for radiation protection and safety in medical uses of radiation, including roles and responsibilities, education, training, qualification and competence, and the management system for protection and safety. This guidance is relevant to nuclear medicine, and reference to Section 2 should be made as necessary. |
| Nuclear medicine facilities |
4.8. |
Provisions for the incorporation of radiation protection and safety features should be made at the facility design stage. The siting and layout should take into account workload and patient flow, both within the nuclear medicine facility and, in cases where the nuclear medicine facility is part of a larger hospital or medical centre, within other departments of the facility. The nuclear medicine facility is likely to provide services to both inpatients and outpatients, so the location of the facility should give easy access to both groups. Consideration should also be given to providing easy exit routes for patients, after the examination or treatment has been performed, that minimize movement through the facility. |
| Nuclear medicine facilities |
4.9. |
A typical nuclear medicine facility using unsealed sources will have areas for the following: source storage and preparation (radiopharmacy, radioisotope laboratory or ‘hot lab’), radiopharmaceutical administration to patients, uptake rooms, imaging (in vivo), sample measurement (in vitro), waiting areas, changing areas and toilets, radioactive waste storage and predisposal processing. Separate waiting areas for patients before and after radiopharmaceutical administration should be considered. For those nuclear medicine facilities at which therapy with radiopharmaceuticals is performed, a dedicated ward for patients undergoing such treatments should be considered. The facility will also have areas where radioactive materials are not expected to be found, such as in offices, reporting areas and staff rooms, including cloakrooms, showers and toilets for staff. Detailed guidance on setting up nuclear medicine facilities, including PET–CT facilities, is given in Refs [62, 204–210]. |
| Nuclear medicine facilities |
4.10. |
For security purposes, nuclear medicine facilities should be located in areas where access by members of the public to the rooms where sources, including radionuclide generators, and radiopharmaceutical dispensing equipment are used and stored can be restricted. Furthermore, the proximity of source storage facilities to personnel that may need to respond in the event of a security breach should also be considered. |
| Nuclear medicine facilities |
4.11. |
As a general rule, the design of the nuclear medicine facility should make provision for safety systems or devices associated with the equipment and rooms. This includes electrical wiring relating to emergency off switches, as well as safety interlocks and warning signs and signals. |
| Nuclear medicine facilities |
4.12. |
A stable power supply should be available for the facility. An uninterruptible power supply or battery backup systems should be installed to capture the active information at the time of the outage and to shut down all software in a controlled manner. Servers should be programmed to shut down automatically when the power supply is interrupted. |
| Nuclear medicine facilities |
4.13. |
The design of the facility should include an air conditioning system sufficient to maintain the temperature in the examination room within the parameters defined by the equipment manufacturers. Alternatively, in the case of PET scanners, water cooling can also be used, depending on the equipment. In addition, temperature control is necessary for uptake rooms in a PET facility to prevent artefacts (e.g. brown fat uptake) occurring if room temperatures are too low.= |
| Nuclear medicine facilities |
4.14. |
Issues to be considered for the design of the nuclear medicine facility include: optimization of protection and safety against external radiation and contamination; maintaining of low radiation background levels to avoid interference with imaging equipment; meeting requirements for radiopharmaceuticals (see para. 4.39); and ensuring safety and security of sources (locking and control of access). |
| Nuclear medicine facilities |
4.15. |
For external exposure, the three factors relevant to dose reduction (time, distance and shielding) should be combined in the design to optimize occupational radiation protection and public radiation protection. Larger rooms are preferable to allow easy access for patients on bed trolleys and to reduce exposure of staff as well as the public. Larger rooms also allow for easier patient positioning and movement during the procedures. For internal exposure, the principles of control, containment and radiation protection by means of barriers should also be considered in the design, to optimize occupational radiation protection and public radiation protection (see paras 4.21 and 4.22). |
| Nuclear medicine facilities |
4.16. |
The design of the nuclear medicine facility should include provision for secure and shielded storage for radioactive sources. Facility design personnel and engineers should be consulted with regard to floor-loading requirements, with account taken of factors such as radiation shielding, imaging and ancillary equipment. Shielding should be appropriate to the type and energy of the emitted radiation. Storage may be provided in a room or a separate space outside the work area or in a locked cupboard, safe, refrigerator or freezer situated in the work area. Separate storage compartments for radiopharmaceuticals and an area for temporary storage of radioactive waste should be provided, with appropriate protective barriers. |
| Nuclear medicine facilities |
4.17. |
Special consideration should be given to avoiding interference with work in adjoining areas, such as imaging or counting procedures, or where fogging of films stored nearby can occur. |
| Nuclear medicine facilities |
4.18. |
Signs and warning lights should be used at the entrances of controlled areas and supervised areas to prevent inadvertent entry (see also paras 4.269 and 4.270 on control of access). For controlled areas, para. 3.90(c) of GSR Part 3 [3] requires the use of the basic ionizing radiation symbol recommended by ISO [56]. Signs should also be available at the entrances to areas for source preparation and storage, hybrid imaging rooms and rooms for hospitalized patients undergoing radiopharmaceutical therapy (see also the guidance on treatment rooms and wards, in paras 4.29–4.31). The signs should be clear and easily understandable. Warning lights, such as illuminated and flashing signs, should be activated when CT is being used in hybrid imaging procedures. |
| Nuclear medicine facilities |
4.19. |
Bathrooms designated for use by nuclear medicine patients should be finished in materials that can be easily decontaminated. Staff of the nuclear medicine facility should not use the patient bathrooms, as it is likely that the floors, toilet seats and tap handles of the sink will be contaminated. |
| Mobile facilities |
4.20. |
In some States, PET–CT scanners are mounted on a truck and this mobile unit provides a service to specific regions of that State. These mobile units should meet the same requirements of GSR Part 3 [3] as fixed facilities and the relevant guidance in this Safety Guide is applicable. |
| Areas where unsealed radioactive materials are handled |
|
4.21. Radiopharmacies or laboratories where unsealed radioactive materials are handled, such as the source preparation area, should have: Means to prevent access by unauthorized persons;
Adequate storage space for equipment used in the given room or area to be available at all times to minimize the potential for spreading contamination to other areas;
A contained workstation for easy decontamination;
Shielded storage for radioactive sources;
Shielded temporary storage for both solid and liquid radioactive waste, and places designated for the authorized discharge of liquid radioactive effluent;
Shielding to protect workers where significant external exposure might occur;
A wash-up area for contaminated articles, such as glassware;
An entry area where protective clothing can be stored, put on and taken off, and which is provided with a hand washing sink and a contamination monitor;
Taps and soap dispenser that are operable without direct hand contact and disposable towels or a hot air dryer;
An emergency eyewash, installed near the hand washing sink;
An emergency shower for decontamination of persons.
|
| Areas where unsealed radioactive materials are handled |
|
Detailed guidance is given in Refs [62, 204–210]. |
| Areas where unsealed radioactive materials are handled |
4.22. |
Radiopharmacies, laboratories and other work areas for manipulation of unsealed radioactive materials should be provided with equipment kept specifically for this purpose, which should include: Tools for maximizing the distance from the source, for example tongs and forceps;
Syringe shields;
Containers for radioactive materials, with shielding as close as possible to the source;
Double walled containers (with an unbreakable outer wall) for liquid samples;
Drip trays for minimizing the spread of contamination in the case of spillage;
Disposable tip automatic pipettes (alternatively, hypodermic syringes to replace pipettes);
Lead walls or bricks for shielding;
Lead barriers with lead glass windows;
Barriers incorporating a low atomic number material (i.e. acrylic) for work with beta emitters;
Radiation and contamination monitoring equipment (surface and air);
P.Shielded carrying containers, wheeled if necessary, for moving radioactive materials from place to place;
Equipment to deal with spills (decontamination kits).
|
| Areas where unsealed radioactive materials are handled |
4.23. |
Drainpipes from sinks in a radiopharmacy or laboratory should go as directly as possible to the main building sewer and should not connect with other drains within the building, unless those other drains also carry radioactive material. This is to minimize the possibility of the drainage system ‘backing up’ and contaminating other, non-controlled, areas. The final plans of the drainage system, which should be supplied to maintenance personnel, should clearly identify the drains from radiopharmacies and laboratories. Pipelines through which radioactive materials flow should be marked to ensure that monitoring precedes any maintenance. |
| Areas where unsealed radioactive materials are handled |
4.24. |
Some States require that drainpipes from a nuclear medicine facility and especially from radionuclide therapy wards terminate in a delay tank. Requirements on this issue differ very much among States, but each nuclear medicine facility should comply with the State’s regulations (see para. 4.280(g)). |
| Areas where unsealed radioactive materials are handled |
4.25. |
The floors of areas with the potential for contamination should be finished in an impermeable material that is washable and resistant to chemical change, curved to the walls, with all joints sealed and glued to the floor. The walls should be finished in a smooth and washable surface, for example painted with washable, non-porous paint. The surfaces of the room where unsealed radioactive materials are used or stored, such as benches, tables, seats, and door and drawer handles, should be smooth and non-absorbent, so that they can be cleaned and decontaminated easily. Supplies (e.g. gas, electricity and vacuum equipment) should not be mounted on bench tops, but on walls or stands. |
| Areas where unsealed radioactive materials are handled |
4.26. |
The floor and benches, including worktops, should be strong enough to support the weight of any necessary shielding materials or of radionuclide generators. The need for lifting equipment for radionuclide generators should be assessed. |
| Areas where unsealed radioactive materials are handled |
4.27. |
Radiopharmacies or laboratories in which radioactive aerosols or gases are produced or handled should have an appropriate ventilation system that includes a fume hood, laminar airflow cabinet or glove box. The fume hood should be constructed of material that is smooth, impervious, washable and resistant to chemicals, and it should exhibit a negative flow rate. The work surface should have a slightly raised lip to contain any spills. The ventilation system should be designed such that the radiopharmacy or laboratory is at negative pressure relative to surrounding areas and should be adequate to the radioisotopes used [210]. |
| Areas where unsealed radioactive materials are handled |
4.28. |
The airflow should be from areas of minimal likelihood of airborne contamination to areas where such contamination is likely. Room air from a radiopharmacy or radiochemistry laboratory should be vented through a filtration system or other mechanism for trapping airborne radioactive materials and should not be recirculated, neither directly, in combination with incoming fresh air in a mixing system, nor indirectly, as a result of proximity of the exhaust to a fresh air intake. The possibility for competitive airflow should be considered in the design. For reasons of asepsis, some radiopharmacies may need a positive rather than a negative pressure. In this case, the pressure gradient can be obtained by locating other workstations requiring negative pressure next to the radiopharmacy workstation. |
| Treatment rooms and wards |
4.29. |
Floors and other surfaces of rooms designated for patients undergoing radiopharmaceutical therapy should be covered with smooth, continuous and non-absorbent materials that can be easily cleaned and decontaminated. Shielding should be designed using appropriate dose constraints for workers and the public. Bins for the temporary storage of linen and waste contaminated with radioactive materials should be located in secure areas. Storage areas should be clearly marked, using the basic ionizing radiation symbol recommended by ISO [56]. |
| Treatment rooms and wards |
4.30. |
Rooms designated for patients undergoing radiopharmaceutical therapy should have separate toilets and washing facilities. A sign requesting patients to flush the toilet at least twice and to wash their hands should be displayed to ensure adequate dilution of excreted radioactive materials and to minimize contamination. The facilities should include a hand washing sink as a normal hygiene measure (see para. 4.19 for guidance on bathrooms and their use). |
| Treatment rooms and wards |
4.31. |
The design of safe and comfortable accommodation for carers and comforters (see also paras 4.235–4.239) should be considered for nuclear medicine facilities with radiopharmaceutical therapy patients. |
| Shielding calculations |
4.32. |
The shielding should be designed to meet the requirements for the optimization of protection and safety and should take into consideration the classification of the areas within the facility, the type of work to be done and the radionuclides (and their activity) intended to be used. Shielding should consider both structural and ancillary protective barriers at the design stage. It is convenient to shield the source, where possible, rather than the room or the person. The need for wall, floor and ceiling shielding should be assessed, for example in the design of therapy facilities and of PET–CT facilities, to reduce occupational and public exposure to acceptable levels. Wall shielding may be needed in the design of rooms housing sensitive instruments (to keep a low background), such as well counters, probes and imaging equipment (gamma cameras and PET scanners). In designing such wall shielding, consideration should be given to the height of the wall to ensure that scatter radiation, such as from a CT scanner, does not pass over the wall into the area being protected.
|
| Shielding calculations |
4.33. |
Methodologies and data for shielding calculations for nuclear medicine facilities are given in Refs [54, 61, 205] (see also paras 3.18–3.22) for shielding with respect to X ray imaging systems (e.g. CT) used as part of hybrid imaging equipment. The nominal design dose in an occupied area is derived by the process of constrained optimization (i.e. selection of a source related dose constraint), with the condition that each individual dose from all relevant sources is well below the dose limit for a person occupying the area to be shielded. Nominal design doses are levels of air kerma used in the design calculations and evaluation of barriers for the protection of individuals, at a reference point beyond the barrier. Specifications for shielding are calculated on the basis of the attenuation that the shielding needs to provide to ensure that the nominal design doses are achieved. Potential changes in practice and increases in workload should be considered. |
| Shielding calculations |
4.34. |
Care should be taken to avoid multiplication of conservative assumptions, which can lead to unrealistic overestimates of the shielding required. Typical conservative assumptions are: attenuation by the patient is not considered; decay of short lived radionuclides, such as 18F, is not considered; workload, use and occupancy factors are overestimated; and the persons to be protected are considered as remaining permanently in the most exposed place of the adjacent room. Therefore, a balanced decision should be achieved and accumulation of overly conservative measures that may go beyond optimization should be avoided. |
| Shielding calculations |
4.35. |
Specification of shielding, including calculations, should be performed by a medical physicist or a qualified expert in radiation protection. In some States, there may be a requirement for shielding plans to be submitted to the regulatory body for review or approval prior to any construction (see also para. 2.74). |
| Shielding calculations |
4.36. |
The adequacy of the shielding should be verified, preferably during construction, and certainly before the facility, room or area comes into clinical use. Clearly, requirements of the regulatory body should be met (para. 2.74). |
| Design of display and interpretation (reading) rooms |
4.37. |
To facilitate their interpretation by the radiological medical practitioner, images should be displayed in rooms specifically designed for such purposes. A low level of ambient light in the viewing room should be ensured (see also paras 3.45 and 3.46 on image display devices and view boxes). |
| Design of display and interpretation (reading) rooms |
4.38. |
Viewing rooms with workstations for viewing digital images should be ergonomically designed to facilitate image processing and manipulation so that reporting can be performed accurately. The viewing monitors of the workstations should meet applicable standards (see para. 3.46). |
| Radiopharmaceuticals |
4.39. |
Radiopharmaceuticals should be manufactured according to good manufacturing practice following relevant international standards [207, 208, 210–214] for: |
| Medical radiological equipment, software and ancillary equipment |
4.40. |
This subsection considers medical radiological equipment, including its software, used in a nuclear medicine facility. Such equipment falls into two categories: those that detect ionizing radiation from unsealed or sealed sources and those that generate ionizing radiation. The former includes probes, gamma cameras (planar and SPECT systems) and PET scanners, since these have an influence on the activity that needs to be administered to the patient in order to obtain the desired diagnosis. The latter includes CT, typically as part of a hybrid imaging system such as a PET–CT or SPECT–CT scanner. Some hybrid equipment utilizes MRI, and although MRI does not generate ionizing radiation and so is outside the scope of this Safety Guide, the performance of MRI can influence the efficacy of the nuclear medicine procedure, and hence such equipment should meet relevant IEC standards or equivalent national standards. |
| Medical radiological equipment, software and ancillary equipment |
4.41. |
The requirements for medical radiological equipment and its software are established in paras 3.49 and 3.162 of GSR Part 3 [3]. The IEC has published international standards applicable to medical radiological equipment. Current IEC standards relevant to nuclear medicine include Refs [215–221] (for those relevant to the X ray based component of hybrid imaging, see para. 3.28). It is recommended that the IEC web site be visited to view the most up to date list of standards. ISO publishes international standards applicable to medical radiological equipment. It is recommended that the ISO web site be visited to view the most up to date list of standards.
|
| Medical radiological equipment, software and ancillary equipment |
4.42. |
As licensees take responsibility for the radiation safety of medical radiological equipment they use, they should impose purchasing specifications that include conditions to meet relevant international standards of the IEC and ISO or equivalent national standards. In some States, there may be an agency with responsibilities for medical devices or a similar organization that gives type approval to particular makes and models of medical radiological equipment. |
| Medical radiological equipment, software and ancillary equipment |
4.43. |
Some nuclear medicine facilities operate a cyclotron for on-site radionuclide production. As the cyclotrons are not directly involved in the exposure of the patient, they need not comply with the requirements of GSR Part 3 [3] for medical radiological equipment. Nevertheless, they should comply with the more general requirements of GSR Part 3 [3] for radiation generators (Requirement 17 and paras 3.49–3.60 of GSR Part 3 [3]), as well as additional regulatory requirements, in a given State, for the preparation and control of radiopharmaceuticals. |
| Medical radiological equipment, software and ancillary equipment |
4.44. |
Displays, gauges and instructions on operating consoles of medical radiological equipment, and accompanying instruction and safety manuals, might be used by staff who do not understand, or who have a poor understanding of, the manufacturer’s original language. In such cases, the accompanying documents should comply with IEC and ISO standards and should be translated into the local language or into a language acceptable to the local staff. The software should be designed so that it can be easily converted into the local language, resulting in displays, symbols and instructions that will be understood by the staff. The translations should be subject to a quality assurance process to ensure proper understanding and to avoid operating errors. The same applies to maintenance and service manuals and instructions for maintenance and service engineers and technicians who do not have an adequate understanding of the original language (see also paras 2.104 and 2.137). |
| Design features for medical radiological equipment |
4.45. |
The performance of probes, gamma cameras (planar and SPECT systems) and PET scanners determines the efficacy of the diagnostic radiological procedures and hence can influence the amount of radioactive material that needs to be administered to the patient, or even whether the procedure is diagnostically successful. Many design features contribute to the performance of such equipment and should be considered when purchasing such equipment, as indicated briefly in paras 4.46–4.51 and described in detail in Refs [183, 200, 201, 209, 215–228].
|
| Design features for medical radiological equipment |
4.46. |
Design features that should be considered for probes used for uptake measurements include energy response, energy resolution, sensitivity, counting precision, linearity of count rate response and geometrical dependence. |
| Design features for medical radiological equipment |
4.47. |
Design features that should be considered for probes used intra-operatively include energy resolution, background count rate, sensitivity in scatter, sensitivity to scatter radiation, shielding (side and back), counting precision, linearity of count rate response (with scatter radiation), and count rate recorded by visual display and by an audible sound, the intensity of which is proportional to the count rate. |
| Design features for medical radiological equipment |
4.48. |
Design features that should be considered for gamma cameras (planar and SPECT systems) as well as their accessories include: Detector features:
Detector head motion.
Automatic patient–detector distance sensing.
Collision detection and emergency stops.
Collimators and collimator exchange mechanisms.
Imaging table and attachments.
Data acquisition features:
Data processing system:
Accessories, such as features for physiological triggering, anatomical landmarking and phantoms.
|
| Design features for medical radiological equipment |
4.49. |
Design features that should be considered for PET scanners include: Detector features:
Spatial resolution;
Sensitivity;
Scatter fraction, count losses and random measurements;
Energy resolution;
Image quality and accuracy of attenuation, and scatter correction and quantitation;
Coincidence timing resolution for time of flight PET accuracy.
Time of flight capability.
Data acquisition features, including 2-D and 3-D whole body imaging, and cardiac and respiratory gating.
Data processing system, including image reconstruction algorithms, image manipulation and image correction.
Emergency stop.
|
| Design features for medical radiological equipment |
4.50. |
Guidance on medical radiological equipment using X rays, used for imaging as part of nuclear medicine, is given in paras 3.27–3.41. |
| Design features for medical radiological equipment |
4.51. |
All digital medical radiological equipment should have connectivity to RIS and to PACS. |
| Ancillary equipment |
4.52. |
All equipment used for digital image display should meet appropriate international or national standards, for example meeting the performance specifications in Ref. [115]. Workstations and image processing and display software should be specifically designed for nuclear medicine, ensuring DICOM conformance and network interconnectivity. Guidance on DICOM image and data management for nuclear medicine is given in Ref. [229] (see paras 4.37 and 4.38 for guidance on display and interpretation rooms). |
| Ancillary equipment |
4.53. |
The nuclear medicine facility should have equipment, instruments and test objects for measurements, dosimetry and quality control. This may include liquid scintillation counters, well counters, activity meters (dose calibrators), probes, check sources, flood sources, phantoms, and geometry and mechanical test tools. Where applicable, such instrumentation should adhere to relevant IEC standards or equivalent national standards. Further guidance on appropriate equipment, instruments and test objects is given in Refs [215, 224, 227, 230]. |
| Ancillary equipment |
4.54. |
The nuclear medicine facility should be equipped with properly calibrated workplace monitoring instruments, including survey meters and portable contamination monitors. |
| Ancillary equipment |
4.55. |
Radiopharmaceutical dispensing equipment should adhere to relevant IEC standards or equivalent national standards. |
| Security of sources |
4.56. |
The objective of source security is to ensure continuity in the control and accountability of each source at all times in order to meet the requirement of para. 3.53 of GSR Part 3 [3]. In a nuclear medicine facility, the sources include unsealed radiopharmaceuticals as well as radionuclide generators, radiopharmaceutical dispensing equipment and sealed sources used for calibration or quality control tests. Standards for the identification and documentation of unsealed radioactive substances are issued by ISO [231]. Situations that are particularly critical with respect to security of sources in a nuclear medicine facility include receipt of radiopharmaceuticals, storage of sources, movement of sources within the facility and storage of radioactive waste (see Ref. [232]). The licensee of the nuclear medicine facility should develop procedures to ensure the safe receipt and movement of radioactive sources within the facility and should establish controls to prevent the theft, loss and unauthorized withdrawal of radioactive materials or the entrance of unauthorized personnel to controlled areas. An inventory of sources should be maintained, and procedures should be put in place to check and confirm that the sources are in their assigned locations and are secure. Written procedures should be developed to encourage proactive behaviour, for example to trigger a search when a delivery of radiopharmaceuticals is not received at the expected time. |
| Maintenance |
4.57. |
Paragraphs 3.15(i) and 3.41 of GSR Part 3 [3] establish requirements for maintenance to ensure that sources meet their design requirements for protection and safety throughout their lifetime and to prevent accidents as far as reasonably practicable. The registrant or licensee is required to ensure that adequate maintenance (preventive maintenance and corrective maintenance) is performed as necessary to ensure that medical radiological equipment used in the nuclear medicine facility retains, or improves through appropriate hardware and software upgrades, its design specifications for image quality and radiation protection and safety for its useful life. The registrant or licensee should, therefore, establish the necessary arrangements and coordination with the manufacturer or installer before initial operation and on an ongoing basis. |
| Maintenance |
4.58. |
All maintenance procedures should be included in the programme of quality assurance and should be carried out at the frequency recommended by the manufacturer of the equipment and relevant professional bodies. Servicing should include a report describing the equipment fault, the work done and the parts replaced and adjustments made, which should be filed as part of the programme of quality assurance. A record of maintenance carried out should be kept for each item of equipment. This should include information on any defects found by users (a fault log), remedial actions taken (both interim repairs and subsequent repairs) and the results of testing before equipment is reintroduced to clinical use. |
| Maintenance |
4.59. |
In line with the guidance provided in para. 2.113, after any modifications or maintenance, the person responsible for maintenance should immediately inform the licensee of the nuclear medicine facility before the equipment is returned to clinical use. The person responsible for the use of the equipment, in conjunction with the medical physicist, the medical radiation technologist and other appropriate professionals, should decide whether quality control tests are needed with regard to radiation protection, including image quality, and whether changes to protocols are needed, especially in the amount of administered activity. |
| Maintenance |
4.60. |
The electrical safety and mechanical safety aspects of the medical radiological equipment are an important part of the maintenance programme, as these can have direct or indirect effects on radiation protection and safety. Authorized persons who understand the specifications of the medical radiological equipment should perform this work (see also paras 2.112–2.114). Electrical and mechanical maintenance should be included in the programme of quality assurance and should be performed, preferably by the manufacturer of the medical radiological equipment or an authorized agent, at a frequency recommended by the manufacturer. Servicing should include a written report describing the findings. These reports and follow-up corrective actions should be archived as part of the programme of quality assurance. |
| Maintenance |
4.61. |
In nuclear medicine, as described in paras 4.1–4.6, occupationally exposed individuals are usually medical radiation technologists, radiological medical practitioners (including, e.g., nuclear medicine physicians), radiopharmacists and medical physicists. Other health professionals such as nurses and other support staff involved in the management of patients who have been administered with radiopharmaceuticals, particularly in nuclear medicine facilities providing therapy services, may also be considered occupationally exposed. |
| Maintenance |
4.62. |
Additional occupationally exposed personnel may include biomedical, clinical and service engineers and some contractors, depending on their role. |
| Maintenance |
4.63. |
Other nuclear medicine facility workers such as administrative personnel and other service support personnel, cleaning personnel, and workers in the wider medical facility where the nuclear medicine facility is located, for whom radiation sources are not required by, or directly related to, their work, are required to have the same level of protection as members of the public, as established in para. 3.78 of GSR Part 3 [3]. Consequently, the recommendations provided in paras 4.267–4.270 are also applicable in respect of such workers. Rules should be established for these workers, especially with regard to access to controlled areas and supervised areas. |
| Maintenance |
4.64. |
This subsection contains guidance very specific to nuclear medicine. More general and comprehensive guidance on occupational radiation protection is given in GSG-7 [23], including guidance on radiation protection programmes, assessment of occupational exposure and providers of dosimetry services, applicable to all areas of radiation use (including non-medical uses). |
| Classification of areas |
4.65. |
Various areas and rooms in a nuclear medicine facility should be classified as controlled areas or supervised areas, in line with the requirements established in paras 3.88–3.92 of GSR Part 3 [3]. Once designated, these areas should meet the requirements established in paras 3.89 and 3.90 (for controlled areas) and 3.91 and 3.92 (for supervised areas) of GSR Part 3 [3], including requirements for area delineation, signage, protection and safety measures, control of access, provision of personal protective equipment, provision of individual and area monitoring, provision of equipment for monitoring for contamination, and provision of personal decontamination facilities. All other rooms and areas that are not so designated are considered as being in the public domain, and levels of radiation in these areas should be low enough to ensure compliance with the dose limits for public exposure. Classification of areas in a nuclear medicine facility should be based on the analysis of the process as a whole, and not only on the location of the equipment and the radiation sources. Paragraphs 4.66–4.69 give general guidance, and it would be expected that final decisions by the licensee for a given medical radiation facility would be based on the expert advice of the medical physicist, a qualified expert in radiation protection or the RPO. |
| Classification of areas |
4.66. |
In a nuclear medicine facility, rooms for preparation of radiopharmaceuticals (i.e. radiopharmacies or hot labs), for injection of radiopharmaceuticals and for storage and decay of radiopharmaceuticals meet the criteria for a controlled area and should be so designated. Imaging rooms, particularly those housing radiopharmaceutical dispensing equipment (i.e. PET radiopharmaceutical and radioactive gas and aerosol dispenser devices), as well as waiting rooms dedicated to patients who have been injected with radiopharmaceuticals (e.g. uptake rooms in a PET facility) should also be designated as controlled areas. Rooms for patients undergoing radiopharmaceutical therapy should be designated as controlled areas. Rooms housing hybrid machines that have an X ray component (PET–CT and SPECT–CT) should be designated as controlled areas. A warning light at the entry to the room should be used to indicate when the machine is on to prevent unintended entry. |
| Classification of areas |
4.67. |
Supervised areas may include examination rooms with probes, corridors and other areas where there are patients who have been administered with radiopharmaceuticals. |
| Classification of areas |
4.68. |
The area around the control panel of hybrid imaging equipment (e.g. PET–CT and SPECT–CT) should be classified as a supervised area, even though the radiation levels may be very low owing to the shielding design. Classification of this area as a supervised area will ensure restricted access and hence, inter alia, avoid distraction of the operator, which could lead to accidental or unintended medical exposure of patients (see also para. 3.59). |
| Classification of areas |
4.69. |
In order to avoid uncertainties about the extent of controlled areas and supervised areas, the boundaries of such areas should, when possible, be walls and doors or other physical barriers, clearly marked or identified with suitable warning signs. |
| Local rules and procedures |
4.70. |
Paragraph 3.93 of GSR Part 3 [3] establishes a hierarchy of preventive measures for protection and safety with engineered controls, including structured and ancillary shielding, specific physical barriers, signs and interlocks, being supported by administrative controls and personal protective equipment. To this end, and as established in para. 3.94 of GSR Part 3 [3], local rules and procedures are required to be established in writing in any nuclear medicine facility. Their purpose is to ensure protection and safety for workers and other persons. Such local rules and procedures should include measures to minimize occupational radiation exposure both for normal work and in unusual events. The local rules and procedures should also cover the wearing, handling and storing of personal dosimeters, and should specify investigation levels and ensuing follow-up actions (see paras 4.118–4.140). |
| Local rules and procedures |
4.71. |
Since all personnel involved in using radiation in nuclear medicine need to know and follow the local rules and procedures, the development and review of these local rules and procedures should involve representatives of all health professionals involved in nuclear medicine. |
| Local rules and procedures |
4.72. |
Equipment (both hardware and software) should be operated in a manner that ensures satisfactory performance at all times with respect to both the tasks to be accomplished and to radiation protection and safety. The manufacturer’s operating manual is an important resource in this respect, but additional procedures should also be considered. The final documented set of operational procedures should be subject to approval by the licensee of the nuclear medicine facility, and should be incorporated into the facility’s management system (see paras 2.138–2.149). |
| Local rules and procedures |
4.73. |
Nuclear medicine staff should understand the documented procedures for their work with radiopharmaceuticals and for the operation of the equipment with which they work, including the safety features, and should be trained, with periodic refresher training, in what to do if things go wrong. Additional training should be conducted when new radiopharmaceuticals or devices are brought into nuclear medicine practice. |
| Local rules and procedures |
4.74. |
Many local rules and procedures address some or all aspects of occupational radiation protection, patient radiation protection and public radiation protection, either directly or indirectly, as well as providing for a successful diagnostic examination or application of the treatment. Paragraphs 4.75–4.109 give recommendations that should be incorporated into the nuclear medicine facility’s local rules and procedures. They are placed in this section on occupational radiation protection because they are to be followed by workers, but they will often also have significance for patient and public radiation protection (see also para. 4.56 on the security of sources). |
| Local rules and procedures |
4.75. |
Work procedures should be formulated so as to minimize exposure from external radiation and contamination, to prevent spillage from occurring and, in the event of spillage, to minimize the spread of contamination (surface and airborne). For instance, all manipulation for dispensing radioactive materials should be carried out over a drip tray and/or plastic backed absorbent pad. Work with unsealed sources should be restricted to a minimum number of specifically designated areas. |
| Local rules and procedures |
4.76. |
No food or drink, cosmetic or smoking materials, crockery or cutlery should be brought into an area where unsealed radioactive materials are used. An exception to this is food that is radiolabelled for patient studies. Food or drink should not be stored in a refrigerator used for unsealed radioactive materials. Personal cell phones and handkerchiefs should not be used in such areas (with respect to the latter, an adequate supply of paper tissues should be provided). Before a person enters an area where radioactive material is handled, any cut or break in the skin should be covered with a waterproof dressing. |
| Local rules and procedures |
4.77. |
In areas classified as controlled areas, protective clothing should be worn as determined by the safety assessment. Protective clothing is unlikely to be necessary for persons accompanying patients into gamma camera rooms. On leaving the controlled area, protective clothing that is contaminated should be placed in an appropriate container. The method of removing gloves should be based on the surgical technique, in order to avoid transferring activity to the hands. |
| Local rules and procedures |
4.78. |
Staff leaving a controlled area, classified as such on account of the potential for contamination, should, after removal of their protective clothing, wash their hands and then monitor their hands, clothing and body for residual contamination. Liquid soap should be provided unless aseptic considerations require an alternative cleaner. Non-abrasive nail brushes should only be used if contamination persists after simple washing (see also paras 4.105–4.109 on decontamination of persons). |
| Local rules and procedures |
4.79. |
Pipettes should never be operated by mouth. Syringes used for handling radioactive liquids should be appropriately shielded wherever practicable. The distance between the fingers and the radioactive liquid should be as large as can be achieved. Needles that have been used to inject patients should not be recapped. In other circumstances, needles should be recapped when working with radioactive liquids to maintain containment. Specific recapping tools should be used to prevent injuries from needles. |
| Local rules and procedures |
4.80. |
The work area should be kept tidy and free from articles not required for work. A monitoring and cleaning programme should be established to ensure minimal spread of contamination. Cleaning and decontamination can be simplified by covering benches and drip trays with disposable material such as plastic backed absorbent paper. |
| Local rules and procedures |
4.81. |
All containers used for radioactive material should be clearly labelled, indicating the radionuclide, chemical form and activity at a given date and time. The batch number and the expiry date and time should be added as appropriate. All such containers should be adequately sealed and shielded at all times. Except for very small activities, containers should not be handled directly and, if possible, tongs or forceps for vials and syringe shields should be used. Records of stocks, administrations and predisposal waste management should be kept. |
| Local rules and procedures |
4.82. |
The amount of shielding material required can be minimized by positioning the shielding material close to the source. A variety of materials can be used for this purpose, such as lead, tungsten, lead glass and lead composite. Shielding incorporating acrylic is usually more suitable for beta emitters, as it lowers the amount of bremsstrahlung produced. Lead should be coated to provide a cleanable surface. |
| Local rules and procedures |
4.83. |
The attenuation by lead aprons at the typical gamma energies used in nuclear medicine is modest and is even less for non-lead based protective aprons. More effective ways for dose reduction are automatic dispensers and injectors, and mobile shields. |
| Local rules and procedures |
4.84. |
The following protective approaches can reduce occupational exposure significantly: For preparation and dispensing of radiopharmaceuticals, working behind a lead glass bench shield, using shielded vials and syringes, and wearing disposable gloves;
During examinations, when the distance to the patient is short, using a movable transparent shield.
|
| Local rules and procedures |
4.85. |
All radioactive sources should be returned to safe storage immediately when no longer required. |
| Local rules and procedures |
4.86. |
All operations involving radioactive gases or aerosols should be carried out in a fume hood or similar ventilated device to prevent airborne contamination. Exhaust vents should be situated well away from air intakes. The administration of aerosols to patients, such as for ventilation studies, should be performed using a mouthpiece and nose clip or mask for the patient. The placing of extracting devices close to the patient could be considered to improve radiation protection. |
| Local rules and procedures |
4.87. |
Glassware and implements for use in the radiopharmacy should be appropriately marked, and under no circumstances should they be removed from that area. |
| Local rules and procedures |
4.88. |
Packaging and containers for radioactive material should be checked for contamination on opening. |
| Local rules and procedures |
4.89. |
Items such as containers and lead pots that no longer contain radioactive material are required to be managed as non-radioactive waste. They should have any radiation warning labels removed or obliterated before removing them from regulatory control. |
| Local rules and procedures |
4.90. |
For X ray based imaging (e.g. CT) in the nuclear medicine facility, reference should be made to the guidance, where appropriate, in paras 3.65–3.77. |
| Local rules and procedures |
4.91. |
Local rules for pregnant workers and persons under the age of 18 should reflect the guidance given in paras 4.145–4.149 and 4.150, respectively. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.92. |
Administration of radiopharmaceuticals is normally by the oral route, intravenous injection (systemic), intra-arterial injection (locoregional) or instillation into closed joints (intra-articular/radiosynoviorthesis) or body cavities (intracavitary): Shielded syringes should be utilized during the intravenous or intra-arterial administration of radiopharmaceuticals as necessary to ensure extremity doses are maintained below occupational dose constraints. Absorbent materials or pads should be placed underneath an injection or infusion site. The RPO at the facility should be consulted to determine the necessity of other protective equipment (e.g. shoe covers and step off pads) for particular radiopharmaceutical therapies.
For intravenous or intra-arterial administration by bolus injection, when dose rates warrant, the syringe should be placed within a syringe shield (usually a plastic shield for beta emitting radionuclides to minimize bremsstrahlung or a shield of high atomic number material for photon emitting radionuclides) with a transparent window to allow the material in the syringe to be seen. For intravenous administration by slower drip or infusion, the container containing the radioactive material should be placed within a suitable shield. For high energy photons, a significant thickness of lead or other high atomic number material may need to be used. In addition, consideration should be given to the shielding of pumps and lines.
For oral administration of therapeutic radiopharmaceuticals, the radioactive material should be placed in a shielded, spill-proof container. Care should be taken to minimize the chance of splashing liquid or of dropping capsules. Appropriate long handled tools should be utilized when handling unshielded radioactive materials.
|
| Specific local rules and procedures for radiopharmaceutical therapy |
4.93. |
Patients hospitalized for therapy with radiopharmaceuticals should be attended by staff (physicians, nurses, aides and cleaning staff) trained in radiation protection. This also includes night staff. The training should cover radiation protection and specific local rules, in particular for situations where there is a risk of significant contamination from urine, faeces or vomit. Ward nurses should be informed when a patient may pose a radioactive hazard. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.94. |
Local rules should be established concerning the type of nursing that can be performed according to the level of the radiation hazard. In general, non-essential nursing should be postponed to take advantage of the reduction of activity by decay and excretion. Blood and urine analyses should be performed prior to therapy. Procedures should be established for the handling of any potentially contaminated item (e.g. bed linen, clothing, towels, crockery and bed pans). |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.95. |
As described in para. 4.66, rooms occupied by patients treated with radiopharmaceuticals should be designated as controlled areas, and both the basic ionizing radiation symbol recommended by ISO [56] and a warning sign should be posted. Access should be restricted and a list of relevant contacts (such as nuclear medicine physicians and on-call physicians, medical radiation technologists and the RPO) should be provided. Protective clothing, such as laboratory coats, gloves and shoe covers, should be made available at the entrance to the room. The nursing staff should be familiar with the implications of the procedures for controlled areas, the time and date the radiopharmaceuticals were administered, and any relevant instructions to carers and comforters. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.96. |
Values of ambient dose equivalent rates at suitable distances should be determined by the RPO or medical physicist. This information will assist in deriving appropriate arrangements for entry by staff and by carers and comforters. These arrangements should be made in writing and included in the local rules. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.97. |
On leaving the work area, staff should remove any protective clothing and wash their hands. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.98. |
Patients treated with radiopharmaceuticals should use designated toilets. Measures to minimize contamination should be implemented (such as laying plastic backed absorbent paper on the floor around the toilet bowl, and instructions to sit down when using the toilet and to flush the toilet at least twice in the absence of delay tanks). |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.99. |
Particular attention and measures to limit spread of contamination are required in the case of incontinent patients and in the case of vomiting after oral administration of the radiopharmaceutical. Plastic backed absorbent paper on the bed and floor can help to reduce spread of contamination. Contaminated bedding and clothing should be changed promptly and retained for monitoring. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.100. |
Crockery and cutlery may become contaminated. Local rules should specify washing up and segregation procedures and the management of single use dishes, cutlery and food waste. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.101. |
Nursing care items should be covered when possible to prevent contamination. For example, a stethoscope can be covered with a glove. The blood pressure cuff and the thermometer should remain in the room until the release of patient, and then checked for contamination before being returned to regular use. |
| Specific local rules and procedures for radiopharmaceutical therapy |
4.102. |
The staff should be informed about the treatment procedure and any relevant medical history. If the medical condition of a patient deteriorates such that intensive care becomes necessary, the advice of the RPO should be sought immediately. While urgent medical care is a priority and should not be delayed, it may be necessary to restrict the maximum time that individual health professionals spend with a patient. |
| Specific local rules and procedures for PET facilities |
4.103. |
Personnel carrying out PET imaging can receive relatively large annual occupational radiation doses compared to their counterparts in general nuclear medicine. The main contribution to the occupational dose for personnel comes from patient handling. PET radiopharmacists at facilities performing radiopharmaceutical synthesis and unit dose preparations can receive significant hand and body doses, even where heavily shielded ‘hot cells’ are available to moderate doses. For these reasons, local rules and procedures for PET facilities should emphasize the means described in paras 4.75–4.102 for minimizing the dose to personnel when handling radiopharmaceuticals and patients containing radiopharmaceuticals. |
| Specific local rules and procedures for PET facilities |
4.104. |
Radiopharmaceuticals should be stored and transported in lead or tungsten containers specifically designed to limit external radiation levels from radionuclides used for PET. An additional plastic shield inside a lead or tungsten syringe shield will absorb positrons before striking the tungsten, minimizing unwanted production of bremsstrahlung radiation. The use of tongs to handle unshielded radiopharmaceutical vials markedly reduces hand doses. Automatic systems are available that allow the safe and quick dispensing of radiopharmaceuticals into syringes, thus minimizing the operator’s actions. |
| Decontamination of persons |
4.105. |
Hands should be washed on completing work with unsealed radioactive materials and on leaving an area that is classified as controlled because of possible contamination. If detectable contamination remains on the hands after simple washing, use of a surfactant or chelating agent specific to the chemical form of the contaminant agent can be more successful. Guidance for monitoring the contamination level should be made available. A decontamination kit and procedures for its use should be available on the site. |
| Decontamination of persons |
4.106. |
The RPO should be consulted when contamination of parts of the body other than the hands is suspected, or when the procedures for decontamination of the hands are ineffective. Special care should be taken in the decontamination of the face to restrict entry of radioactive material into the eyes, nose or mouth. |
| Decontamination of persons |
4.107. |
If the skin is broken or a wound is sustained under conditions where there is a risk of radioactive contamination, the injury should be flushed with water as soon as appropriate, and care should be taken not to wash contamination into the wound. As soon as the first aid measures have been taken, the person should seek further treatment, including decontamination if necessary. The RPO should be consulted as needed. |
| Decontamination of persons |
4.108. |
Contaminated clothing should be removed as soon as practicable, and care should be taken not to spread contamination. |
| Decontamination of persons |
4.109. |
All staff working with unsealed sources should be trained in the procedures for dealing with accidents, spills or contaminated persons, with refresher training at appropriate intervals. This includes instructions on appropriate showering and eye washing. |
| Personal protective equipment and in-room protective devices |
4.110. |
Paragraphs 3.93 and 3.95 of GSR Part 3 [3] require that personal protective equipment and in-room protective devices be available and used when structural shielding and administrative controls alone cannot afford the required level of occupational radiation protection. The need for this protective equipment should be established by the RPO at the nuclear medicine facility or by the medical physicist. |
| Personal protective equipment and in-room protective devices |
4.111. |
In a nuclear medicine facility, protective equipment includes the following: Shields for bench tops, vials, syringes, activity meters and for the preparation of the radiopharmaceuticals (i.e. L-blocks and side blocks) of a material and thickness appropriate to the type and energy of the radiation. Particular considerations for the choice of shield include the following:
Alpha emitters may need to be shielded by high atomic number materials because of their characteristic X rays and high energy gamma components.
223Ra does not need a high atomic number shield because the gamma component does not contribute significantly to the dose.
Solutions containing pure low energy beta emitters, such as 14C, require a plastic shield to attenuate the beta particles.
Solutions containing high energy beta emitters, such as 32P and 90Y, require a plastic shield to attenuate the beta particles followed by a high atomic number material shield for the bremsstrahlung radiation.
Solutions containing radionuclides that have both beta radiation and gamma radiation, such as 169Er, 177Lu, 186Re and 153Sm, may need lead shielding to attenuate the high energy gamma photons.
Gamma emitters always require shielding by high atomic number materials.
Protective clothing should be used in work areas where there is a likelihood of contamination, such as in areas for radiopharmaceutical preparation and administration. The protective clothing may include laboratory gowns, waterproof gloves (made of latex or non-latex material such as neoprene, polyvinyl chloride or nitrile), overshoes, and caps and masks for aseptic work. The clothing serves both to protect the body of the wearer and to help to prevent the transfer of contamination to other areas. The clothing should be monitored and removed before the wearer leaves a designated area. When moving between supervised areas such as the camera room and the injection area, the wearer might not need to change the protective clothing unless a spill is suspected. It is good practice to change gloves after each manipulation. Protective clothing should be removed before entering other areas, such as staff rooms.
When lower energy beta emitters are handled, gloves should be thick enough to protect against external beta radiation.
Lead aprons should be worn when entering a room with hybrid imaging (e.g. PET–CT) if the X rays are about to be used and either a carer or comforter or a staff member needs to be in the room with the patient. Lead aprons may also be worn when preparing and administering high activities of 99mTc, although their use is not recommended, as other protective measures are more effective (see para. 4.83).
Tools for remote handling of radioactive material, including tongues and forceps.
Containers for the transport of radioactive waste and radioactive sources.
Fume hoods, fitted with appropriate filters and adequate ventilation, should be used with volatile radiopharmaceuticals, such as 131I and 133Xe. The sterility of the intravenous or intra-arterial radiopharmaceuticals should be preserved.
|
| Workplace monitoring |
4.112. |
Paragraphs 3.96–3.98 of GSR Part 3 [3] establish the requirements and responsibilities for workplace monitoring. Workplace monitoring comprises measurements made in the working environment and the interpretation of the results. Workplace monitoring serves several purposes, including routine monitoring, special monitoring for specific occasions, activities or tasks, and confirmatory monitoring to check assumptions made about exposure conditions. Workplace monitoring can be used to verify the occupational doses of personnel whose work involves exposure to predictable low levels of radiation. It is particularly important for staff members who are not individually monitored. In the nuclear medicine facility, workplace monitoring should address both external exposure and contamination. Further general guidance on workplace monitoring is given in GSG-7 [23]. |
| Workplace monitoring |
4.113. |
Laboratories and other areas in which work with unsealed sources is undertaken should be monitored, both for external radiation and for surface contamination, on a systematic basis. Contamination monitoring is required for: All work surfaces (including the interior of enclosures), tools, equipment and devices (including dosimetry systems, computers and peripherals, and stress testing units), the floor and any items removed from these areas;
Workstations, ventilation systems and drains, when any of these needs to be accessed for maintenance purposes;
Protective and personal clothing, and shoes, particularly when the wearer is leaving a controlled area (monitors should be available near the exit);
Clothing, bedding and utensils used by radiopharmaceutical therapy patients.
|
| Workplace monitoring |
4.114. |
Periodic monitoring with a survey meter and contamination monitor, or by wipe tests, should be conducted for controlled areas and supervised areas. Continuous monitoring with an area monitor should be considered for areas for storage and handling of sources. If a package containing radioactive sources is damaged upon arrival, a survey of removable contamination and the external radiation field should be carried out. |
| Workplace monitoring |
4.115. |
Workplace monitoring with respect to X ray based imaging systems used in nuclear medicine should follow the guidance given in paras 3.100–3.103. |
| Workplace monitoring |
4.116. |
Workplace monitoring should be performed and documented as part of the nuclear medicine facility’s radiation protection programme. The nuclear medicine facility’s RPO or medical physicist should provide specific advice on the workplace monitoring programme, including any investigations that are triggered when investigation levels are exceeded (see paras 4.131 and 4.132). |
| Workplace monitoring |
4.117. |
The survey meters used for external radiation monitoring should be calibrated in terms of the relevant operational quantities. In nuclear medicine, the relevant quantity is normally the ambient dose equivalent, H*(10), and the unit is the sievert (Sv) and its submultiples. Contamination monitors should be calibrated in appropriate quantities (see also further guidance on calibration in paras 4.197–4.202). |
| Assessment of occupational exposure |
4.118. |
The purpose of monitoring and dose assessment is, inter alia, to provide information about the exposure of workers and to confirm good working practices and regulatory compliance. Paragraph 3.100 of GSR Part 3 [3] establishes the requirement of individual monitoring for “any worker who usually works in a controlled area, or who occasionally works in a controlled area and may receive a significant dose from occupational exposure”. Workers who may require individual monitoring include nuclear medicine physicians, other specialist doctors, medical radiation technologists, medical physicists, the RPO, radiopharmacists and any other persons involved in the preparing, dispensing and administering of radiopharmaceuticals to patients for diagnosis and therapy, staff dealing with radioactive waste, biomedical and clinical engineers, maintenance and servicing personnel, and any nursing or other staff who need to spend time with nuclear medicine patients or who work in controlled areas. |
| Assessment of occupational exposure |
4.119. |
Monitoring involves more than just measurement. It includes interpretation, assessment, investigation and reporting, which may lead to corrective measures, if necessary. Individual external doses can be assessed by using individual monitoring devices, which include thermoluminescent dosimeters, optical stimulated luminescent dosimeters, radiophotoluminiscent dosimeters, film badges and electronic dosimeters. Individual monitoring devices should be calibrated and should be traceable to a standards dosimetry laboratory (for more detailed guidance, see GSG-7 [23]). |
| Assessment of occupational exposure |
4.120. |
With the exception of electronic dosimeters used sequentially by several workers with individual doses recorded separately, each personal dosimeter should be used for monitoring only the person to whom it is issued, for work performed at that nuclear medicine facility, and it should not be taken to other facilities where that person may also work. For example, if a person is issued with a dosimeter at hospital A, it should be worn only at hospital A and not at any other hospitals or medical centres where he or she also works. Monitoring results can then be interpreted for the person working in a specific nuclear medicine facility, and this will allow appropriate review of the effectiveness of the optimization of protection and safety for that individual in that facility. However, national regulatory requirements may differ from this advice, and they would need to be followed in those jurisdictions in which they apply (see also paras 4.133–4.135). |
| Assessment of occupational exposure |
4.121. |
The monitoring period (period of dosimeter deployment) specified by regulatory bodies in most States is typically in the range of one to three months. It is determined by such factors as service availability, work load and type of work. A one month monitoring period is usually used for persons performing procedures associated with higher occupational exposure. A longer monitoring period (two or three months) is more typical for personnel exposed to lower doses, as a one month cycle would usually mean that the actual occupational dose is less than the minimum detection level of the dosimeter, resulting in no detectable doses. With a longer cycle, it is more likely that a reading can be obtained. In certain circumstances (e.g. the introduction of new procedures, and work at high dose rates), shorter monitoring periods may be necessary. In these situations, the supplementary use of electronic dosimeters may be appropriate. Unnecessary delays in the return, reading and reporting of the recorded dose on dosimeters should be avoided. Dosimeters should be sent from the nuclear medicine facility to the dosimetry service provider, which should then process the dosimeters and return the dose reports, all in a timely manner. Some regulatory bodies may specify a performance criterion for timely reporting. |
| Assessment of occupational exposure |
4.122. |
The operational dosimetric quantity used for external radiation is the personal dose equivalent Hp(d ). For weakly penetrating radiation and strongly penetrating radiation, the recommended depths, d, are 0.07 mm and 10 mm, respectively. Both weakly penetrating radiation and strongly penetrating radiation are used in nuclear medicine. Hp(10) is used to provide an estimate of effective dose that avoids both underestimation and excessive overestimation [23]. |
| Assessment of occupational exposure |
4.123. |
For monitoring the skin and extremities, a depth of 0.07 mm (d = 0.07) is recommended, and Hp(0.07) is used to provide an estimate of equivalent dose to the skin and extremities. When there is a possibility of high exposure of the hands, such as in the preparation and administration of radiopharmaceuticals, extremity dosimeters should be worn (if this is compatible with good clinical practice). |
| Assessment of occupational exposure |
4.124. |
For monitoring the lens of the eye, a depth of 3 mm (d = 3) is recommended, and Hp(3) is used to provide an estimate of equivalent dose to the lens of the eye. In practice, however, the use of Hp(3) has not been widely implemented for routine individual monitoring. In nuclear medicine, it is generally expected that the dose to the lens of the eye is not significantly higher than for the rest of the body. A possible exception is in the handling of sources for preparation and administration, but with accepted practices (as described in paras 4.70–4.91) the lens of the eye should be adequately protected. Nonetheless, monitoring of dose to the lens of the eye may need to be considered. |
| Assessment of occupational exposure |
4.125. |
There are three dose limits applicable to workers in nuclear medicine: the limit for effective dose, and the limits for equivalent dose to the lens of the eye and to the skin and extremities. However, in nuclear medicine, both exposure from external radiation and exposure from internal contamination are relevant. The dosimeter being worn will measure external radiation only and will be used to estimate one or more of the quantities used for the dose limits. Depending on the work performed by the person being individually monitored, there may be a preferred position for wearing the dosimeter, and more than one dosimeter may be used. In nuclear medicine, dosimeters are usually worn on the front of the upper torso (and under any protective clothing), as occupational exposure arising from most nuclear medicine procedures results in the whole body being fairly uniformly exposed (see para. 4.123 for guidance on when extremity dosimeters should be worn). |
| Assessment of occupational exposure |
4.126. |
When a protective apron is being used, the assessment of effective dose might not be straightforward: A single dosimeter placed under the apron, reported in Hp(10), provides a good estimate of the contribution to the effective dose of the parts of the body protected by the apron, but underestimates the contribution of the unprotected parts of the body (the thyroid, the head and neck, and the extremities).
A single dosimeter worn outside the apron, reported in Hp(10), provides a significant overestimate of effective dose and should be corrected for the protection afforded by the apron by using an appropriate algorithm [120, 122].
Notwithstanding (a) and (b), in nuclear medicine, a single dosimeter under the apron provides an estimate of the effective dose that is sufficient for radiation protection purposes.
|
| Assessment of occupational exposure |
4.127. |
In nuclear medicine, certain workers may be at risk of both surface (skin) contamination and internal contamination by ingestion, inhalation or adsorption of radioactive material. Employers are responsible for identifying those persons and for arranging for appropriate monitoring (para. 3.102 of GSR Part 3 [3]). This requirement is typically met by monitoring the thyroid with an external detector that assesses the iodine uptake for individuals handling radioiodine and by monitoring the hands after the protective gloves have been removed. In some special cases, it may be required to measure the activity of urine samples. The committed effective dose should be calculated as part of the worker’s total effective dose [23]. |
| Assessment of occupational exposure |
4.128. |
When not in use, individual dosimeters should be kept in a dedicated place and should be protected from damage or from irradiation. If an individual loses his or her dosimeter, the individual should inform the RPO, who should perform a dose assessment, record this evaluation of the dose and add it to the individual’s dose record. Where there is a national dose registry, it should be updated with the dose estimate in a timely manner. The most reliable method for estimating an individual’s dose is to use his or her recent dose history. In cases where the individual performs non-routine types of work, it may be better to use the doses of co-workers experiencing similar exposure conditions as the basis for the dose estimate. |
| Assessment of occupational exposure |
4.129. |
In some cases, occupational doses can be estimated from the results of workplace monitoring. The effective dose for personnel can be inferred from the measured ambient dose equivalent H*(10), provided the dose gradient in the workplace is relatively low. The ICRP [119] provides conversion coefficients from ambient dose equivalent to effective dose for different types of radiation and energy. |
| Assessment of occupational exposure |
4.130. |
Additional direct reading operational dosimeters, such as electronic dosimeters, should be considered for use in a nuclear medicine facility, for example in a new facility or with the introduction of new procedures, as these devices can give the worker an instant indication of both the cumulative dose and the current dose rate and also allow pre-setting of an alarm to alert when a given level has been reached [23]. These dosimeters are also useful for staff involved in radiopharmaceutical therapies and for pregnant workers, where a ‘real time’ reading of the dose is recommended. |
| Investigation levels for staff exposure |
4.131. |
Investigation levels are different from dose constraints and dose limits; they are a tool used to provide a warning of the need to review procedures and performance, to investigate what is not working as expected and to take timely corrective action. The exceeding of an investigation level should prompt such actions. In nuclear medicine, one could use predetermined values such as 0.5 mSv per month for effective dose or 15 mSv per month for finger dose. Suitable alternatives can be doses that exceed an appropriate fraction (e.g. 25%), pro rata per monitoring period, of the annual dose limits or a pre-set value above a historical average. Abnormal conditions and events should also trigger an investigation. In all cases, the investigation should be carried out with a view to improving the optimization of occupational protection, and the results should be recorded. Investigation levels should also be set for workplace monitoring, with account taken of exposure scenarios and the predetermined values adopted for investigation levels for workers. Details on investigation levels are provided in GSG-7 [23]. |
| Investigation levels for staff exposure |
4.132. |
An investigation should be initiated as soon as possible following a trigger or event, and a written report should be prepared concerning the cause, including determination or verification of the dose, corrective or mitigatory actions, and instructions or recommendations to avoid recurrence. Such reports should be reviewed by the quality assurance committee and the radiation safety committee, as appropriate, and the licensee should be informed. In some cases, the regulatory body may also need to be informed. |
| Persons who work in more than one place |
4.133. |
Some individuals might work in more than one nuclear medicine facility. The facilities may be quite separate entities in terms of ownership and management, or they may have common ownership but separate management, or they may even have common ownership and management but be physically quite separate. Regardless of the ownership and management structure, the occupational radiation protection requirements for the particular nuclear medicine facility apply when the person is working in that facility. As described in para. 4.120, a dosimeter issued for individual monitoring should be worn only in the facility for which it is issued, as this facilitates the effective optimization of protection and safety in that facility. This approach is logistically more easily implemented, since each physical site has its own dosimeters, and so there is no need to transport dosimeters between facilities, with the risk of losing or forgetting them. In cases where the facilities are under common ownership, it may be seen as an unnecessary financial burden to provide more than one set of dosimeters for staff that work in more than one of its facilities. However, the radiation protection advantages of having the dosimeter results linked to a person’s work in only one nuclear medicine facility remain (see also para. 4.135). |
| Persons who work in more than one place |
4.134. |
There is, however, an important additional consideration, namely the need to ensure compliance with the occupational dose limits. Any person who works in more than one nuclear medicine facility should notify the licensee for each of those facilities. Each licensee, through its RPO, should establish formal contact with the licensees of the other nuclear medicine facilities and their RPOs, so that each facility has an arrangement to ensure that a personal dosimeter is available and that there is an ongoing record of the occupational doses for that person in all the facilities he or she works.
|
| Persons who work in more than one place |
4.135. |
Some individuals, such as consultant medical physicists or service engineers, might perform work in many nuclear medicine facilities and, in addition, in other medical radiation facilities. They can be employed by a company or be self-employed, providing contracted services to the nuclear medicine facility and the other facilities. In such cases, it is simpler for the company or the self-employed person to provide the dosimeters for individual monitoring. Therefore, in these cases, a worker uses the same dosimeter for work performed in all nuclear medicine facilities (and other medical radiation facilities) in the monitoring period. |
| Records of occupational exposure |
4.136. |
Paragraphs 3.103–3.107 of GSR Part 3 [3] establish the detailed requirements for records of occupational exposure and place obligations on employers, registrants and licensees. In addition to demonstrating compliance with legal requirements, records of occupational exposure should be used within the nuclear medicine facility for additional purposes, including assessing the effectiveness of the optimization of protection and safety at the facility and evaluating trends in exposure. The regulatory body might specify additional requirements for records of occupational exposure and for access to the information contained in those records. Employers are required to provide workers with access to records of their own occupational exposure (para. 3.106(a) of GSR Part 3 [3]). Further general guidance on records of occupational exposure is given in GSG-7 [23]. |
| Health surveillance for workers |
4.137. |
The primary purpose of health surveillance is to assess the initial and continuing fitness of employees for their intended tasks, and requirements are given in paras 3.108 and 3.109 of GSR Part 3 [3]. |
| Health surveillance for workers |
4.138. |
No specific health surveillance relating to exposure to ionizing radiation is necessary for staff involved in nuclear medicine. Under normal working conditions, the occupational doses incurred in nuclear medicine are low, and no specific radiation related examinations are required, as there are no diagnostic tests that yield information relevant to exposure at low doses. It is, therefore, rare for considerations of occupational exposure arising from the working environment of a nuclear medicine facility to influence significantly the decision about the fitness of a worker to undertake work with radiation or to influence the general conditions of service [23]. |
| Health surveillance for workers |
4.139. |
Only in cases of overexposed workers, at doses much higher than the dose limits (e.g. a few hundred millisieverts or higher), would special investigations involving biological dosimetry and further extended diagnosis and medical treatment be necessary [23]. In case of internal contamination, additional investigations to determine uptake and retention may be required. Interventions to facilitate excretion or limit uptake of the radioactive agent should be considered, as appropriate. |
| Health surveillance for workers |
4.140. |
Counselling should be made available to workers who have or may have been exposed in excess of dose limits, and information, advice and, if indicated, counselling should be made available to workers who are concerned about their radiation exposure. In nuclear medicine, the latter group may include women who are or may be pregnant. Counselling should be given by appropriately experienced and qualified practitioners. Further guidance is given in GSG-7 [23]. |
| Information, instruction and training |
4.141. |
All staff involved in nuclear medicine should meet the respective training and competence criteria described in paras 2.119–2.137. This will include general education, training, qualification and competence for occupational radiation protection in nuclear medicine. Nuclear medicine physicians, medical radiation technologists, medical physicists and nurses may not have been trained with respect to the X ray based component of hybrid imaging systems, such as PET–CT, and as such they should undertake radiation protection and safety training relevant to the additional imaging modalities in their nuclear medicine facility. |
| Information, instruction and training |
4.142. |
Paragraph 3.110 of GSR Part 3 [3] places responsibilities on the employer to provide, inter alia, adequate information, instruction and training for protection and safety as it pertains to the nuclear medicine facility. This is not only for new staff but also for all staff as part of their continuing professional development. Specific instruction and training should be provided when new radiopharmaceuticals, medical radiological equipment, software and technologies are introduced. |
| Information, instruction and training |
4.143. |
Information on potential contamination risks should be given to ancillary staff, including IT specialists, and contractors performing occasional work in a nuclear medicine facility or radiopharmaceutical laboratory. |
| Conditions of service and special arrangements |
4.144. |
Paragraph 3.111 of GSR Part 3 [3] requires that no special benefits be offered to staff because they are occupationally exposed. It is not acceptable to offer benefits as substitutes for measures for protection and safety.
|
| Pregnant or breast-feeding workers |
4.145. |
There is no requirement in GSR Part 3 [3] for a worker to notify the licensee that she is pregnant, but it is necessary that female workers understand the importance of making such notifications so that their working conditions can be modified accordingly. Paragraph 3.113(b) of GSR Part 3 [3] establishes the requirement that employers, in cooperation with registrants and licensees, provide female workers with appropriate information in this regard. |
| Pregnant or breast-feeding workers |
4.146. |
Paragraph 3.114 of GSR Part 3 [3] establishes the requirement that: |
| Pregnant or breast-feeding workers |
4.147. |
Other possible solutions include reassignment of a pregnant worker to duties where the likelihood of an accident is lower or to a location that has a lower ambient dose equivalent. Such reassignments should be accompanied by adequate training. A further consideration is the need to avoid having pregnant workers respond to an accident such as a radioactive spill (see also paras 4.294–4.298). |
| Pregnant or breast-feeding workers |
4.148. |
The dose to the fetus should be monitored using an additional dosimeter appropriately positioned (see also GSG-7 [23]). Personal electronic dosimeters are valuable in assessing radiation doses to pregnant workers and subsequently the embryo or fetus (see also para. 4.130). |
| Pregnant or breast-feeding workers |
4.149. |
With regard to the dose limit of 1 mSv for the embryo or fetus, the dose to the embryo or fetus is not likely to exceed 25% of the personal dosimeter measurement of external exposure. This value depends on the penetration of the radiation (i.e. on the photon energy of the radionuclides in use). Information, advice and, if indicated, counselling for pregnant workers should be made available (see also para. 4.140). |
| Persons under 18 |
4.150. |
In many States, there is the possibility of students aged 16 or more, but under 18, commencing their studies and training to become a medical radiation technologist or other health professional that can involve occupational exposure to ionizing radiation. Paragraph 3.116 of GSR Part 3 [3] establishes the requirements for access to controlled areas and the dose limits for such persons are more restrictive (see Box 1 of this Safety Guide and Schedule III of GSR Part 3 [3]). |
| Protection of workers responding to incidents in a nuclear medicine facility |
4.151. |
The practice of nuclear medicine is a planned exposure situation, and when circumstances result in incidents that lead to, or could lead to, unintended or accidental exposures of patients or staff, they are still within the framework of a planned exposure situation. The potential occurrence of such incidents should be considered in advance in the safety assessment for the facility and mitigatory procedures should be developed accordingly (see the guidance in paras 4.283–4.301 on prevention and mitigation of accidents). |
| Protection of workers responding to incidents in a nuclear medicine facility |
4.152. |
Occupational exposure of staff responding to such incidents is still subject to the occupational dose limits, and the mitigatory procedures for incidents should include considerations for the optimization of protection and safety for the responding workers. The mitigatory procedures should also include allocation of responsibilities and should provide for the education and training of the relevant staff in executing the mitigatory measures, which should be periodically exercised. Most of these situations, for example the response to spillage of radioactive materials on work surfaces, can be executed in a planned manner so that doses can be kept low. There may be situations with high doses, for example in medical emergencies involving immediate care of patients in the case of a stroke or cardiac arrest, when large amounts of radioactive material have been incorporated (e.g. 2 GBq of 131I), but in these events the dose is justified because the procedure is lifesaving. However, even in the case of urgent surgery, rotation of personnel may be utilized if the surgical procedure is lengthy to help to maintain optimized occupational radiation protection for this situation. The advice of the facility’s RPO should be sought for these situations (see the guidance in paras 4.299 and 4.300 for more details). |
| Protection of workers responding to incidents in a nuclear medicine facility |
4.153. |
This section covers radiation protection of patients, carers and comforters, and volunteers in biomedical research. The term ‘patient’, when used in the context of medical exposure, means the person undergoing the radiological procedure. Other patients in the nuclear medicine facility, including those who may be waiting for their own radiological procedure, are considered members of the public and their radiation protection is covered in paras 4.263–4.272. |
| Protection of workers responding to incidents in a nuclear medicine facility |
4.154. |
As described in para. 2.8, there are no dose limits for medical exposure, so it is very important that there is effective application of the requirements for justification and optimization. |
| Justification of medical exposure |
4.155. |
The requirements for justification of medical exposure (paras 3.155–3.161 of GSR Part 3 [3]) incorporate the three-level approach to justification (see para. 2.11) [4, 125, 126]. |
| Justification of medical exposure |
4.156. |
The roles of the health authority and professional bodies with respect to a level 2 or generic justification of radiological procedures, justification of health screening programmes, and justification of screening intended for the early detection of disease, but not as part of a health screening programme, are described in paras 2.55–2.60. |
| Justification of medical exposure for the individual patient |
4.157. |
GSR Part 3 [3] requires a joint approach to justification at the level of an individual patient, with a shared decision involving both the referring medical practitioner (who initiates the request for a radiological procedure) and the radiological medical practitioner. A referral for a nuclear medicine procedure should be regarded as a request for a professional consultation or opinion rather than an instruction or order to perform. The referring medical practitioner brings the knowledge of the medical context and the patient’s history to the decision process, while the radiological medical practitioner has the specialist expertise in performing the radiological procedure. The efficacy, benefits and risks of alternative methods (both methods involving ionizing radiation and methods not involving ionizing radiation) should be considered. The ultimate responsibility for justification will be specified in the individual State’s regulations. |
| Justification of medical exposure for the individual patient |
4.158. |
In the case of radiopharmaceutical therapy, the requirements for justification are applied more effectively as part of the medical process of determining the best approach to treatment. When a patient is referred by a referring medical practitioner for treatment, careful consideration should be made by a multidisciplinary team, including such specialists as radiation oncologists or endocrinologists, on whether to treat the patient with radiopharmaceutical therapy or some other form of radiation therapy, another modality, a combined treatment approach (sequential or concomitant) or not to be treated at all. Ideally, every treatment decision should be discussed within the team and documented at a ‘tumour board’ or equivalent multidisciplinary meeting. |
| Justification of medical exposure for the individual patient |
4.159. |
The patient should also be informed about the expected benefits, risks and limitations of the proposed radiological procedure, as well as the consequences of not undergoing the procedure. |
| Justification of medical exposure for the individual patient |
4.160. |
In nuclear medicine imaging, requirements for justification are applied more effectively as part of the medical process of determining the ‘appropriateness’ of a radiological procedure. The process of determining appropriateness is an evidence based approach to choosing the best test for a given clinical scenario, with account taken of diagnostic efficacy and justification as well as alternative procedures that do not use ionizing radiation, for example, ultrasound or MRI. Useful tools to support this decision making process include national or international imaging referral guidelines developed by professional societies [127–133, 233]. Imaging referral guidelines can be disseminated or utilized through electronic requesting systems and clinical decision support tools or systems. |
| Justification of medical exposure for the individual patient |
4.161. |
In determining the appropriateness of the nuclear medicine imaging procedure for an individual patient, the following questions should be asked by the referring medical practitioner [132]: Has it already been done? A radiological procedure that has already been performed within a reasonable time period (depending on the procedure and clinical question) should not be repeated (unless the clinical scenario indicates the appropriateness of repeating the procedure). In some cases, an alternative procedure may have already been performed in another facility, making the proposed radiological procedure unnecessary, for example a patient who has recently undergone a CT pulmonary angiography in one facility might be referred for a ventilation/perfusion scan at another facility. The results (images and reports) of previous examinations should be made available, not only at a given nuclear medicine facility but also for consideration at different facilities. Digital imaging modalities and electronic networks should be used to facilitate this process.
Is it needed? The anticipated outcome of the proposed radiological procedure (positive or negative) should influence the patient’s management.
Is it needed now? The timing of the proposed radiological procedure in relation to the progression of the suspected disease and the possibilities for treatment should all be considered as a whole.
Is this the best investigation to answer the clinical question? Advances in imaging techniques are taking place continually, and the referring medical practitioner may need to discuss with the radiological medical practitioner what is currently available for a given problem.
Has the clinical problem been explained to the radiological medical practitioner? The medical context for the requested radiological procedure is crucial for ensuring the correct technique is performed with the correct focus.
|
| Justification of medical exposure for the individual patient |
4.162. |
The three particular groups of patients identified in para. 3.157 of GSR Part 3 [3] for special consideration with respect to justification in nuclear medicine are patients who are pregnant or breast-feeding or are paediatric. Owing to the higher radiosensitivity of the embryo or fetus, it should be ascertained whether a female patient is pregnant before a nuclear medicine procedure is performed. Paragraph 3.176 of GSR Part 3 [3] requires that procedures be “in place for ascertaining the pregnancy status of a female patient of reproductive capacity before the performance of any radiological procedure that could result in a significant dose to the embryo or fetus”. Pregnancy would then be a factor in the justification process and might influence the timing of the proposed radiological procedure or a decision as to whether another approach to treatment is more appropriate. Care should be taken to ascertain that the examination or treatment selected is indeed indicated for a medical condition that requires prompt medical treatment. Confirmation of pregnancy could occur after the initial justification and before the radiological procedure is performed. Repeat justification is then necessary, with account taken of the additional sensitivity of the pregnant patient and embryo or fetus.
(i) Most diagnostic procedures with 99mTc do not cause high fetal doses. For radionuclides that do not cross the placenta, the fetal dose is derived from the radioactivity in maternal tissues. Some radiopharmaceuticals, or their breakdown components, that do cross the placenta and concentrate in a specific organ or tissue can pose a significant risk to the fetus. Particular attention should be given to radiopharmaceuticals labelled with iodine isotopes. Radiopharmaceuticals labelled with other radionuclides, in particular positron emitters, need special consideration. In all these instances, the medical physicist should estimate the fetal dose. Detailed information on doses to the embryo or fetus from intakes of radionuclides by the mother is given by the ICRP [234].
(ii) As a rule, a pregnant patient should not be subject to radioiodine therapy unless the application is lifesaving. Otherwise, the therapeutic application should be deferred until after the pregnancy and after any period of breast-feeding [124, 235, 236]. In particular, radioiodine will easily cross the placenta, and the fetal thyroid begins to accumulate iodine at about ten weeks of gestation.
In breast-feeding patients, excretion through the milk and possibly enhanced dose to the breast should be considered in the justification process. Detailed information on doses to infants from the ingestion of radionuclides in breast milk is given by the ICRP [237].
As children are at greater risk of incurring radiation induced stochastic effects, paediatric examinations necessitate special consideration in the justification process [233].
|
| Justification of medical exposure for the individual patient |
4.163. |
A ‘self-referral’ occurs when a health professional undertakes a radiological procedure for patients as a result of justification on the basis of his or her own clinical assessment. Most examples of acceptable self-referral practice occur with X ray imaging, such as in dentistry, and relevant professional bodies in many States develop appropriate guidance for their specialty (para. 3.149). Self-referral in nuclear medicine, if it occurs, would need to be guided by such professional guidelines. |
| Justification of medical exposure for the individual patient |
4.164. |
‘Self-presentation’, including ‘individual health assessment’, occurs when a member of the public asks for a radiological procedure without a referral from a health professional. This may have been prompted by media reports or advertising. Self-presentation for nuclear medicine procedures is not widely prevalent, but for any such case justification is required, as for all radiological procedures. Relevant professional bodies have an important role in considering evidence for developing guidance when new practices are proposed. States may choose to incorporate such guidance into legislation [136]. |
| Justification of medical exposure for the individual patient |
4.165. |
Means to improve awareness, appropriateness and auditing should be developed to support the application of the requirement for justification of medical exposure. Awareness of the need for justification underpins the whole process of justification. Means for promoting awareness include traditional education and training, such as at medical school or during specialty training, Internet based learning or learning ‘on the job’ (e.g. junior doctors in an emergency department), and the use of feedback in the reporting process. Appropriateness is described in paras 4.160 and 4.161, and the audit process is used for monitoring and feedback to improve both awareness and appropriateness. |
| Justification of medical exposure for biomedical research volunteers |
4.166. |
The role of the ethics committee in the justification of medical exposure of volunteers exposed as part of a programme of biomedical research is described in para. 2.99. |
| Justification of medical exposure for biomedical research volunteers |
4.167. |
The three-level approach to justification is not applicable for carers and comforters. Instead, para. 3.155 of GSR Part 3 [3] establishes the requirement to ensure that there be some net benefit arising from the exposure, for example the successful performance of a diagnostic procedure on a child. The crucial component in the justification of medical exposure of carers and comforters is their knowledge and understanding about radiation protection and the radiation risks for the procedure being considered. To this end, the radiological medical practitioner or medical radiation technologist involved in the radiological procedure, prior to the performance of the procedure, has the responsibility to ensure that the carer or comforter is correctly informed about radiation protection and the radiation risks involved, and that the carer or comforter understands this information and consequently agrees to take on the role of carer or comforter. |
| Optimization of protection and safety |
4.168. |
In medical exposure, optimization of protection and safety has several components, some applicable directly to the radiological procedure about to be performed and others providing the support or framework for the other components. These components of optimization of protection and safety are described in paras 4.169–4.240. Key personnel in the optimization process are the radiological medical practitioner, the medical radiation technologist and the medical physicist. |
| Design considerations |
4.169. |
The use of appropriate and well designed medical radiological equipment and associated software underpins any nuclear medicine procedure. Gamma cameras, SPECT–CT and PET–CT scanners and their accessories should be designed and manufactured so as to facilitate the keeping of doses from medical exposure as low as reasonably achievable consistent with obtaining adequate diagnostic information. Guidance on design considerations is given in the subsection on medical radiological equipment in paras 4.45–4.51. Guidance on design considerations applicable for X ray imaging systems as part of hybrid systems is given in paras 3.32–3.41. Ultimately, as established in para. 3.162 of GSR Part 3 [3], it is the responsibility of the licensee of the nuclear medicine facility to ensure that the facility uses only medical radiological equipment and software that meets applicable international or national standards. |
| Operational considerations: General |
4.170. |
Following justification, the nuclear medicine procedure is required to be performed in such a way as to optimize patient protection (para. 3.163 of GSR Part 3 [3] for diagnostic procedures and para. 3.165 of GSR Part 3 [3] for radiopharmaceutical therapy procedures). The level of image quality sufficient for diagnosis is determined by the radiological medical practitioner and is based on the clinical question posed. |
| Operational considerations: General |
4.171. |
The following points apply to all nuclear medicine patients, whether undergoing diagnostic or therapeutic procedures: There should be an effective system for correct identification of patients, with at least two, preferably three, forms of verification, for example name, date of birth, address and medical record number.
Patient details should be correctly recorded, such as age, sex, body mass, height, pregnancy and breast-feeding status, current medications and allergies.
The clinical history of the patient should be reviewed.
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| Operational considerations: Diagnostic imaging |
4.172. |
A written protocol should be drawn up for each diagnostic procedure performed in the facility, designed to maximize the clinical information to be obtained from the study, with consideration given to the appropriate DRL for the procedure (see paras 2.34 and 2.45). Such protocols are best developed using guidelines from national or international professional bodies, and hence will reflect current best practices, as for example in Refs [62, 137, 142–147, 204, 205, 238–240]. For modern digital equipment, many of the factors are automated through menu driven selections on the equipment console. Nevertheless, in setting up these options, significant scope exists for the optimization of protection and safety through the appropriate selection of values for the various technical parameters, thereby effectively creating an electronic protocol. Protocols should be periodically reviewed in line with the requirements for quality assurance and radiological reviews (see paras 4.234 and 4.259–4.261). |
| Operational considerations: Diagnostic imaging |
4.173. |
Deviations from such protocols may be necessary owing to the special needs of a particular patient or because of the local unavailability of components for a test. In such cases, the radiological medical practitioner should record a valid reason for the decision. |
| Operational considerations: Diagnostic imaging |
4.174. |
Equipment should be operated within the conditions established in the technical specifications, and in accordance with any licence conditions, to ensure that it will operate satisfactorily at all times, in terms of both the tasks to be accomplished and radiation protection and safety, so that optimal acquisition and processing of images can be achieved with the minimum patient exposure. |
| Operational considerations: Diagnostic imaging |
4.175. |
Many factors influence the relationship between image quality and patient dose in diagnostic nuclear medicine procedures. Detailed guidance on appropriate choices for these factors is widely available and should be followed [62, 204, 205, 209, 238–240]. Such factors include the following: Appropriate selection of the best available radiopharmaceutical and its activity, with account taken of special requirements for children and for patients with impaired organ function.
Adherence to patient preparation requirements specific to the study to be performed. Examples include:
Use of methods for blocking the uptake in organs not under study and for accelerated excretion, when applicable.
Withdrawal of medications, food or substances that might interfere with the outcome of the procedure.
Correct hydration.
The storage or retention of radiopharmaceuticals within specific organs can be influenced by drugs such as diuretics or gall bladder stimulants, whenever they do not adversely interfere with the procedure. This method is sometimes used to increase the specificity of the examination, but has also a positive influence on radiation protection, for example the use of a ‘diuretic challenge’ in renography.
For children undergoing diagnostic procedures, the amount of activity administered should be chosen by utilizing methodologies described in international or national guidelines [62, 204, 205, 209, 238, 241–243].
Use of appropriate image acquisition parameters:
In nuclear medicine and with a gamma camera (planar and SPECT systems), this may include selection of the collimator, acquisition matrix, energy windows, acquisition zoom, time per frame and imaging distance.
For PET systems, this may include 2-D and 3-D acquisitions, matrix size, field of view, time of flight, attenuation correction, slice overlap, scatter correction and coincidence timing.
Use of appropriate reconstruction parameters (e.g. algorithm, matrix, filters, scatter correction and zoom factor), and application of appropriate image corrections (e.g. attenuation and scatter correction, and, in the case of PET systems, random correction).
Utilization of quantitative and qualitative capabilities, such as the generation of region of interest analysis, time–activity curve generation, image reformatting, or tissue uptake ratios, specific to the clinical need.
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| Operational considerations: Diagnostic imaging |
4.176. |
Many radionuclides are excreted by the kidneys. Bladder doses can be minimized by drinking plenty of fluid and frequently emptying the bladder. Patients, particularly children, should be encouraged to empty the bladder frequently, especially in the immediate time following the examination. |
| Operational considerations: Diagnostic imaging |
4.177. |
While most adults can maintain the required position without restraint or sedation during nuclear medicine examinations, it may be necessary to immobilize or sedate children so that the examination can be completed successfully. Increasing the administered activity to reduce the examination time is an alternative that can be used for elderly patients who are in pain. |
| Operational considerations: Diagnostic imaging |
4.178. |
In some cases, if the patient is healthy and cooperative, activity can be reduced and scan times can be increased, for example for lung scans for pregnant patients. In all cases, however, the diagnostic information produced should not be compromised by a reduction in activity. |
| Operational considerations: Diagnostic imaging |
4.179. |
Care should be taken to ensure that there is no contamination on the collimator surface, patient table or elsewhere, as this might impair the quality of the images. |
| Operational considerations: Radiopharmaceutical therapy |
4.180. |
Protocols should be established in writing for each type of radiopharmaceutical therapy performed in the facility, designed to meet the requirements of para. 3.165 of GSR Part 3 [3]. Such protocols are best developed using guidelines from national or international professional bodies, and hence should reflect current best practices, as for example in Refs [204, 205, 244, 245]. Protocols should be periodically reviewed in line with the requirements for quality assurance and radiological reviews (see paras 4.234 and 4.259–4.261). |
| Operational considerations: Radiopharmaceutical therapy |
4.181. |
In addition to the guidance in paras 4.170–4.180 (for both diagnostic nuclear medicine procedures and therapeutic nuclear medicine procedures), the following provisions should be put in place: Verbal and written information and instructions should be provided to patients about their radiopharmaceutical therapy and about how to minimize exposure of family members and the public, and advice should be provided on pregnancy and contraception after therapy (for detailed guidance, including sample information sheets, see Refs [21, 204, 246–249]).
Special attention should be given to preventing the spread of contamination due to patient vomit and excreta.
A protocol should be drawn up for the release of patients after the administration of therapeutic doses of radiopharmaceuticals (see the guidance in paras 4.246–4.248).
A protocol should be drawn up for the actions to be taken when the dose incurred is above or below the value prescribed by the radiological medical practitioner as required by para. 3.180 of GSR Part 3 [3].
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| Operational considerations: Radiopharmaceutical therapy |
4.182. |
Paragraph 3.165 of GSR Part 3 [3] establishes the requirement that the type and activity of the therapeutic radiopharmaceuticals that are administered to each patient are appropriate. Although algorithms for determining appropriate activities for a given patient on the basis of radiation doses to critical organs exist, there is no standardized algorithm. Methodologies are described in Refs [250–256]. Ideally, the administered activity should be based on the results of a pre-therapeutic dosimetry. Typically, therapeutic radiopharmaceuticals are administered at standard fixed activities (GBq), standard fixed activities per unit body mass (MBq/kg) or standard fixed activities per unit body surface area (MBq/m2 ), based on the results of toxicity studies and evaluation of side effects in clinical trials. |
| Operational considerations: Radiopharmaceutical therapy |
4.183. |
For female patients, their pregnancy and breast-feeding status should be evaluated before administration of a therapeutic dose (see also paras 4.241–4.245). |
| Operational considerations: Radiopharmaceutical therapy |
4.184. |
Immediately prior to administration of a therapeutic radiopharmaceutical, the following information, as applicable, should be verified, preferably by two individuals: The dose on the radiopharmaceutical label matches the prescription;
The identity of the patient by two independent means;
The identity of the radionuclide;
The identity of the radiopharmaceutical;
The total activity;
The date and time of calibration.
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| Operational considerations: Radiopharmaceutical therapy |
4.185. |
The administered activity should be verified by means of an activity meter (dose calibrator) or other suitable device to ensure that the total activity does not deviate significantly from the prescribed administered activity (e.g. <5% deviation), and the measured value should be recorded. Corrections should be calculated for residual activity in the syringe, cups, tubing, inline filter or other materials used in the administration. |
| Operational considerations: Radiopharmaceutical therapy |
4.186. |
Patients undergoing radiopharmaceutical therapy should be informed in advance that it will be necessary for medical personnel to minimize close or direct contact, so that this precaution will not be interpreted as a lack of concern. |
| Operational considerations: Radiopharmaceutical therapy |
4.187. |
Both female and male patients should be advised about avoidance of pregnancy after therapeutic administrations. Data on the periods during which conception should be avoided after administration of a radiopharmaceutical to a female patient for therapeutic purposes are given in Appendix II, with further guidance provided in Ref. [238]. |
| Operational considerations: Radiopharmaceutical therapy |
4.188. |
The administration of therapeutic doses of relatively long lived radionuclides in ionic chemical forms to male patients is a possible source of concern because of the presence of larger quantities of these radionuclides in ejaculate and in sperm. It may be prudent to advise sexually active men who have been treated with, for example, 32P (phosphate), 89Sr (chloride), 131I (iodide), 223Ra (chloride) to avoid fathering children for a period of four months after treatment, and to have protected intercourse for a period of time to be defined by the medical practitioner. The period of four months is suggested, as this is longer than the sperm regeneration cycle [238, 249, 257]. |