| Main |
1.1. |
This Safety Requirements publication supersedes the edition of Site Evaluation for Nuclear Installations that was issued in 2016 as IAEA Safety Standards Series No. NS-R-3 (Rev. 1). NS-R-3 (Rev. 1) was a partial revision of IAEA Safety Standards Series No. NS-R-3 issued in 2003 and it took into account issues highlighted after the Fukushima Daiichi accident. This publication takes into account developments that have occurred since 2003 in relation to site evaluation for nuclear installations. |
| Main |
1.2. |
The requirements for site evaluation for nuclear installations established in this publication are intended to contribute to the protection of workers and the public, and to the protection of the environment, from harmful effects of ionizing radiation, in order to meet the fundamental safety objective established in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles [1]. It is recognized that there are steady advances in technology and scientific knowledge in nuclear safety and corresponding advances in what is considered adequate protection. Safety requirements evolve with these advances, and this publication reflects the present consensus among States. |
| Main |
1.3. |
This Safety Requirements publication establishes requirements for site evaluation for nuclear installations, in order to meet the fundamental safety objective [1]. Several related Safety Guides (see Refs [2–8]) provide recommendations on how to meet the requirements for site evaluation for nuclear installations as contained in this publication. |
| Main |
1.4. |
The objective of this publication is to establish requirements for:Defining the information to be used in the site evaluation process;
Evaluating a site such that the site specific hazards and the safety related site characteristics are adequately taken into account, in order to derive appropriate site specific design parameters;
Analysing the characteristics of the population and the region surrounding the site to determine whether there would be significant difficulties in implementing emergency response actions effectively [9].
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| Main |
1.5. |
The requirements in this publication are to be applied: To identify the natural and human induced external hazards that could affect the safety of the nuclear installation;
To assess the interactions between the site and nuclear installation for operational states and accident conditions, over the lifetime of the nuclear installation, including accidents that could warrant the implementation of emergency response actions.
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| Main |
1.6. |
This publication is intended for use by regulatory bodies in establishing regulatory requirements, and by operating organizations or their contractors in conducting site evaluation for nuclear installations. |
| Main |
1.7. |
The requirements in this publication apply to all nuclear installations [10], as follows: Nuclear power plants;
Research reactors (including subcritical and critical assemblies) and any adjoining radioisotope production facilities;
Storage facilities for spent fuel;
Facilities for the enrichment of uranium;
Nuclear fuel fabrication facilities;
Conversion facilities;
Facilities for the reprocessing of spent fuel;
Facilities for the predisposal management of radioactive waste arising from nuclear fuel cycle facilities;
Nuclear fuel cycle related research and development facilities.
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| Main |
1.8. |
This Safety Requirements publication covers site evaluation for both new and existing nuclear installations. For existing nuclear installations, decisions concerning the implementation of new or enhanced safety features will need to consider, as practicable, the safety significance of such features, as well as economic, social and environmental factors. |
| Main |
1.9. |
The ‘site area’ is the geographical area that contains an authorized facility, authorized activity or source, and within which the management of the authorized facility or authorized activity or first responders may directly initiate an emergency response [9]. The site area is typically the area within the security perimeter fence or other designated property marker. |
| Main |
1.10. |
The ‘external zone’ is the area immediately surrounding a proposed site area in which the population distribution and density, and land and water uses, are considered with respect to their impact on planning effective emergency response actions [9]. |
| Main |
1.11. |
The word ‘region’ is used generally in this publication to refer to the area surrounding the site and is normally intended to include more than the external zone. The size of this region will be defined for each specific external hazard (see para. 4.14). This region is also sometimes known as the ‘geographical area of interest’. |
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1.12. |
The ‘site vicinity’ is smaller than the region and larger than the site area (typically covering a geographical area not less than 5 km in radius). |
| Main |
1.13. |
The human induced external events considered in this Safety Requirements publication are all of accidental origin. Considerations relating to the physical protection of the nuclear installation against sabotage, and to physical protection against unauthorized removal or sabotage of the nuclear material, are outside the scope of this publication, although such considerations are likely to have significant implications for site evaluation. This publication does not address the threat assessment of malicious acts. Recommendations for the establishment of the design basis threat are provided in IAEA Nuclear Security Series No. 13 [11] and in supporting publications in the IAEA Nuclear Security Series. |
| Main |
1.14. |
The interfaces between nuclear safety and nuclear security have to be considered and synergies have to be developed so that safety and nuclear security complement and enhance one another. For example, site specific design parameters for the qualification of structures, systems and components important to safety against natural and human induced external hazards, as required in this publication, can also be used for the qualification of structures, systems and components important for nuclear security against relevant external hazards. |
| Main |
1.15. |
The siting process for a nuclear installation is divided into two stages: Site survey, in which candidate sites are identified after the investigation of a large region and the rejection of unsuitable sites;
Site selection, in which the candidate sites are assessed by screening, evaluation, comparison and ranking on the basis of safety and other considerations to select one or more preferred candidate sites.
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| Main |
1.16. |
The suitability of the site is then confirmed in the site evaluation process. The site evaluation process starts with the second stage of the siting process (i.e. site selection), and continues throughout the entire lifetime of the nuclear installation. The detailed site evaluation (for the selected site) provides input to the preliminary safety analysis report and the final safety analysis report. Site evaluation continues throughout the operational stage of the nuclear installation, and includes monitoring, periodic safety review and other activities to confirm the site specific design parameters as well as safety re-evaluations based on the outcome of periodic safety reviews. |
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1.17. |
This publication addresses the evaluation of those site related factors that have to be taken into account to ensure that the site–installation combination does not constitute an unacceptable risk to people or the environment over the lifetime of the nuclear installation. It is recognized that there are other important factors in site evaluation, such as technology, economics, non-radiological environmental impacts and socioeconomic impacts, as well as the opinion of interested parties, including the public. Such aspects of site evaluation are not covered in this publication. |
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1.18. |
Section 2 of this publication sets out the fundamental safety objective and the safety principles applicable to site evaluation. Section 3 establishes requirements for the application of the management system for site evaluation. Section 4 establishes the general requirements that are applicable to all types of external hazard. Section 5 establishes requirements for specific technical aspects related to the evaluation of natural and human induced external hazards. Section 6 establishes requirements for specific technical aspects related to the evaluation of the effects of the nuclear installation on the surrounding environment (including the atmosphere, the hydrosphere and the biosphere) and on the population. Section 7 establishes requirements for monitoring and periodic review of natural and human induced external hazards and site conditions throughout the lifetime of the nuclear installation. |
| Main |
2.1. |
As stated in SF-1 [1]: “The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation.” Paragraph 2.1 of SF-1 [1] states: To control the radiation exposure of people and the release of radioactive material to the environment;
To restrict the likelihood of events that might lead to a loss of control over a nuclear reactor core, nuclear chain reaction, radioactive source or any other source of radiation;
To mitigate the consequences of such events if they were to occur.”
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| Main |
2.2. |
Paragraph 2.2 of SF-1 [1] states: |
| Main |
2.3. |
This Safety Requirements publication establishes requirements for application of the principles of SF-1 [1], in particular Principles 8 and 9: “All practical efforts must be made to prevent and mitigate nuclear or radiation accidents” (Principle 8 of SF-1 [1]).
“The primary means of preventing and mitigating the consequences of accidents is ‘defence in depth’. Defence in depth is implemented primarily through the combination of a number of consecutive and independent levels of protection that would have to fail before harmful effects could be caused to people or to the environment” (para. 3.31 of SF-1 [1]).
“Defence in depth is provided by an appropriate combination of [inter alia] … [a]dequate site selection and the incorporation of good design and engineering features providing safety margins, diversity and redundancy” (para. 3.32 of SF-1 [1]).
“Arrangements must be made for emergency preparedness and response for nuclear or radiation incidents” (Principle 9 of SF-1 [1]).
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2.4. |
To address Principle 8 of SF-1 [1], site evaluation for a nuclear installation shall characterize the natural and human induced external hazards that could affect the safety of the nuclear installation (see Requirement 1). The site evaluation shall provide adequate input to the design and safety assessment for demonstration of protection of people and the environment from harmful effects of ionizing radiation. |
| Main |
2.5. |
To address Principle 9 of SF-1 [1], site evaluation for a nuclear installation shall provide adequate input for demonstration of protection of people and the environment from the consequences of radioactive releases. The site evaluation shall identify the site characteristics that could affect the feasibility of planning effective emergency response actions in the external zone. |
| Requirement 1: Safety objective in site evaluation for nuclear installations |
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The safety objective in site evaluation for nuclear installations shall be to characterize the natural and human induced external hazards that might affect the safety of the nuclear installation, in order to provide adequate input for demonstration of protection of people and the environment from harmful effects of ionizing radiation. |
| Requirement 1: Safety objective in site evaluation for nuclear installations |
2.6. |
The safety objective in site evaluation is derived from the fundamental safety objective established in SF-1 [1]. Demonstration of compliance with the safety requirements established in this publication provides the basis for demonstration of achievement of the safety objective for site evaluation. |
| Requirement 2: Application of the management system for site evaluation |
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Site evaluation shall be conducted in a comprehensive, systematic, planned and documented manner in accordance with a management system. |
| Requirement 2: Application of the management system for site evaluation |
3.1. |
An integrated management system that meets the requirements of IAEA Safety Standards Series No. GSR Part 2, Leadership and Management for Safety [12] shall be established. The management system shall cover the organization, planning, work control, verification and documentation of activities and qualification and training of personnel to ensure that the required quality of the work is achieved at each stage of site evaluation. The management system shall be implemented at the earliest possible time in the conduct of site evaluation for the nuclear installation. |
| Requirement 2: Application of the management system for site evaluation |
3.2. |
Site evaluation shall include, as part of the management system, proper quality assurance arrangements covering each activity that could influence safety or affect the derivation of site specific design parameters and other safety related site characteristics. The quality assurance arrangements shall be consistent with regulatory requirements and their application shall be commensurate with the importance of the activity under consideration to safety. |
| Requirement 2: Application of the management system for site evaluation |
3.3. |
For each site evaluation activity, including inspection, testing, verification and validation, the acceptance criteria and the responsibilities for performing the activity shall be specified. |
| Requirement 2: Application of the management system for site evaluation |
3.4. |
The results of studies and investigations conducted as part of the site evaluation shall be documented in sufficient detail to permit an independent review. |
| Requirement 2: Application of the management system for site evaluation |
3.5. |
An independent review shall be made of the evaluation of the natural and human induced external hazards and the site specific design parameters, and of the evaluation of the potential radiological impact of the nuclear installation on people and the environment. |
| Requirement 3: Scope of the site evaluation for nuclear installations |
|
The scope of the site evaluation shall encompass factors relating to the site and factors relating to the interaction between the site and the installation, for all operational states and accident conditions, including accidents that could warrant emergency response actions. |
| Requirement 3: Scope of the site evaluation for nuclear installations |
4.1. |
The scope of the site evaluation shall cover all external hazards, monitoring activities and site specific parameters relevant for the safety of the nuclear installation. In determining the scope of the site evaluation, a graded approach shall be applied commensurate with the radiation risk posed to people and the environment. |
| Requirement 3: Scope of the site evaluation for nuclear installations |
4.2. |
The application of the safety requirements for site evaluation for nuclear installations shall be commensurate with the potential hazards associated with the nuclear installation. |
| Requirement 3: Scope of the site evaluation for nuclear installations |
4.3. |
The level of detail needed in the evaluation of a site for a nuclear installation shall be commensurate with the risk associated with the nuclear installation and the site and will differ depending on the type of nuclear installation. |
| Requirement 3: Scope of the site evaluation for nuclear installations |
4.4. |
The scope and level of detail of the site evaluation process necessary to support the safety demonstration for the nuclear installation shall be determined in accordance with a graded approach. |
| Requirement 3: Scope of the site evaluation for nuclear installations |
4.5. |
For site evaluation for nuclear installations other than nuclear power plants, the following shall be taken into consideration in the application of a graded approach: The amount, type and status of the radioactive inventory at the site (e.g. whether the radioactive material on the site is in solid, liquid and/or gaseous form, and whether the radioactive material is being processed in the nuclear installation or is being stored on the site);
The intrinsic hazards associated with the physical and chemical processes that take place at the nuclear installation;
For research reactors, the thermal power;
The distribution and location of radioactive sources in the nuclear installation;
The configuration and layout of installations designed for experiments, and how these might change in future;
The need for active systems and/or operator actions for the prevention of accidents and for the mitigation of the consequences of accidents;
The potential for on-site and off-site consequences in the event of an accident.
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| Requirement 4: Site suitability |
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The suitability of the site shall be assessed at an early stage of the site evaluation and shall be confirmed for the lifetime of the planned nuclear installation. |
| Requirement 4: Site suitability |
4.6. |
In the assessment of the suitability of a site for a nuclear installation, the following aspects shall be addressed at an early stage of the site evaluation: The effects of natural and human induced external events occurring in the region that might affect the site;
The characteristics of the site and its environment that could influence the transfer of radioactive material released from the nuclear installation to people and to the environment;
The population density, population distribution and other characteristics of the external zone, in so far as these could affect the feasibility of planning effective emergency response actions [9], and the need to evaluate the risk to individuals and to the population.
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| Requirement 4: Site suitability |
4.7. |
The site shall be deemed unsuitable for a nuclear installation if one or more of the three aspects listed in para. 4.6 indicates that the site is unacceptable and the deficiencies cannot be compensated for by means of a combination of measures for site protection, design features of the nuclear installation and administrative procedures. |
| Requirement 4: Site suitability |
4.8. |
Site suitability shall be assessed on the basis of relevant current data and methodologies. If relevant, conservative criteria shall be developed in relation to site specific accident scenarios, and the consistency of such criteria with the overall site suitability shall be demonstrated. |
| Requirement 4: Site suitability |
4.9. |
A decision regarding the suitability of the site shall be based on the characteristics of the nuclear installation, including planned operations at the site, the amount and nature of potential radioactive releases and their impact on people and the environment. |
| Requirement 4: Site suitability |
4.10. |
For nuclear power plants, the total nuclear capacity to be installed at the site shall be determined at the first stages of the siting process. If it is later determined or anticipated that the installed nuclear capacity (or, for other nuclear installations, the inventory of nuclear material) or its impact has increased to a level significantly greater than that previously determined to be acceptable, the site shall be re-evaluated considering the higher capacity, inventory or impact. |
| Requirement 4: Site suitability |
4.11. |
In the overall evaluation of site suitability, site specific attributes, such as cooling water availability or extreme environmental conditions, and their potential role in affecting the safe and continuous operation of the nuclear installation, shall also be addressed. |
| Requirement 5: Site and regional characteristics |
|
The site and the region shall be investigated with regard to the characteristics that could affect the safety of the nuclear installation and the potential radiological impact of the nuclear installation on people and the environment. |
| Requirement 5: Site and regional characteristics |
4.12. |
Natural phenomena as well as human activities in the region with the potential to induce hazards at the site that might affect the safety of the nuclear installation shall be identified and evaluated. The extent of this evaluation shall be commensurate with the safety significance of the potential hazards at the site. |
| Requirement 5: Site and regional characteristics |
4.13. |
The characteristics of the natural environment in the region that could be affected by the potential radiological impact of the nuclear installation shall be investigated and assessed, for all operational states and accident conditions and for all stages of the lifetime of the nuclear installation (see Section 6). |
| Requirement 5: Site and regional characteristics |
4.14. |
The size of the region to be investigated shall be defined for each of the natural and human induced external hazards. Both the magnitude of the hazard and the distance from the source of the hazard to the site shall be considered in determining the size of the region to be investigated. For certain natural external events, such as tsunamis and volcanic phenomena, it shall be ensured that the size of the region that is investigated is sufficiently large to address the potential effects at the site. |
| Requirement 5: Site and regional characteristics |
4.15. |
The site and the region shall be studied to evaluate the present and foreseeable future characteristics that could have an impact on the safety of the nuclear installation. This includes potential changes in the severity and/or the frequency of natural external events, as well as changes in the population distribution in the region, the present and future use of land and water, the further development of existing nuclear installations or the construction of other facilities that could affect the safety of the nuclear installation or the feasibility of planning effective emergency response actions. |
| Requirement 6: Identification of site specific hazards |
|
Potential external hazards associated with natural phenomena, human induced events and human activities that could affect the region shall be identified through a screening process. |
| Requirement 6: Identification of site specific hazards |
4.16. |
The process and associated criteria used in the screening of site specific hazards shall comply with the safety objective for site evaluation and shall be properly justified and documented. |
| Requirement 6: Identification of site specific hazards |
4.17. |
The scope of evaluation of external events in the screening process shall cover the full ranges of severity and frequency of occurrence relevant for the design and the safety assessment of the nuclear installation, including events of high severity but low probability that could contribute to the overall risk. |
| Requirement 6: Identification of site specific hazards |
4.18. |
An event might be screened out because it is enveloped by a set of events. However, it shall be ensured that all potential effects of the screened-out event are bounded by this set of events. |
| Requirement 6: Identification of site specific hazards |
4.19. |
External hazards that are not excluded by the screening process shall be evaluated and then used in establishing the site specific design parameters and in the re-evaluation of the site, in accordance with the significance of these hazards to the safety of the nuclear installation. |
| Requirement 7: Evaluation of natural and human induced external hazards |
|
The impact of natural and human induced external hazards on the safety of the nuclear installation shall be evaluated over the lifetime of the nuclear installation. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.20. |
The site evaluation for a nuclear installation shall consider the frequency and severity of natural and human induced external events, and potential combinations of such events, that could affect the safety of the nuclear installation. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.21. |
Information on the frequency and severity of external events derived from the characterization of the hazards shall be used in establishing the site specific design parameters. Adequate account shall be taken of both aleatory uncertainties and epistemic uncertainties in the establishment of site specific design parameters. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.22. |
Appropriate methods, supported by numerical models when necessary, shall be used to characterize the hazards relevant for site evaluation and the design of the nuclear installation. A thorough uncertainty analysis of the method and input data shall be performed as part of the hazard evaluation. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.23. |
The decision to use deterministic and/or probabilistic methodologies in hazard evaluation shall be based on the nature of the hazard, the availability of data and the applicable requirements for safety assessment. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.24. |
Special consideration shall be given to the use of applicable probabilistic methodologies and the use of probabilistic hazard curves representing external events as an input to the probabilistic safety assessment for external hazards. Such probabilistic hazard curves shall be developed with reference to the specific site conditions. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.25. |
The evaluation of hazards shall address the possibility that external events can occur in combination, simultaneously or within short time frames. Interrelationships and causality between external events shall be evaluated. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.26. |
The results of the evaluation of hazards shall be expressed in terms that can be used as an input for deriving the site specific design parameters; that is, appropriate parameters for describing the severity of the effects of the hazards shall be selected or developed. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.27. |
The potential for explosion, chemical releases and/or thermal releases that might affect the safety of the nuclear installation or the dispersion of radioactive material shall be considered in the site evaluation process. |
| Requirement 7: Evaluation of natural and human induced external hazards |
4.28. |
The potential for interactions between radioactive and non-radioactive substances, such as interactions due to heat or chemicals in radioactive liquid effluents, shall be considered. |
| Requirement 8: Measures for site protection |
|
If the projected design of the nuclear installation is not able to safely withstand the impact of natural and human induced external hazards, the need for site protection measures shall be evaluated. |
| Requirement 8: Measures for site protection |
4.29. |
The need for protection of the site against the effects of specific phenomena associated with natural and human induced external hazards shall be evaluated considering adequate safety margins. |
| Requirement 8: Measures for site protection |
4.30. |
The availability of adequate engineering solutions for implementing measures for site protection shall be evaluated. If such engineering solutions are not available, the site shall be deemed unsuitable. |
| Requirement 8: Measures for site protection |
4.31. |
If measures for site protection are required to be implemented, uncertainties shall be properly taken into account in the evaluation of extreme values of parameters for describing the severity of natural and human induced external hazards. Measures for site protection shall be classified, designed, built, maintained and operated in accordance with their safety significance. |
| Requirement 9: Site evaluation for multiple nuclear installations on the same site or on adjacent sites |
|
The site evaluation shall consider the potential for natural and human induced external hazards to affect multiple nuclear installations on the same site as well as on adjacent sites. |
| Requirement 9: Site evaluation for multiple nuclear installations on the same site or on adjacent sites |
4.32. |
Occurrences of natural and human induced external events and their credible combinations that could affect the safety of multiple installations on the same site or installations on adjacent sites shall be considered. The potential for hazards originating from one nuclear installation to affect other nuclear installations located on the same site or on adjacent sites shall be assessed. |
| Requirement 9: Site evaluation for multiple nuclear installations on the same site or on adjacent sites |
4.33. |
For identified accident scenarios, the combined effects of accidents at nuclear installations located on the same site or at adjacent and nearby sites on people and the environment shall be evaluated (see Requirement 12). |
| Requirement 10: Changes of hazards and site characteristics with time |
|
The external hazards and the site characteristics shall be assessed in terms of their potential for changing over time and the potential impact of these changes shall be evaluated. |
| Requirement 10: Changes of hazards and site characteristics with time |
4.34. |
The site characteristics and the natural and human induced external hazards that can change over time and which could affect the safety of a nuclear installation shall be identified. The potential consequences of such changes shall be duly assessed for the planned lifetime of the nuclear installation. |
| Requirement 10: Changes of hazards and site characteristics with time |
4.35. |
Due account shall be taken of uncertainties in the projections of any potential changes of the external hazards and site characteristics over time by means of appropriate safety margins in the related site specific design parameters. |
| Requirement 11: Special considerations for the ultimate heat sink for nuclear installations that require an ultimate heat sink |
|
The evaluation of site specific natural and human induced external hazards for nuclear installations that require an ultimate heat sink shall consider hazards that could affect the availability and reliability of the ultimate heat sink. |
| Requirement 11: Special considerations for the ultimate heat sink for nuclear installations that require an ultimate heat sink |
4.36. |
As appropriate for the ultimate heat sink under consideration, data for the following shall be evaluated: Air temperature and humidity;
Water depth and temperature;
Water quality characteristics, including turbidity, suspended solids, floating debris, and chemical and biochemical changes (both natural and human induced changes);
Availability and sustainability of the water flow (for a river), minimum and maximum water level and the period of time for which safety related supplies of cooling water are at a minimum level, with account taken of the potential for failure of water control structures.
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| Requirement 11: Special considerations for the ultimate heat sink for nuclear installations that require an ultimate heat sink |
4.37. |
All natural and human induced external events that could cause a loss of the ultimate heat sink shall be identified and evaluated. |
| Requirement 12: Potential effects of the nuclear installation on people and the environment |
|
In determining the potential radiological impact of the nuclear installation on the region for operational states and accident conditions, including accidents that could warrant emergency response actions, appropriate estimates shall be made of the potential releases of radioactive material, with account taken of the design of the nuclear installation and its safety features. |
| Requirement 12: Potential effects of the nuclear installation on people and the environment |
4.38. |
The potential effects of the nuclear installation on people and the environment shall be estimated by considering the postulated accident scenarios (including the resulting source terms) and taking into account the feasibility of planning effective emergency response actions at the site and in the external zone. These estimates shall be confirmed when the design of the nuclear installation and its safety features has been established. |
| Requirement 12: Potential effects of the nuclear installation on people and the environment |
4.39. |
The direct and indirect pathways by which radioactive releases from the nuclear installation could potentially affect the public and the environment shall be identified and evaluated. In this evaluation, specific regional and site characteristics, including the population distribution in the region, shall be taken into account, with special attention paid to the transport and accumulation of radionuclides in the biosphere. |
| Requirement 12: Potential effects of the nuclear installation on people and the environment |
4.40. |
It shall be demonstrated that the information provided to assess the potential effects on the population associated with accident conditions, including accidents that could warrant emergency response actions being taken in the external zone, is consistent with achieving the safety objective for site evaluation. |
| Requirement 13: Feasibility of planning effective emergency response actions |
|
The feasibility of planning effective emergency response actions on the site and in the external zone shall be evaluated, with account taken of the characteristics of the site and the external zone as well as any external events that could hinder the establishment of complete emergency arrangements prior to operation. |
| Requirement 13: Feasibility of planning effective emergency response actions |
4.41. |
Requirement 13 applies also to the infrastructure of the external zone where emergency response actions might be warranted. |
| Requirement 13: Feasibility of planning effective emergency response actions |
4.42. |
An assessment shall be made of the feasibility of planning effective emergency response actions in accordance with GSR Part 7 [9]. Nuclear installations on the same site and at adjacent or nearby sites shall be considered in the assessment, with special emphasis on nuclear installations that could experience concurrent accidents. |
| Requirement 13: Feasibility of planning effective emergency response actions |
4.43. |
Any causal relationships between external events and the condition of the infrastructure on the site and in the external zone shall be considered when evaluating the feasibility of planning effective emergency response actions. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
|
The data necessary to perform an assessment of natural and human induced external hazards and to assess both the impact of the environment on the safety of the nuclear installation and the impact of the nuclear installation on people and the environment shall be collected. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
4.44. |
Data on natural and human induced external hazards with the potential to affect the safety of the nuclear installation shall be collected throughout the lifetime of the nuclear installation. Data shall be confirmed to be relevant (spatially and temporally) to the site, with preference given to the use of site specific data in site evaluation. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
4.45. |
The extent, objectives and scope of the data collection process shall be defined on the basis of the safety objective for site evaluation, and shall be commensurate with the hazard posed by the nuclear installation to people and the environment. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
4.46. |
At a minimum, the data collection process shall include the following: Information on natural and human induced external hazards, including information on sources of hazards, propagation of hazards and the potential effects on the nuclear installation and on people and the environment;
Information describing site conditions and regional environmental conditions;
Information on the proposed engineering and administrative measures for site protection and mitigatory measures;
Information on the potential impact of the nuclear installation on people and the environment for operational states and accident conditions;
Information required for planning effective emergency response actions on the site and off the site in all environmental conditions and for all states of the nuclear installation;
Information on conditions for access to the site and information for supporting design and development of the site infrastructure.
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| Requirement 14: Data collection in site evaluation for nuclear installations |
4.47. |
Information and records, if available, of the occurrence and severity of important prehistoric, historical and recent natural phenomena shall be obtained as appropriate for the hazard to be evaluated and shall be analysed for reliability, accuracy, temporal and spatial relevance, and completeness. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
4.48. |
The data shall be maintained and reviewed periodically, and/or as necessary as part of a review of the site evaluation within the framework of the periodic safety review of the nuclear installation, for example, to address developments in data gathering techniques and in the analysis and use of data and to confirm that the data remain relevant to the site within the context of evolving hazards. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
4.49. |
The data collected for site investigations shall be of sufficient quality and quantity to support the selected methodology for hazard evaluation. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
4.50. |
The details of the information collected for each hazard shall be appropriate for the distance between the source of the hazard and the site and the potential impact on the site. The sources of uncertainties relating to data collection shall be documented. |
| Requirement 14: Data collection in site evaluation for nuclear installations |
5.1. |
This section establishes requirements for the evaluation of external hazards. These requirements are to be applied as appropriate for the type of nuclear installation as well as the site under consideration. |
| Requirement 15: Evaluation of fault capability |
|
Geological faults larger than a certain size and within a certain distance of the site and that are significant to safety shall be evaluated to identify whether these faults are to be considered capable faults. For capable faults, potential challenges to the safety of the nuclear installation in terms of ground motion and/or fault displacement hazards shall be evaluated. |
| Requirement 15: Evaluation of fault capability |
5.2. |
|
| Requirement 15: Evaluation of fault capability |
5.3. |
The potential effect of fault displacement on safety related structures, systems and components shall be evaluated. The evaluation of fault displacement hazards shall include detailed geological mapping of excavations for safety related engineered structures to enable the evaluation of fault capability for the site. |
| Requirement 15: Evaluation of fault capability |
5.4. |
A proposed new site shall be considered unsuitable when reliable evidence shows the existence of a capable fault that has the potential to affect the safety of the nuclear installation and which cannot be compensated for by means of a combination of measures for site protection and design features of the nuclear installation. If a capable fault is identified in the site vicinity of an existing nuclear installation, the site shall be deemed unsuitable if the safety of the nuclear installation cannot be demonstrated. |
| Requirement 16: Evaluation of ground motion hazards |
|
An evaluation of ground motion hazards shall be conducted to provide the input needed for the seismic design or safety upgrading of the structures, systems and components of the nuclear installation, as well as the input for performing the deterministic and/or probabilistic safety analyses necessary during the lifetime of the nuclear installation. |
| Requirement 16: Evaluation of ground motion hazards |
5.5. |
Hazards due to earthquake induced ground motion shall be assessed by means of appropriate methods. The effect of the vibratory ground motion in combination with other seismically induced events, if any, shall be considered. The potential for seismicity due to human activities shall also be considered. |
| Requirement 17: Evaluation of volcanic hazards |
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Hazards due to volcanic activity that have the potential to affect the safety of the nuclear installation shall be evaluated. |
| Requirement 17: Evaluation of volcanic hazards |
5.6. |
Capable volcanoes shall be identified and evaluated. The evaluation shall consider the volcanic characteristics of a region of sufficient size to ensure that potentially hazardous volcanic phenomena are considered appropriately. |
| Requirement 17: Evaluation of volcanic hazards |
5.7. |
The hazards of capable volcanoes shall be evaluated to provide the input needed for determining the site specific design parameters or for re-evaluating the site, as well as for deterministic and/or probabilistic safety analyses performed during the lifetime of the nuclear installation. |
| Requirement 17: Evaluation of volcanic hazards |
5.8. |
A proposed new site shall be considered unsuitable if reliable evidence shows the existence of a capable volcano that has the potential to affect the safety of the nuclear installation and which cannot be compensated for by means of a combination of measures for site protection and design features of the nuclear installation. |
| Requirement 17: Evaluation of volcanic hazards |
5.9. |
An evaluation of volcanic hazards that focuses on determining the geological characteristics of volcanic phenomena and their spatial extent will usually be more certain than one focusing on an estimation of the likelihood of occurrence of hazardous phenomena. Volcanic hazards shall be evaluated using appropriate information, methods and models with adequate account taken of the uncertainties. |
| Requirement 17: Evaluation of volcanic hazards |
5.10. |
The effect of volcanic phenomena in combination with other volcanically induced hazards shall be considered. This shall include consideration of volcanic ash fall. |
| Requirement 18: Evaluation of extreme meteorological hazards |
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Extreme meteorological hazards and their possible combinations that have the potential to affect the safety of the nuclear installation shall be evaluated. |
| Requirement 18: Evaluation of extreme meteorological hazards |
5.11. |
Meteorological phenomena such as wind, precipitation, snow and ice, air and water temperature, humidity, storm surges and sand or dust storms, as well as their credible combinations, shall be evaluated for their extreme values based on available records. If necessary, efforts shall be made to extend the database on meteorological hazards (e.g. by incorporating historical climate data, numerical models and simulations). |
| Requirement 18: Evaluation of extreme meteorological hazards |
5.12. |
Appropriate methods shall be applied for the evaluation of meteorological hazards, taking into account the amount of data available (both measured data and historical data) and known past changes in relevant characteristics of the region. |
| Requirement 19: Evaluation of rare meteorological events |
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The potential for the occurrence of rare meteorological events such as lightning, tornadoes and cyclones, including information on their severity and frequency, shall be evaluated. |
| Requirement 19: Evaluation of rare meteorological events |
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Lightning |
| Requirement 19: Evaluation of rare meteorological events |
5.13. |
The potential for the occurrence and the frequency and severity of lightning shall be evaluated for the site vicinity. |
| Requirement 19: Evaluation of rare meteorological events |
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Tornadoes and cyclones |
| Requirement 19: Evaluation of rare meteorological events |
5.14. |
The potential for the occurrence and the frequency and severity of tornadoes, cyclones and associated missiles shall be evaluated for the site. The hazards associated with tornadoes and cyclones shall be derived and expressed in terms of parameters such as rotational wind speed, translational wind speed, radius of maximum rotational wind speed, pressure differentials and rate of change of pressure. |
| Requirement 20: Evaluation of flooding hazards |
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Hazards due to flooding, considering natural and human induced events including their possible combinations, shall be evaluated. |
| Requirement 20: Evaluation of flooding hazards |
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Floods due to precipitation and other natural causes |
| Requirement 20: Evaluation of flooding hazards |
5.15. |
The potential for flooding in the region surrounding the site due to one or more natural causes, such as storm surge, wind generated waves, meteorological tsunamis or seiches, or extreme precipitation — or due to a combination of such events that have a common cause or a relatively high frequency of occurrence — shall be evaluated. |
| Requirement 20: Evaluation of flooding hazards |
5.16. |
Appropriate meteorological, hydrological and hydraulic models shall be developed to derive the flooding hazards for the site, including secondary effects such as debris, ice and sediments. Where available, relevant information from studies of historic and prehistoric floods shall be used to inform estimates of the frequency and magnitude of riverine floods. |
| Requirement 20: Evaluation of flooding hazards |
5.17. |
The potential for instability of a coastal area or river channel due to erosion or sedimentation shall be investigated. |
| Requirement 20: Evaluation of flooding hazards |
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Water waves induced by earthquakes or other geological phenomena |
| Requirement 20: Evaluation of flooding hazards |
5.18. |
The potential for tsunamis or seiches in the region that could affect the safety of the nuclear installation shall be evaluated. The potential for tsunamis or seiches from phenomena other than seismic sources (e.g. from submarine landslides) shall be evaluated, as appropriate for the region. |
| Requirement 20: Evaluation of flooding hazards |
5.19. |
The hazards associated with tsunamis or seiches shall be derived from historical records and any available information on prehistoric floods, as well as from physical and/or analytical modelling. Such hazards shall include potential draw-down and run-up that could result in physical effects on the site. |
| Requirement 20: Evaluation of flooding hazards |
5.20. |
The hazards associated with tsunamis or seiches shall be evaluated as appropriate for the region, using nearshore bathymetry and coastal topography, with account taken of any amplification due to the coastal configuration (including artificial structures). |
| Requirement 20: Evaluation of flooding hazards |
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Floods and waves caused by failure of water control structures |
| Requirement 20: Evaluation of flooding hazards |
5.21. |
Upstream water control structures such as dams shall be analysed to determine the potential hazard associated with the failure of one or more of the upstream structures, including in combination with flooding from other causes. |
| Requirement 20: Evaluation of flooding hazards |
5.22. |
If a preliminary examination of the nuclear installation indicates that it would not be able to safely withstand the effects of the failure of one or more of the upstream water control structures, then the hazards associated with the nuclear installation shall be evaluated with the inclusion of such effects. Alternatively, such upstream structures shall be analysed by methods equivalent to those used in determining the hazards associated with the nuclear installation to demonstrate that the upstream structures could survive the event concerned. |
| Requirement 20: Evaluation of flooding hazards |
5.23. |
Flooding and associated phenomena caused by an accumulation of water due to a blockage of rivers upstream or downstream (e.g. caused by landslides or ice), or due to a change in land use, shall be considered. |
| Requirement 21: Geotechnical characteristics and geological features of subsurface materials |
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The geotechnical characteristics and geological features of subsurface materials shall be investigated, and a soil and rock profile for the site that considers the variability and uncertainty in subsurface materials shall be derived. |
| Requirement 21: Geotechnical characteristics and geological features of subsurface materials |
5.24. |
The static and dynamic geotechnical characteristics and geological features of subsurface materials at the site, including any backfill, shall be established. Laboratory and field based methods shall be used, in conjunction with appropriate sampling techniques and sufficient repetition of each test, to characterize each parameter of the subsurface materials at the site. |
| Requirement 21: Geotechnical characteristics and geological features of subsurface materials |
5.25. |
The stability and bearing capacity of foundation materials shall be assessed, including consideration of the potential for excessive settlement under static and seismic loading. |
| Requirement 21: Geotechnical characteristics and geological features of subsurface materials |
5.26. |
The physical and the geochemical properties of the soil and groundwater shall be studied by appropriate methods and taken into account in the evaluation of the subsurface material at the site. |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
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Geotechnical hazards and geological hazards, including slope instability, collapse, subsidence or uplift, and soil liquefaction, and their effect on the safety of the nuclear installation, shall be evaluated. |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
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Slope instability |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
5.27. |
The site and the site vicinity shall be evaluated to determine the potential for slope instability (such as landslides, rock fall and snow avalanches), caused by natural or human induced phenomena, which could affect the safety of the nuclear installation. In the evaluation of slope instability, the configuration of the site during and after site preparation activities shall be addressed. The evaluation of slope stability shall also take into account extreme meteorological conditions and rare meteorological events. |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
5.28. |
The potential for slope instability resulting from seismic loading shall be evaluated using parameters appropriate for describing the seismic hazards and the soil and groundwater characteristics at the site. |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
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Collapse, subsidence or uplift of the site surface |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
5.29. |
The potential for collapse, subsidence or uplift of the surface that could affect the safety of the nuclear installation over its lifetime shall be evaluated using a detailed description of subsurface conditions obtained from reliable methods of investigation. |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
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Soil liquefaction |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
5.30. |
The potential for liquefaction and non-linear effects of the subsurface materials at the site shall be evaluated using parameters appropriate for describing the seismic hazards and geotechnical properties of the subsurface materials at the site. |
| Requirement 22: Evaluation of geotechnical hazards and geological hazards |
5.31. |
The evaluation of soil liquefaction shall include the use of accepted methods for field and laboratory testing in combination with analytical methods to assess the hazards. |
| Requirement 23: Evaluation of other natural hazards |
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Other natural phenomena that are specific to the region and which have the potential to affect the safety of the nuclear installation shall be investigated. |
| Requirement 23: Evaluation of other natural hazards |
5.32. |
Other natural external hazards, such as wild fires, drought, hail, frazil ice formation, diversion of a river, debris avalanche and biological hazards (e.g. jellyfish, small animals and barnacles) shall be identified and assessed so that the site specific design parameters for these hazards can be derived. |
| Requirement 24: Evaluation of hazards associated with human induced events |
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The hazards associated with human induced events on the site or in the region shall be evaluated. |
| Requirement 24: Evaluation of hazards associated with human induced events |
5.33. |
Human induced events to be addressed shall include, but shall not be limited to: Events associated with nearby land, river, sea or air transport (e.g. collisions and explosions);
Fire, explosions, missile generation and releases of hazardous gases from industrial facilities near the site;
Electromagnetic interference.
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| Requirement 24: Evaluation of hazards associated with human induced events |
5.34. |
Human activities that might influence the type or severity of natural hazards, such as resource extraction or other significant re-contouring of land or water or reservoir induced seismicity, shall be considered. |
| Requirement 24: Evaluation of hazards associated with human induced events |
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Aircraft crashes |
| Requirement 24: Evaluation of hazards associated with human induced events |
5.35. |
The potential for accidental aircraft crashes on the site shall be assessed with account taken, to the extent practicable, of potential changes in future air traffic and aircraft characteristics. |
| Requirement 24: Evaluation of hazards associated with human induced events |
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Chemical hazards |
| Requirement 24: Evaluation of hazards associated with human induced events |
5.36. |
Current or foreseeable activities in the region surrounding the site that involve the handling, processing, transport and/or storage of chemicals having a potential for explosions or for producing gas clouds capable of deflagration or detonation shall be addressed. |
| Requirement 24: Evaluation of hazards associated with human induced events |
5.37. |
Hazards associated with chemical explosions or other releases shall be expressed in terms of heat, overpressure and toxicity (if applicable), with account taken of the effect of distance and non-favourable combinations of atmospheric conditions at the site. In addition, the potential effects of such events on site workers shall be evaluated. |
| Requirement 25: Dispersion of radioactive material |
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The dispersion in air and water of radioactive material released from the nuclear installation in operational states and in accident conditions shall be assessed. |
| Requirement 25: Dispersion of radioactive material |
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Atmospheric dispersion of radioactive material |
| Requirement 25: Dispersion of radioactive material |
6.1. |
The analysis of the atmospheric dispersion of radioactive material shall take into account the orography, land cover and meteorological features of the region, including parameters such as wind speed and direction, air temperature, precipitation, humidity, atmospheric stability parameters, prolonged atmospheric inversions and any other parameters required for modelling of atmospheric dispersion. If possible, long term meteorological data for nearby locations shall be obtained, evaluated for quality and used. |
| Requirement 25: Dispersion of radioactive material |
6.2. |
A programme for meteorological measurements shall be prepared and carried out at or near the site using instrumentation capable of measuring and recording the main meteorological parameters at appropriate elevations, locations and sampling intervals. Data from at least one representative full year shall be collected and used in the analyses of atmospheric dispersion, together with any other relevant data available from other information sources. The meteorological data shall be expressed in terms of appropriate meteorological parameters. |
| Requirement 25: Dispersion of radioactive material |
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Dispersion of radioactive material through surface water and groundwater |
| Requirement 25: Dispersion of radioactive material |
6.3. |
A survey programme shall be designed to gather relevant data to characterize the hydrogeological and hydrological parameters at the site and in the region to permit the assessment of the potential movement of radionuclides through surface water and groundwater and the subsequent assessment of the radiological impact. This measurement programme shall be carried out for at least one full year prior to hydrogeological investigations (see para. 6.5). The data shall be expressed in terms of appropriate parameters for surface hydrology and groundwater. |
| Requirement 25: Dispersion of radioactive material |
6.4. |
A programme of surface water investigations (including the interactions between surface water and groundwater) for the region shall be developed. The description of surface water shall include the main physical and chemical characteristics of the water bodies, both natural and artificial, the major structures for water control, the locations of water intake structures and information on water use in the region. |
| Requirement 25: Dispersion of radioactive material |
6.5. |
A programme of hydrogeological investigations for the region shall be developed, including descriptions of the main characteristics of the water-bearing formations and their interaction with surface water, as well as data on the uses of groundwater in the region. |
| Requirement 25: Dispersion of radioactive material |
6.6. |
The programme of hydrogeological investigations for the region shall include investigations of the migration and retention characteristics of radionuclides in groundwater and investigations of the associated exposure pathways. |
| Requirement 25: Dispersion of radioactive material |
6.7. |
The hydrogeological and hydrological investigations shall determine, to the extent necessary, the dilution and dispersion characteristics of water bodies, the re-concentration ability of sediments and biota, the migration and retention characteristics of radionuclides, the transfer mechanisms for radionuclides in the hydrosphere, as well as the associated exposure pathways. |
| Requirement 26: Population distribution and public exposure |
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The existing and projected population distribution within the region over the lifetime of the nuclear installation shall be determined and the potential impact of radioactive releases on the public, in both operational states and accident conditions, shall be evaluated and periodically updated. |
| Requirement 26: Population distribution and public exposure |
6.8. |
Information on the existing and projected population distribution in the region, including resident populations and (to the extent possible) transient populations, shall be collected and kept up to date over the lifetime of the nuclear installation. Special attention shall be paid to vulnerable populations and residential institutions (e.g. schools, hospitals, nursing homes and prisons) when evaluating the potential impact of radioactive releases and considering the feasibility of implementing protective actions. |
| Requirement 26: Population distribution and public exposure |
6.9. |
The most recent census data for the region, or information obtained by extrapolation of the most recent data on resident populations and transient populations, shall be used in obtaining the population distribution. In the absence of reliable data, a special study shall be carried out. |
| Requirement 26: Population distribution and public exposure |
6.10. |
The data shall be analysed to obtain the population distribution in terms of the direction and distance from the site. This information shall be used to carry out an evaluation of the potential radiological impact of normal discharges and accidental releases of radioactive material, including reasonable consideration of releases due to severe accidents, with the use of site specific design parameters and models as appropriate. |
| Requirement 27: Uses of land and water in the region |
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The uses of land and water shall be characterized in order to assess the potential effects of the nuclear installation on the region. |
| Requirement 27: Uses of land and water in the region |
6.11. |
The characterization of the uses of land and water shall include investigations of the land and surface water and groundwater resources that might be used by the population or that serve as a habitat for organisms in the food chain. |
| Requirement 28: Monitoring of external hazards and site conditions |
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All natural and human induced external hazards and site conditions that are relevant to the licensing and safe operation of the nuclear installation shall be monitored over the lifetime of the nuclear installation. |
| Requirement 28: Monitoring of external hazards and site conditions |
7.1. |
The monitoring of external hazards and site conditions shall be commenced no later than the start of construction and shall be continued until decommissioning. The monitoring plan shall be developed as part of the objectives and scope of the site evaluation. |
| Requirement 28: Monitoring of external hazards and site conditions |
7.2. |
The monitoring plan shall include the parameters to be monitored, the type of data to be collected, the methodology for data collection (including the location and frequency of data collection), the necessary resolution and precision of any measurements, data backup requirements, as well as requirements for data processing and analysis. |
| Requirement 28: Monitoring of external hazards and site conditions |
7.3. |
Before commissioning of the nuclear installation begins, the levels of background radioactivity in the atmosphere, hydrosphere and lithosphere and in biota in the region shall be measured so as to make it possible to determine any additional radioactivity due to the operation of the nuclear installation. |
| Requirement 29: Review of external hazards and site conditions |
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All natural and human induced external hazards and site conditions shall be periodically reviewed by the operating organization as part of the periodic safety review and as appropriate throughout the lifetime of the nuclear installation, with due account taken of operating experience and new safety related information. |
| Requirement 29: Review of external hazards and site conditions |
7.4. |
As part of periodic safety review (or as part of safety assessments conducted under alternative arrangements), natural and human induced external hazards and site conditions shall be reviewed throughout the lifetime of the nuclear installation using updated information. Such reviews shall be undertaken at regular intervals (typically no less than once in ten years), and in the event of any of the following: |
| Requirement 29: Review of external hazards and site conditions |
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An update of the regulatory requirements;
Indications of inadequate design against external hazards;
New technical findings, such as the vulnerability of particular structures, systems and components to external hazards;
New information, experience and lessons from the occurrence of actual external events that affected the safety of another nuclear installation or an industrial facility;
Changes of hazards over time for which new information and assessments have become available;
A need to provide additional confidence that there are sufficient margins to prevent cliff edge effects;
As part of a programme for long term operation, or in support of an application for an extension to the operating licence for the nuclear installation;
The development of new methods to analyse hazards that substantially improve earlier estimates.
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| Requirement 29: Review of external hazards and site conditions |
7.5. |
The site specific external hazards and the site conditions shall be re-evaluated, as necessary, based on the outcome of the periodic review of site specific hazards or because of new data relevant to the radiological environmental impact assessment or to the safe operation of the nuclear installation.EUROPEAN ATOMIC ENERGY COMMUNITY, FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOUR ORGANIZATION, INTERNATIONAL MARITIME ORGANIZATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN HEALTH ORGANIZATION, UNITED NATIONS ENVIRONMENT PROGRAMME, WORLD HEALTH ORGANIZATION, Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, IAEA, Vienna (2006). INTERNATIONAL ATOMIC ENERGY AGENCY, External Human Induced Events in Site Evaluation for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.1, IAEA, Vienna (2002). INTERNATIONAL ATOMIC ENERGY AGENCY, Dispersion of Radioactive Material in Air and Water and Consideration of Population Distribution in Site Evaluation for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.2, IAEA, Vienna (2002). INTERNATIONAL ATOMIC ENERGY AGENCY, Geotechnical Aspects of Site Evaluation and Foundations for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.6, IAEA, Vienna (2004). INTERNATIONAL ATOMIC ENERGY AGENCY, Seismic Hazards in Site Evaluation for Nuclear Installations, IAEA Safety Standards Series No. SSG-9, IAEA, Vienna (2010). INTERNATIONAL ATOMIC ENERGY AGENCY, WORLD METEOROLOGICAL ORGANIZATION, Meteorological and Hydrological Hazards in Site Evaluation for Nuclear Installations, IAEA Safety Standards Series No. SSG-18, IAEA, Vienna (2011). INTERNATIONAL ATOMIC ENERGY AGENCY, Volcanic Hazards in Site Evaluation for Nuclear Installations, IAEA Safety Standards Series No. SSG-21, IAEA, Vienna (2012). INTERNATIONAL ATOMIC ENERGY AGENCY, Site Survey and Site Selection for Nuclear Installations, IAEA Safety Standards Series No. SSG-35, IAEA, Vienna (2015). 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, IAEA Safety Glossary: Terminology Used in Nuclear Safety and Radiation Protection, 2018 Edition, IAEA, Vienna (in preparation). INTERNATIONAL ATOMIC ENERGY AGENCY, Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5), IAEA Nuclear Security Series No. 13, IAEA, Vienna (2011). INTERNATIONAL ATOMIC ENERGY AGENCY, Leadership and Management for Safety, IAEA Safety Standards Series No. GSR Part 2, IAEA, Vienna (2016).
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