Переводы документов. Translations in English

NP-024-2000. Requirements for justification of the possibility to extend the design service life for nuclear facilities

NP-024-2000

FEDERAL INSPECTORATE OF RUSSIA

FOR NUCLEAR AND RADIATION SAFETY

 

FEDERAL RULES AND REGULATIONS

IN THE FIELD OF ATOMIC ENERGY USE

 

REQUIREMENTS FOR JUSTIFICATION OF THE POSSIBILITY

TO EXTEND THE DESIGN SERVICE LIFE

FOR NUCLEAR FACILITIES

 

NP-024-2000

 

 

These federal rules and regulations "Requirements for justification of the possibility to extend the design service life for nuclear facilities" establish the main criteria and requirements for safety in order to extend the service life of nuclear facilities in excess of the specified lifetime and to obtain the license of the Federal Inspectorate for Nuclear and Radiation Safety for operation within the additional service life.

This regulatory document shall be applicable to all operating nuclear facilities except for power units of nuclear power plants and nuclear facilities for military use.

Approaches to regulation of service life extension for power units of nuclear power plants are taken into account in its development.

The regulatory document is issued for the first time.

The regulatory document is developed by: P.P. Aleksashin, Yu.G. Vishnevsky, A.T. Gutsalov (Federal Inspectorate of Russia for Nuclear and Radiation Safety), I.V. Kaliberda, N.I. Karpunin, B.K. Maltsev, V.P. Stutsker, L.P. Soloviev, N.N. Shabanov (Scientific and Research Center for Nuclear and Radiation Safety).

Proposals of the National Research Center "Kurchatov Institute", JSC TVEL, FSUE "Siberian Chemical Works", JSC "Murmansk Shipping Corporation" and other organizations are taken into account in this regulatory document subsequent to their discussion and development of consensus resolutions.

 

Terms and definitions

 

1. Safety (nuclear and radiation) of the nuclear facility (hereinafter - the NF safety) - the property of the nuclear facility under normal operation conditions and in case of abnormal operation including accidents to restrict radiation impact and any other accompanying impacts on the workers (personnel), the public and the environment to the established limits and also to prevent occurrence of self-sustained chain nuclear fission reaction in the course of nuclear material handling.

2. Safety deficiency - lack of any safety function at the nuclear facility within the scope determined by the requirements of the effective rules and regulations in the area of atomic energy use.

3. Additional service life - calendar duration (period) of the nuclear facility operation in excess of the specified lifetime according to its intended purpose (exceeding the 30-year operation period).

4. Compensatory measures - technical and administrative measures for partial or complete elimination of safety deficiencies and (or) limitation of their safety impact.

5. Non-repairable component - any component for which recovery of operable state in the situation under consideration is impossible and not provided in the regulatory and technical and (or) design and engineering documentation.

6. Nuclear facility - a nuclear installation, a radiation source, a storage facility for nuclear materials and radioactive substances, a storage facility for radioactive waste.

7. Residual lifetime of the component - the accumulated operational time of the component from the moment of its technical condition control till transition to the limit state.

8. Service life extension - activities aimed to prepare the nuclear facility for operation within the additional period.

9. System - the set of components designed for performance of the specified functions.

10. Technical condition - the set of the component (system, the entire nuclear facility) properties subject to changes in the course of production or operation and characterized at a given instant by the parameters established in the technical documentation and (or) subsequent to the results of the component reliability (lifetime) management.

11. Components - equipment, instruments, pipelines, cables, building structures and others items ensuring performance of the prescribed functions independently or within the systems and considered in the technical design of the nuclear facility as structural units for reliability and safety analysis.

 

1. Purpose. Scope of application

 

1.1. This document "Requirements for justification of the possibility to extend the design service life for nuclear facilities" is developed with due regard for federal laws "On atomic energy use", "On radiation safety of the public", "On environmental impact assessment" and "On safety of hazardous industrial facilities".

1.2. This document establishes the basic criteria and requirements for safety in order to extend the nuclear facility service life in excess of the design lifetime".

1.3. This document shall be applicable to all operating nuclear facilities except for power units of nuclear power plants and nuclear facilities for military use.

 

2. General

 

2.1. Upon achievement of the specified (or 30-year) service life of the nuclear facility the operating organization shall assess the possibility to continue operation of the nuclear facility.

2.2. Duration of the nuclear facility operation in excess of the design (or 30-year) service life shall be determined with due regard for the particular nuclear facility peculiarities and also technical and economic factors including:

- the possibility to provide and maintain the required safety level in the course of the nuclear facility operation in excess of the design (or 30-year) service life;

- availability of the required lifetime of  irreplaceable equipment;

- the possibility to ensure safety in management of radioactive waste generated within the additional service life of the nuclear installation;

- the possibility to ensure the required safety level for the nuclear facility in the course of its decommissioning upon expiry of the additional service life;

- the possibility to store additional amounts of spent nuclear fuel at the nuclear installation site or to remove it.

2.3. In order to extend the service life of the nuclear facility in excess of the design (or 30-year) lifetime the operating organization shall:

- carry out comprehensive examination of the nuclear facility;

- assess the possibility to extend the nuclear facility service life;

- develop the program of the nuclear facility preparation for the service life extension;

- perform the works aimed to prepare the nuclear facility for operation within the additional service life including substantiation of safety and residual lifetime of the components, replacement of equipment with expired lifetime and the nuclear facility retrofitting and (or) refurbishment in case of necessity;

- carry out testing of the nuclear facility systems (components) necessary to confirm their compliance with the design requirements.

2.4. The comprehensive examination shall be performed in accordance with the program developed by the operating organization and approved by the federal executive authority for control of atomic energy use.

2.5. The program of works for the nuclear facility preparation for service life extension shall provide for:

- performance of additional investigations in order to determine residual lifetime of the nuclear facility components including equipment, buildings and structures and also definition and implementation of the required measures to extend operational life of these components;

- development of technical and administrative measures for partial or complete elimination of safety deficiencies and (or) limitation of their safety impact;

- development of the nuclear facility retrofitting and (or) refurbishment project and its implementation in case of necessity;

- development of the quality assurance program for the works aimed to prepare the nuclear facility for the service life extension;

- testing of the nuclear facility systems and components necessary to confirm their compliance with the design requirements;

- updating of the effective safety analysis documents in accordance with the actual state of the nuclear facility or development of new safety analysis documents for the nuclear facility operation within the additional period.

2.6. The program of works for the nuclear facility preparation for service life extension developed by the operating organization shall be approved by the federal executive authority for control of atomic energy use.

2.7. The nuclear facility safety analysis used as the basis to develop the resolution on the possibility to extend its service life in excess of the design (or 30-year) lifetime shall be performed based on the criteria and requirements of federal rules and regulations in the area of atomic energy use effective as per the assessment moment as well as the criteria established in this document.

2.8. Methods used to assess safety of the nuclear facility shall be conservative in order to compensate for uncertainty of the input information and the applied software tools shall be validated.

2.9. Sufficiency of the technical and administrative measures aimed to bring the nuclear facility in compliance with the criteria and requirements of the effective regulatory documents in the area of atomic energy use shall be substantiated by the operating organization based on the results of the comprehensive nuclear facility examination and safety analysis.

2.10. Elimination or compensation of safety deficiencies requiring modifications of the nuclear facility design with regard to implementation of new design and engineering solutions shall be arranged on the basis of the design documentation developed and approved in accordance with the established procedure.

2.11. The decision of the operating organization on extension of the nuclear facility service life shall be approved by the federal executive authority for control of atomic energy use.

2.12. In case the operating organization reveals any factors in the course of the nuclear facility safety analysis that prevent from safe operation within the additional service life and elimination of these factors is not economically feasible the works shall be arranged to prepare the nuclear facility for decommissioning.

 

3. Basic requirements for comprehensive examination of the nuclear facility

 

3.1. The aim of the comprehensive examination is to assess the actual state of the nuclear facility, to determine residual lifetime for its components and also to reveal any safety deficiencies in order to evaluate the possibility for further operation of the nuclear facility in excess of the design (or 30-year) lifetime and to develop the program of works aimed to prepare the nuclear facility for service life extension.

3.2. In case of necessity the operating organization shall engage specialized organizations for performance of the comprehensive nuclear facility examination including:

- organizations that have developed the design of the nuclear facility under examination, its individual systems and components;

- manufacturing organizations specialized in development and production of the systems and components under examination (or having developed and manufactured these systems and components);

- specialized material research organizations;

- any other organizations performing works and rendering services in the area of atomic energy use.

All organizations engaged in the comprehensive examination shall have licenses of the Federal Inspectorate of Russia for Nuclear and Radiation Safety for performance of the relevant activities.

3.3. The following shall be defined during comprehensive examination of the nuclear facility:

- safety deficiencies;

- fire safety of the nuclear facility;

- radiation situation in the rooms of the nuclear facility, at the site and in the sanitary-protective area (if any);

- any changes in human-induced impact of other facilities on the nuclear facility and natural impacts in the location area of the nuclear facility;

- industrial safety state:

- technical condition of safety-related systems and components;

- safety-related components with expired lifetime;

- safety-related components with the possibility to extend their operational life due to periodic maintenance and repair, or these components shall be replaced;

- safety-related components with the residual lifetime and the possibility to extend their service life for a certain period;

- the possibility for storage of spent nuclear fuel and radioactive waste generated within the additional service life;

- the possibility for safe handling of radioactive waste.

3.4. The general program for comprehensive examination of the nuclear facility and individual examination programs for the nuclear facility systems and (or) components shall be developed in order to carry out the comprehensive examination.

3.4.1. The general program for comprehensive examination of the nuclear facility shall define safety-related systems and components subject to examination, the stages of the comprehensive examination, methods and forms of examination, the list of preparatory works, the means for their performance and also the contents of individual examination programs for these systems and components.

3.4.2. Individual examination programs for the nuclear facility systems and (or) components shall be approved by the operating organization and agreed with the specialized organizations.

3.4.3. Residual lifetime of safety-related nuclear facility components shall be determined with due regard for changes in the process parameters within the entire service life of the nuclear facility and their actual state as per the moment of examination.

3.4.4. Residual lifetime of safety-related nuclear facility components shall be substantiated through the use of the developed procedures approved by the operating organization and agreed with the Federal Inspectorate of Russia for Nuclear and Radiation Safety in accordance with the established procedure.

3.4.5. Determination and substantiation of residual lifetime for safety-related nuclear facility components shall be confirmed with the results of expert review performed by organizations having licenses of the Federal Inspectorate of Russia for Nuclear and Radiation Safety for performance of these activities.

3.4.6. The organization having the license of the Federal Inspectorate of Russia for Nuclear and Radiation Safety and carrying out expert review of the documents substantiating residual lifetime for any safety-related nuclear facility component or group of components shall develop the statement with indication of the residual lifetime value for the component or group of components and recommendations for their reliability (lifetime) management within the additional nuclear facility operation period.

3.4.7. Results of the comprehensive examination of the nuclear facility systems and components shall be specified in the report containing:

- brief description of the examined systems and components and their purpose;

- the list of reviewed documents;

- the scope and results of control, testing, measurements, investigations, etc. carried out in the course of examination;

- conclusions on the results of residual lifetime assessment;

- the list of components with expired lifetime;

- conclusions on the actual state of systems and components based on the results of control, testing, measurements, investigations, etc. carried out in the course of examination;

- the opinion on the state of systems and components as well as recommendations for implementation of measures necessary to ensure their operability and reliability;

- revealed safety deficiencies and the proposed compensatory measures;

- proposals for the programs of additional works aimed to determine residual lifetime of the nuclear facility components.

 

4. Criteria for the possibility to extend the nuclear facility service life

in excess of the design lifetime

 

4.1. The nuclear facility operation in excess of the design lifetime shall be possible provided that technical and administrative measures necessary to bring the nuclear facility into compliance with the criteria and requirements of the effective rules and regulations in the area of atomic energy use are implemented.

4.2. Technical condition of the nuclear facility within the additional service life shall be continuously maintained and shall comply with the requirements of effective regulatory documents in the area of nuclear, radiation, technical, fire and environmental safety.

4.3. Residual lifetime of non-repairable safety-related nuclear facility components shall be substantiated and sufficient within the additional service life and also in the course of the nuclear facility decommissioning (after expiry of the additional service life) in case the nuclear facility components are to be used within this period.

4.4. Reliability (lifetime) management shall be arranged for safety-related equipment, buildings and structures of the nuclear facility; for this purpose the lifetime management program for these components shall be developed and implemented.

4.5. Efficiency of the methods and means for control of technical condition of safety-related nuclear facility equipment, buildings and structures shall be sufficient to assess their actual state and also to identify and prevent any design basis initiating events.

4.6. Within the additional service life of the nuclear facility its radiation impact on the workers (personnel), the public and the environment under normal operation conditions and in case of abnormal operation including design basis accidents shall not exceed the established radiation exposure doses for the workers (personnel) and the public, the norms of releases (discharges) and content of radioactive substances in the environment.

4.7. The nuclear facilities shall be resistant to external impacts with due regard for any impacts registered within the previous period of their operation and the expected changes of natural and human-induced factors in the location areas of the nuclear facilities.

Arrangements aimed to ensure seismic resistance in accordance with the requirements of effective regulatory documents in the area of atomic energy use shall be developed and implemented for any nuclear facilities designed without regard to seismic impacts.

 

5. Requirements for the nuclear facility preparation

for additional service life

 

5.1. The operating organization shall implement the program of the nuclear facility preparation for additional service life to the full extent including:

- implementation of arrangements aimed to eliminate or compensate for safety deficiencies;

- determination of residual lifetime for safety-related components in case it could not have been determined in the course of the comprehensive examination;

- implementation of arrangements for replacement of the equipment and other components with expired lifetime;

- performance of adjustment works and testing;

- updating of the operation documentation;

- retraining of the workers (personnel).

5.2. In case any retrofitting and (or) refurbishment of the nuclear facility systems and (or) components is required in order to extend its service life these works shall be performed in accordance with the retrofitting and (or) refurbishment project.

5.2.1. Performance of any retrofitting and (or) refurbishment works shall not result in damage and (or) loss of operability or reliability and safety reduction for any operated nuclear facility systems and (or) components.

5.3. The scope of control with regard to the current state of safety-related nuclear facility systems and components within the additional service life shall be substantiated and ensured, and the procedure for monitoring of their technical condition shall be defined and duly approved.

5.4. The design and engineering works shall be performed in compliance with the quality assurance program developed and approved  according to the established procedure.

5.5. The operating organization shall perform safety analysis for the nuclear facility in accordance with the effective rules and regulations in the area of atomic energy use with due regard for its actual state upon completion of the works aimed to prepare the nuclear facility for additional service life and present it in the safety analysis report or any substitution document.

5.6. The operating organization shall perform tests in order to confirm functioning of all nuclear facility systems and components in accordance with the criteria and technical characteristics of the nuclear facility established in the design.

5.7. Tests shall be performed in compliance with the programs developed and approved by the operating organization in accordance with the established procedure.

5.8. The list and contents of the safety analysis documents for the nuclear facility shall be defined by the Federal Inspectorate of Russia for Nuclear and Radiation Safety.

5.9. The operating organization shall update the effective process regulations of the nuclear facility, the operation manuals for systems and components, manuals and guidelines defining the actions of the workers (personnel) for safety assurance in case of any design basis and beyond design basis accidents in accordance with the changes in the nuclear facility design.

5.10. Subsequent to completion of the works aimed to prepare the nuclear facility for operation within the additional period, tests and trials the operating organization shall issue and approve the acceptance certificate.

 

 

 

 


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