SSG-86 Radiation Protection Programmes for the Transport of Radioactive Material

To provide for adequate consideration of radiation protection measures in transport;

To ensure that the system of radiation protection is adequately applied;

To enhance a safety culture in the transport of radioactive material;

To provide practical measures to meet these objectives.”

Scope of the programme (see paras 302.3–302.5 [of SSG‑26 (Rev. 1) [6]]);

Roles and responsibilities for the implementation of the programme (see para. 302.6 [of SSG‑26 (Rev. 1) [6]]);

Dose assessment and optimization (see para. 303 of the Transport Regulations);

Assessment of surface contamination (see paras 508, 513 and 514 of the Transport Regulations);

Segregation and other protective measures (see paras 562.1–562.13 [of SSG‑26 (Rev. 1) [6]]);

Emergency response arrangements (see paras 304 and 305 of the Transport Regulations);

Training (see paras 311–315 of the Transport Regulations);

Management system (see para. 306 of the Transport Regulations).”

Is likely to be between 1 and 6 mSv in a year, a dose assessment programme via workplace monitoring or individual monitoring shall be conducted; or

Is likely to exceed 6 mSv in a year, individual monitoring shall be conducted.”

Routine conditions of transport (incident free);

Normal conditions of transport (minor mishaps);

Accident conditions of transport.

The sources of routine exposure and reasonably foreseeable potential exposure, such as surface contamination, airborne contamination and sources of external radiation.

The nature and magnitude of exposures in normal operations.

The nature, likelihood and magnitude of potential exposures.…

The measures for protection and safety that are necessary to implement the optimization process.

Appropriate monitoring systems”.

Use of workplace monitoring. This method can give a good assessment of the doses that workers will receive, provided that the radiological conditions in the workplace are reasonably predictable over a long period (at least for several months). Workplace monitoring should be repeated at appropriate intervals, and certainly when the working conditions change significantly.

Use of data from the scientific literature and information from comparable facilities. Some dose values are given in the literature for various workplace situations. These can, in principle, be used to judge whether monitoring is needed.

Use of simulations. Numerical simulations can be powerful and can provide information instantly on the parameters that influence doses that would be received in given exposure situations. The results of simulations should be verified by measurement.

Use of confirmatory measurements. Performing confirmatory measurements with personal dosimeters can help to determine whether individual monitoring is needed.”

The radionuclides, the activity levels, the physical and chemical form of radioactive material, the package type and category being transported, and the dose rates around packages and in and around vehicles.

The magnitude and likelihood of occupational exposures and public exposures arising from routine (incident free), normal (minor mishaps) and accident conditions of transport, taking into account the following: use of overpacks or freight containers; ad hoc stops, parking and delays due to traffic conditions during land transport; the necessity of storage in transit; the use of different modes of transport or conveyances and stowage within the conveyance; and specific handling procedures (e.g. for small packages or packages that are handled remotely). If applicable, this may also include consideration of potential exposures arising from failures to correctly assemble and use packages.

The number of workers involved and their activities that might involve exposure to radiation.

The duration and frequency of operations.

The distance between workers and packaged or unpackaged radioactive material.

The distance between members of the public and packaged or unpackaged radioactive material.

Shielding and other protective measures implemented to optimize radiation protection.

Assessing the exposure of workers and demonstrating compliance with regulatory requirements.

Confirming the effectiveness of working practices (e.g. the adequacy of supervision and training) and engineering standards.

Determining the radiological conditions in the workplace, whether these are under adequate control and whether operational changes have improved or worsened the situation.

Evaluating and improving operating procedures from a review of the collected monitoring data for individuals and groups. Such data may be used to identify both good and bad features of operating procedures and design characteristics, and thereby contribute to the development of safer working practices in relation to radiation.

Providing information that can be used to enable workers to understand how, when and where they are exposed, and to motivate them to take steps to reduce their exposure.

Providing information for the evaluation of doses in the event of accidental exposures.”

Information on the general nature of the work in which the worker was subject to occupational exposure;

Information on dose assessments, exposures and intakes at or above the relevant recording levels specified by the regulatory body and the data upon which the dose assessments were based;

When a worker is or has been exposed while in the employ of more than one employer, information on the dates of employment with each employer and on the doses, exposures and intakes in each such employment;

Records of any assessments made of doses, exposures and intakes due to actions taken in an emergency or due to accidents or other incidents, which shall be distinguished from assessments of doses, exposures and intakes due to normal conditions of work and which shall include references to reports of any relevant investigations.”

Demonstrating the effectiveness of the optimization process;

Providing data for the compilation of dose distributions;

Evaluating trends in exposure and thus providing the information necessary for the evaluation of the radiation protection programme;

Developing effective procedures and programmes for monitoring;

Providing exposure data from new medical procedures and programmes;

Providing data for epidemiological and research studies;

Providing information that may be necessary for litigation related purposes or for workers’ compensation claims, which can arise years after the actual or claimed exposure.”

Several publications give results of assessments of doses to workers and to members of the public from the transport of radioactive material by specific modes of transport, for example Refs [11–14].

The results of a coordinated research project that included the assessment of doses to workers and to members of the public from the transport of naturally occurring radioactive material are documented in Ref. [15].

An assessment of the doses to workers and to members of the public from the transport of radioactive waste from a 99Mo production facility is documented in Ref. [16].

An assessment of the doses to workers and to members of the public from nuclear fuel cycle material, including fresh fuel, spent fuel and high level waste, and for various modes of transport, is summarized in Ref. [17].

Information about dose assessments relating to the transport of spent nuclear fuel is provided in Ref. [18]. Information about dose assessments for workers involved in the transport of spent nuclear fuel and high level waste by rail is provided in Ref. [19].

Data on doses to workers from the transport and handling of large numbers of packages for medical use and for industrial use are provided in Ref. [20].

To establish a relationship between the sum of the TIs for the packages transported and the external exposures received;

To determine the external exposure associated with the transport of packages with a unit TI that is representative of good practices in a specific transport operation;

To define a threshold for the sum of the TIs for the packages handled in a year, below which the occupational exposures are likely to be below 1 mSv in a year.

Reviews of individual and collective doses, and comparison with the results of the prior radiological evaluation to identify any problem areas;

Application of suitable segregation distances;

Adequate shielding arrangements;

Specific stowing, loading, unloading and tie‑down instructions for packages with high TIs;

Restrictions on access to areas with high dose rates;

Implementation of work schedules designed to optimize occupational exposures;

Use of equipment for movement and lifting of packages to reduce exposure time and/or increase distance between workers and packages;

Implementation of driving and routing restrictions (depending on the road conditions and the weather).

Engineered controls;

Administrative controls;

Personal protective equipment.”

4 Bq/cm² for beta and gamma emitters and low toxicity alpha emitters;

0.4 Bq/cm² for all other alpha emitters.

From workers in regularly occupied working areas by distances calculated using a dose criterion of 5 mSv in a year and conservative model parameters;

From members of the public in areas where the public has regular access by distances calculated using a dose criterion of 1 mSv in a year and conservative model parameters”.

Preparing transport documents in a low dose rate area instead of near the package(s);

Performing dose rate measurements at the package surface and at 1 m from the surface of the package by remote means;

Using mechanical means such as trolleys or carts to move packages to and from a conveyance instead of carrying individual packages against the body;

Planning work processes so that a conveyance can be loaded or unloaded in the minimum amount of time.

A ‘concept of operations’³⁷ for emergency response is developed at the beginning of the preparedness stage.

Emergency plans and procedures are prepared and, as appropriate, approved for any facility or activity, area or location that could give rise to an emergency warranting protective actions and other response actions.

To regain control of the situation and to mitigate consequences;

To save lives;

To avoid or to minimize severe deterministic effects;

To render first aid, to provide critical medical treatment and to manage the treatment of radiation injuries;

To reduce the risk of stochastic effects;

To keep the public informed and to maintain public trust;

To mitigate, to the extent practicable, non‑radiological consequences;

To protect, to the extent practicable, property and the environment;

To prepare, to the extent practicable, for the resumption of normal social and economic activity.”

General awareness/familiarization training:

Function specific training: Each person shall receive detailed training concerning specific radioactive material transport requirements that are applicable to the function that person performs.

Safety training: Commensurate with the risk of exposure in the event of a release, and with the functions performed, each person shall receive training on:

Each person shall receive training designed to provide familiarity with the general provisions of these Regulations.

The general awareness/familiarization training shall include a description of the categories of radioactive material; labelling, marking, placarding and packaging and segregation requirements; the purpose and content of the radioactive material transport document; and the available emergency response documents.

Methods and procedures for avoidance of accident conditions during transport, such as proper use of package handling equipment and appropriate methods of stowage of radioactive material.

Available emergency response information and how to use it.

General hazards presented by the various categories of radioactive material and how to prevent exposure to those hazards, including, if appropriate, the use of personal protective clothing and equipment.

Procedures to be immediately followed in the event of an unintentional release of radioactive material, including any emergency response procedures for which the person is responsible and personal protection procedures to be followed.”

INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport of Radioactive Material, 2018 Edition, IAEA Safety Standards Series No. SSR‑6 (Rev. 1), IAEA, Vienna (2018).

EUROPEAN COMMISSION, FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOUR ORGANIZATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN HEALTH ORGANIZATION, UNITED NATIONS ENVIRONMENT PROGRAMME, WORLD HEALTH ORGANIZATION, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, IAEA Safety Standards Series No. GSR Part 3, IAEA, Vienna (2014).

INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOUR OFFICE, Occupational Radiation Protection, IAEA Safety Standards Series No. GSG‑7, IAEA, Vienna (2018).

INTERNATIONAL ATOMIC ENERGY AGENCY, UNITED NATIONS ENVIRONMENT PROGRAMME, Radiation Protection of the Public and the Environment, IAEA Safety Standards Series No. GSG‑8, IAEA, Vienna (2018).

INTERNATIONAL MARITIME ORGANIZATION, International Maritime Dangerous Goods Code (IMDG Code) (amendment 41‑22), IMO, London (2022).

INTERNATIONAL ATOMIC ENERGY AGENCY, Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2018 Edition), IAEA Safety Standards Series No. SSG‑26 (Rev. 1), IAEA, Vienna (2022).

INTERNATIONAL ATOMIC ENERGY AGENCY, Leadership and Management for Safety, IAEA Safety Standards Series No. GSR Part 2, IAEA, Vienna (2016).

INTERNATIONAL ATOMIC ENERGY AGENCY, The Management System for the Safe Transport of Radioactive Material, IAEA Safety Standards Series No. TS G‑1.4, IAEA, Vienna (2008).

INTERNATIONAL ATOMIC ENERGY AGENCY, Criticality Safety in the Handling of Fissile Material, IAEA Safety Standards Series No. SSG‑27 (Rev. 1), IAEA, Vienna (2022).

INTERNATIONAL ATOMIC ENERGY AGENCY, Compliance Assurance for the Safe Transport of Radioactive Material, IAEA Safety Standards Series No. SSG‑78, IAEA, Vienna (2023).

JONES, A.L., CABIANCA, T., Survey into the Radiological Impact of the Normal Transport of Radioactive Material in the UK by Road and Rail, Rep. PHE‑CRCE‑035, Public Health England, London (2017).

HUGHES, J.S., HARVEY, M.P., A Survey into the Radiological Impact of the Normal Transport of Radioactive Material by Sea, Rep. HPA‑RPD‑050, Public Health England, London (2009).

HARVEY, M.P., JONES, A.L., CABIANCA, T., POTTER, M., Survey into the Radiological Impact of the Normal Transport of Radioactive Material by Air, Rep. PHE‑CRCE‑006, Public Health England, London (2014).

SHAPIRO, J., Exposure of Airport Workers to Radiation from Shipments of Radioactive Materials: A Review of Studies Conducted at Six Major Airports, Rep. NUREG‑0154, Nuclear Regulatory Commission, Washington, DC (1977).

INTERNATIONAL ATOMIC ENERGY AGENCY, Regulatory Control for the Safe Transport of Naturally Occurring Radioactive Material (NORM), IAEA‑TECDOC‑1728, IAEA, Vienna (2013).

ABDELHADY, A., Radiological risks associated with transportation of liquid waste generated from 99Mo production, J. Environ. Waste Manage. Recycl. 1 1 (2018) 1–4.

WILKENSON, W., Radiation Dose Assessment for the Transport of Nuclear Fuel Cycle Materials, Information Paper, WNTI, London (2006).

NUCLEAR REGULATORY COMMISSION, Spent Fuel Transportation Risk Assessment — Final Report, Rep. NUREG‑2125, Office of Nuclear Material Safety and Safeguards, Washington, DC (2014).

OFFICE OF RAILROAD SAFETY, Railroad Carrier Employee Exposure to Radiation — Report to Congress, USDOT, Washington, DC (2010).

SCHWARZ, G., FETT, H.‑J., LANGE, F., “Occupational and public exposures arising from the normal transport of radioactive material: Experience in Germany”, Proc. Int. Conf. on Safety of Transport of Radioactive Material, Vienna, 2003), IAEA, Vienna (2004) 97–100.

WATSON, S.J., OATWAY, W.B., JONES, A.L., HUGHES, J.S., Survey into the Radiological Impact of the Normal Transport of Radioactive Material in the UK by Road and Rail, Rep. NRPB‑W66, National Radiological Protection Board, Chilton, United Kingdom (2005).

WEINER, R.F., HINOJOSA, D., HEAMES, T.J., FARNUM, C.O., KALININA, E.A., RADTRAN 6/RadCat 6 User Guide, Rep. SAND2013‑8095, Sandia National Laboratories, Albuquerque, NM (2013).

ERICSSON, A.M., JAERNRY, C., INTERTRAN2 Transportation Risk Assessment Package, http://www.amckonsult.se

YUAN, Y.C., CHEN, S.Y., LEPOIRE, D.J., ROTHMAN, R., RISKIND: A Computer Program for Calculating Radiological Consequences and Health Risks from Transportation of Spent Nuclear Fuel, Rep. ANL/EAIS‑6, Argonne Natl Lab., IL (1993).

GROVE ENGINEERING, INC., MicroShield Version 13 (2023), https://radiationsoftware.com/microshield

KULESZA, J.A. (Ed.), MCNP Code Version 6.3.0 Theory & User Manual, LA‑UR‑22‑30006, Rev. 1, Los Alamos Natl Lab., NM (2022).

REARDEN, B.T., JESSEE, M.A. (Eds), SCALE Code System, ORNL/TM‑2005/39, Version 6.2.3, Oak Ridge Natl Lab., TN (2018).

HOMANN, S.G., ALUZZI, F., HotSpot Health Physics Codes Version 3.0 User’s Guide, LLNL‑SM‑636474, Lawrence Livermore Natl Lab., CA (2014).

INTERNATIONAL ATOMIC ENERGY AGENCY, Optimization of Radiation Protection in the Control of Occupational Exposure, Safety Reports Series No. 21, IAEA, Vienna (2002).

FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL CIVIL AVIATION ORGANIZATION, INTERNATIONAL LABOUR ORGANIZATION, INTERNATIONAL MARITIME ORGANIZATION, INTERPOL, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN HEALTH ORGANIZATION, PREPARATORY COMMISSION FOR THE COMPREHENSIVE NUCLEAR‑TEST‑BAN TREATY ORGANIZATION, UNITED NATIONS ENVIRONMENT PROGRAMME, UNITED NATIONS OFFICE FOR THE COORDINATION OF HUMANITARIAN AFFAIRS, WORLD HEALTH ORGANIZATION, WORLD METEOROLOGICAL ORGANIZATION, Preparedness and Response for a Nuclear or Radiological Emergency, IAEA Safety Standards Series No. GSR Part 7, IAEA, Vienna (2015).

INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL CIVIL AVIATION ORGANIZATION, INTERNATIONAL MARITIME ORGANIZATION, Preparedness and Response for a Nuclear or Radiological Emergency Involving the Transport of Radioactive Material, IAEA Safety Standards Series No. SSG‑65, IAEA, Vienna (2022).

FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOUR OFFICE, PAN AMERICAN HEALTH ORGANIZATION, WORLD HEALTH ORGANIZATION, Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency, IAEA Safety Standards Series No. GSG‑2, IAEA, Vienna (2011).

INTERNATIONAL ATOMIC ENERGY AGENCY, Application of the Management System for Facilities and Activities, IAEA Safety Standards Series No. GS‑G‑3.1, IAEA, Vienna (2006).

Training of workers and implementation of proper working procedures;

Assessment of worker exposures, if necessary, by individual monitoring or workplace monitoring;

Emergency procedures.’

Complete transport documents;

Measure dose rates and contamination and determine transport index;

Complete and apply package labels;

Load packages onto the vehicle;

Segregate packages;

Implement emergency procedures, if appropriate.

The number and type of packages;

The category and the transport index (TI) of packages;

The radionuclides being shipped;

The frequency of shipment;

The duration of storage and transport;

The tasks performed by the individual that involve radiation exposure.

Implement life saving measures and administer first aid;

Assess the risk of, or occurrence of, fire and use the fire extinguisher if appropriate;

Contact first responders (e.g. firefighting service, emergency medical service, response forces) as appropriate;

Contact a qualified expert in radiation protection and request advice;

Inform the “responsible person” at the main (carrier’s) office;

Maintain the ability to communicate electronically via telephone, radio and/or Internet.

Completion of transport documents;

Preparation of packages;

Measurement of dose rates and contamination, and determination of the transport index;

Completion and application of package labels;

Loading of packages onto the vehicle;

[Further tasks as appropriate].’

Training of workers and implementation of proper work procedures;

Assessment of worker exposures, if necessary, by individual monitoring or workplace monitoring;

Emergency procedures.

Complete transport documents;

Measure dose rates and contamination and determine the TI;

Complete and apply package labels and markings;

Load packages onto the vehicle;

Segregate packages;

Implement emergency procedures, if appropriate.

Obtain information about:

Deliver packages, including driving the vans and dropping off packages.

Implement emergency procedures, if appropriate.

Emergency procedures;

Conditions for storage, loading and securing of the packages onto the conveyance;

Placarding of the conveyance;

Measurements of dose rates around the loaded conveyance.

The number and type of packages handled and transported;

The categories of package and the TIs;

The radionuclides in the packages;

The frequency of shipment;

The duration of storage prior to transport.

Increasing the segregation distances beyond the minimum requirements, where possible;

Minimizing the presence of workers within 5 m of packages, and implementing job rotation among dispatch workers where there is the potential for high levels of radiation exposure and no other practicable means for controlling exposure is available;

Keeping the packages in the shielded bays in the storeroom until as late as possible before loading;

Using a trolley to take the packages from the storeroom to the loading area.

Implement life saving measures and administer first aid;

Assess the risk of, or occurrence of, fire and use the fire extinguisher if appropriate;

Contact first responders (e.g. firefighting service, emergency medical service, response forces) as appropriate;

Contact a qualified expert in radiation protection and request guidance;

Maintain the ability to communicate electronically via telephone, radio and/or Internet;

With the help of and under the direction of a qualified expert in radiation protection, clean up the affected area and collect the damaged packages and radioactive material, if any;

Obtain documentation from a qualified expert in radiation protection to confirm that the affected area is safe for normal use again;

Arrange for the transport of the radioactive material involved in the accident to an authorized recipient, as recommended by a qualified expert in radiation protection;

Inform the competent authority of the incident, in accordance with the applicable rules established by the competent authority.

Person responsible for this RPP ([Name of individual]): ………………..

Qualified expert in radiation protection: ………………..

Other contacts: ………………..

[Name of individual]…………………… (dispatch staff/driver)

[Name of individual]…………………… (dispatch staff/driver)

[Name of individual]…………………… (dispatch staff/driver)

Training of workers and implementation of proper work procedures;

Assessment of worker exposures by workplace monitoring;

Emergency procedures.

Transport documents;

Labelling and marking of the packages or overpacks;

Emergency procedures appropriate for the package or shipment.

Load/unload packages onto/from unit load devices² and/or barrows that are transported to/from the aircraft. All packages are loaded onto the floor of the unit load device and onto the floor of the barrow in accordance with ICAO⁠/⁠IATA requirements for segregation and securing of packages.

Drive the unit load devices and/or barrows within the warehouse or storage area and to/from the aircraft.

Load/unload packages and unit load devices into/from the aircraft cargo compartment in accordance with the load plan.

Implement emergency procedures, as appropriate.

The number and type of packages handled;

The categories of package and the TIs;

The radionuclides in the packages;

The frequency of shipment;

The length of time that packages are stored prior to or following air transport.

For packages that have not been loaded into a unit load device, using a trolley to move them between various locations (e.g. from the airport cargo acceptance area to the storage area; from the storage area to the loading area; from the loading area to the aircraft);

Keeping the packages in the storage room in a shielded bay, if available, until it is necessary to handle the packages;

Prior to loading packages containing radioactive material into unit load devices, ensuring that the necessary equipment, such as shoring material and tie‑down straps, are positioned at the unit load device before the packages are brought from the storage area;

Increasing segregation distances beyond the minimum ICAO/IATA requirements, where possible;

Minimizing the presence of workers within 5 m of the packages;

When carts and dollies carrying unit load devices are coupled together in series and transported, ensuring that unit load devices containing packages of radioactive material are put in the position farthest away from the driver;

When practicable, loading packages and/or unit load devices containing radioactive material into the aircraft cargo compartment last and unloading them first.

4 Bq/cm² in the case of beta and gamma emitters and low toxicity alpha emitters;

0.4 Bq/cm² for all other alpha emitters.

An aircraft accident or serious incident, where the flight is carrying radioactive material, XYZ Airlines will provide information, without delay, to emergency services responding to the accident or serious incident about the radioactive material on board, as shown in the information to the pilot in command. As soon as possible, XYZ Airlines will also provide this information to the appropriate authorities of the State where the principal place of business of XYZ Airlines is located and the State in which the accident or serious incident has occurred.

An aircraft accident or serious incident involving an aircraft carrying radioactive material, XYZ Airlines will activate the company emergency response plan, which includes instructions on the following:

Support of the activities of the ABC Airport emergency response plan;

Provision of information relating to the flight by the incident commander.

Person responsible for this RPP ([Name of individual]): ………………..

Qualified expert in radiation protection: ………………..

Other contacts: ………………..

[Name of individual]……………… (acceptance staff/cargo handler)

[Name of individual]……………… (acceptance staff/cargo handler)

[Name of individual]……………… (acceptance staff/cargo handler)

Training of workers and implementation of proper work procedures;

Assessment of worker exposures by individual monitoring or workplace monitoring;

Emergency procedures.

Complete transport documents;

Measure dose rates and determine the TI;

Complete and affix package labels and markings;

Load packages onto the vehicle;

Segregate and secure packages;

Implement emergency procedures, if appropriate.

Obtain information about actions to be taken in the event of an emergency, and implement these actions, if appropriate;

Obtain information about dose rates around the loaded vehicle;

Placard the vehicle.

The number and type of packages handled;

The category of packages and the TIs;

The radionuclides in the packages;

The frequency of shipment;

The duration of storage prior to transport.

Using a trolley to take the radiography devices from the storeroom to the loading area;

Keeping radiography devices in the storeroom in the shielded bays until as late as possible before loading;

Increasing segregation distances beyond the minimum requirements, where possible;

Minimizing the presence of workers within 5 m of the packages.

Implement life saving measures and administer first aid;

Assess the risk of, or occurrence of, fire and use the fire extinguisher if appropriate;

Contact first responders (e.g. firefighting service, emergency medical service, response forces) as appropriate;

Contact a qualified expert in radiation protection and request guidance;

Maintain the ability to communicate electronically via telephone, radio and/or Internet;

With the help of and under the direction of a qualified expert in radiation protection, clean up the affected area and collect the damaged packages and radioactive material, if any;

Obtain documentation from a qualified expert in radiation protection to confirm that the affected area is safe for normal use again;

Arrange for the transport of the radioactive material involved in the accident to an authorized recipient, as recommended by a qualified expert in radiation protection;

Inform the competent authority of the incident, in accordance with the applicable rules established by the competent authority.

Person responsible for this RPP ([Name of individual]): ………………..

Qualified expert in radiation protection: ………………..

Other contacts: ………………..

[Name of individual]……………………(radiographer)

[Name of individual]……………………(radiographer)

[Name of individual]……………………(radiographer)

Training of workers and implementation of proper work procedures;

Regular review of the workload to identify changes that would result in the need for a dose assessment programme for workers;

Emergency procedures.

Obtain information about:

Unload packages from and load packages onto conveyances.

Move packages within the port, including placing them in and removing them from storage in transit locations.

Implement emergency procedures, if appropriate.

Emergency procedures;

Conditions for storage in transit;

Loading and securing of the packages on the conveyance;

Unloading packages from the conveyance.

Commensurate with the hazards of the radioactive materials to be transported;

In compliance with the relevant international and national emergency response requirements;

Updated regularly in accordance with (a) and (b).

Have received basic training relating to dangerous goods, including radioactive material (Class 7);

Are aware of basic regulatory requirements, including those for storage in transit;

Are capable of recognizing labels for different types of dangerous cargo, reporting incidents and acting in accordance with emergency instructions and as directed by experts in the event of an emergency.

Training of workers and implementation of proper work procedures;

Assessment of worker exposures, if necessary, by individual monitoring or workplace monitoring;

Emergency procedures.

Obtain information on the following:

Load shipping containers onto the vessel.

Segregate and secure containers.

Implement actions to reduce doses to workers.

Implement emergency procedures, if appropriate.

Actions to be taken in the event of an emergency for each consignment;

Conditions for storage, loading and securing of each consignment.

The number and type of packages transported;

The category of packages and the TI;

The radionuclides in the packages;

The frequency of shipment.

Stowing all 20‑foot containers under deck within the vessel hull;

Positioning all 20‑foot containers door to door to lessen that chances that the doors will open as a result of some external event that results in a significant impact or force applied to the containers during transit;

Minimizing the crew members’ presence in the vicinity of the shipping containers;

Increasing segregation distances beyond the minimum requirements, where possible.

For dealing with fires and spills (leaks), implement the recommendations in Emergency Response Procedures for Ships Carrying Dangerous Goods (‘the EmS Guide’) [VI–4];

Implement life saving measures and administer first aid;

Assess the risk of, or occurrence of, fire and use the fire extinguisher if appropriate;

Contact first responders (e.g. firefighting service, emergency medical service, response forces) as appropriate;

Contact a qualified expert in radiation protection and request guidance;

Maintain the ability to communicate electronically via telephone, radio and/ or Internet;

With the help of and under the direction of a qualified expert in radiation protection, clean up the affected area and collect the damaged packages and radioactive material, if any;

Obtain documentation from a qualified expert in radiation protection to confirm that the affected area is safe for normal use again;

Arrange for the transport of the radioactive material involved in the accident to an authorized recipient, as recommended by a qualified expert in radiation protection;

Inform the competent authority of the incident, in accordance with the applicable rules established by the competent authority.

Person responsible for this RPP ([Name of individual]): ………………..

Qualified expert in radiation protection: ………………..

Other contacts: ………………..

[Name of individual]…………………… (captain)

[Name of individual]…………………… (crew member)

[Name of individual]…………………… (crew member)

[Name of individual]…………………… (crew member)

How does the RPP fit within the transport organization’s management system?

Does the scope of the RPP reflect completely and accurately what the RPP needs to cover?

Is the management commitment sufficiently demonstrated?

Are the resources (human and technical) available to fulfil the objectives of the RPP?

Are the roles and responsibilities of all workers concerned adequately described and fully outlined?

Has the prior radiological evaluation of the expected doses to workers in different workplaces been performed correctly? And is it still valid based on the results of workplace monitoring and individual monitoring?

Are the personnel involved in different actions sufficiently and correctly trained and familiar with equipment and instruments (including those that are not routinely used)?

Is the training correctly documented (e.g. certificates, expiry dates)?

If applicable (e.g. to consignors): Are the decisions on classification (e.g. UN number, proper shipping name), packaging (i.e. using the correct and optimized package design) and labelling taken by sufficiently qualified personnel, and are those decisions verified and properly documented and recorded?

Are the necessary approvals and certificates available and valid?

Are instructions and procedures that give clear and adequate guidance implemented by the workers to ensure that protection is optimized?

Are the instructions and procedures up to date and consistent with the objectives of the RPP?

Do the instructions and procedures cover all aspects, including emergency plans and procedures?

Is the measuring equipment (for dose rate, contamination and air monitoring, as appropriate) adequate for routine use or during an emergency, as appropriate?

Are there valid calibration certificates for the monitoring equipment that are relevant to the measurements to be made?

Are the user instructions for use of the monitoring equipment followed?

Are the results of measurements recorded, reported and reviewed?

.1 for crew in regularly occupied working areas, a dose of 5 mSv in a year;

.2 for passengers, in areas where the passengers have regular access, a dose of 1 mSv in a year, taking account of the exposures expected to be delivered by all other relevant sources and practices under control.

by following the segregation table for persons (table 7.1.4.5.18) in respect of living quarters or spaces regularly occupied by persons.

by demonstration that, for the following indicated exposure times, the direct measurement of the radiation level in regularly occupied spaces and living quarters is less than: for the crew: 0.0070 mSv/h up to 700 h in a year, or 0.0018 mSv/h up to 2750 h in a year; and for the passengers: 0.0018 mSv/h up to 550 h in a year, taking into account any relocation of cargo during the voyage. In all cases, the measurements of radiation level must be made and documented by a suitably qualified person.