Переводы документов. Translations in English

NP-007-17. Safety rules for decommissioning of uranium-graphite production reactors

 

Approved by
Order of the Federal
Environmental, Industrial and
Nuclear Supervision Service
dated September, 8, 2017 No. 357

 

FEDERAL RULES AND REGULATIONS
IN THE AREA OF ATOMIC ENERGY USE "SAFETY
RULES FOR DECOMMISSIONING OF
URANIUM-GRAPHITE PRODUCTION REACTORS"

(NP-007-17)

 

I. Purpose and scope of application

 

1. These Federal rules and regulations in the area of atomic energy use "Safety rules for decommissioning of uranium-graphite production reactors" (NP-007-17) (hereinafter - the Rules) are developed in accordance with Article 6 of Federal Law dated November, 21, 1995 No. 170-FZ "On atomic energy use", Decree of the Government of the Russian Federation dated December, 1, 1997 N 1511 "On approval of Regulations on development and approval of federal rules and regulations in the area of atomic energy use" (Collected Acts of the Russian Federation, 1997, No. 49, art. 5600; 2012, No. 51, art. 7203).

2. These Rules establish the requirements for safety assurance in decommissioning of uranium-graphite production reactors implemented in the course of operation and decommissioning of uranium-graphite production reactors as well as for the safety analysis reports with regard to decommissioning of uranium-graphite production reactors.

3. Planning of the uranium-graphite production reactor decommissioning at the lifecycle stages preceding its operation shall be arranged in accordance with the federal rules and regulations in the area of atomic energy use "Safety assurance in decommissioning of nuclear facilities. General provisions" (NP-091-14) approved by Order of the Federal Environmental, Industrial and Nuclear Supervision Service dated May, 20, 2014 No. 216 (registered by the Russian Ministry of Justice on July, 14, 2014, registration No. 33086, Bulletin of Federal Agency Regulations 2014, No. 37) (hereinafter - NP-091-14).

4. The list of abbreviations is given in Appendix 1 to these Rules, terms and definitions are given in Appendix 2.

 

II. General provisions

 

5. The basic safety assurance principles and general requirements established in NP-091-14 shall be observed in the course of the UGPR decommissioning.

6. The operating organization shall arrange the organizational units required for safe decommissioning of the UGPR, provide for selection and training of the workers (personnel), physical protection and control of all activities important for safety assurance in the course of the UGPR decommissioning.

7. The operating organization shall ensure development and implementation of the technical and administrative solutions for safety assurance in the course of the UGPR decommissioning contained in the UGPR decommissioning concept, program and design documentation.

8. Technical and administrative solutions for safety assurance in the course of the UGPR decommissioning shall be developed in accordance with the basic radiation safety principles.

9. Selection of the technical and administrative solutions adopted for safety assurance in the course of the UGPR decommissioning shall be based on experience in decommissioning of similar UGPRs and (or) confirmed by testing, experiments and (or) bench-scale research.

10. The UGPR decommissioning works shall be performed only subject to availability of the relevant safety analysis developed by the operating organization.

Safety assurance for new nuclear facilities arranged at the decommissioned UGPR site (special RW preservation stations and RW disposal facilities) shall be organized in accordance with the requirements of federal rules and regulations in the area of atomic energy use governing safety for the relevant categories of nuclear facilities.

 

III. Quality assurance in decommissioning of
uranium-graphite production reactors

 

11. The required quality of works shall be ensured in the course of the UGPR decommissioning.

12. For the purpose of quality assurance in the course of the UGPR decommissioning the quality assurance program of the organization developing the design documentation for the UGPR decommissioning shall provide for control of the UGPR decommissioning design documentation compliance with the requirements of the federal rules and regulations in the area of atomic energy use, the terms of reference for the design and the regulatory documents.

13. The operating organization shall ensure quality control for the activities of any organizations performing the works and (or) rendering the services to the operating organization with regard to the UGPR preparation for decommissioning and decommissioning.

14. Prior to commencement of the UGPR decommissioning works the operating organization shall develop the individual quality assurance program for the UGPR decommissioning.

15. The individual quality assurance program for the UGPR decommissioning shall establish the quality control procedures for the UGPR decommissioning works including control of compliance with the solutions adopted in the UGPR decommissioning design documentation.

16. Technical documentation applied in the course of the UGPR decommissioning shall be developed in accordance with the requirements of the individual quality assurance program for the UGPR decommissioning.

 

IV. Requirements for safety assurance in
decommissioning of uranium-graphite production reactors
 implemented during operation of
uranium-graphite production reactors

 

17. The operating organization shall develop the UGPR decommissioning concept (hereinafter - the Concept) and present it in the UGPR SAR.

This Concept shall contain:

description of the potential UGPR decommissioning options with indication of the expected end states after the UGPR decommissioning;

the UGPR decommissioning option selected by the operating organization, criteria and substantiation of its selection.

The main UGPR decommissioning options are "Abandonment of the uranium-graphite production reactor" and "Disposal of the uranium-graphite production reactor".

The following shall be taken into account in selection of the UGPR decommissioning option:

impact of the UGPR decommissioning works on safety of the existing nuclear facilities in the UGPR location area;

expected radiation exposure for the workers (personnel), the public and the environment in the course of the UGPR decommissioning works;

characteristics of the UGPR location site including hydro-meteorological, geological, hydrogeological and geotechnical conditions of the UGPR location;

technical and economic parameters of the UGPR decommissioning options.

18. The following information shall be provided in the Concept for the selected UGPR decommissioning option:

basic safety assurance principles in the course of the UGPR decommissioning;

the list, brief description and sequence of the arrangements for the UGPR preparation for decommissioning and decommissioning;

assessment of the total quantity (weight, volume and activity), type and class of radioactive wastes generated in the course of the UGPR decommissioning;

basic solutions for location of the removed radioactive wastes generated in the course of the UGPR decommissioning;

conditions for the Concept review in order to maintain relevance of the Concept.

19. In the course of the UGPR operation the operating organization shall:

ensure operability or limited operability of the buildings and facilities required for the UGPR decommissioning;

ensure operability of the systems and components required to perform the UGPR decommissioning works;

define the list of the design, operation and process documentation required to develop the UGPR decommissioning program.

20. In the course of the UGPR operation the operating organization shall arrange collection, documenting and storage of the information required for development of the UGPR decommissioning program and the UGPR decommissioning design documentation in the database including the following information:

design, operation and process documentation of the UGPR and any changes introduced into this documentation;

results of any technical condition examinations for the UGPR buildings, structures, systems and components including the information on technical conditions of the UGPR load-bearing civil structures and the UGPR graphite stack;

parameters characterizing the radiation situation in the rooms and at the UGPR site;

radionuclide contamination levels for the UGPR systems, components and civil structures, the amount (activity, weight) of nuclear materials particularly in radioactive wastes and the UGPR graphite stack;

any operational occurrences at the UGPR resulting in radionuclide contamination of the UGPR systems, components and site;

amount (weight, volume, activity) and radionuclide composition of radioactive wastes, their class, storage areas and conditions at the UGPR site, capacities and free spaces in the RW storage facilities and repositories at the UGPR site.

 

V. Requirements for safety assurance in
decommissioning of uranium-graphite production reactors
implemented during preparation of
uranium-graphite production reactors for decommissioning

 

21. The operating organization shall develop the UGPR decommissioning program based on the Concept as well as analysis of the UGPR design documentation and operation experience.

22. The UGPR decommissioning program shall contain:

description of the selected UGPR decommissioning option;

sequence and time limits for implementation of the administrative and technical arrangements and performance of the works for the UGPR preparation for decommissioning;

schedule of the UGPR CERE, information on the UGPR CERE scope, methods and equipment;

description of the UGPR state subsequent to completion of the works for the UGPR preparation for decommissioning;

sequence and time limits for the UGPR decommissioning works;

description of the end state after the UGPR decommissioning.

23. Works for the UGPR preparation for decommissioning shall be performed only subject to availability of the relevant safety analysis.

24. The operating organization shall develop administrative and technical solutions for safety assurance in the course of the works for the UGPR preparation for decommissioning with due regard for any consequences of the UGPR operational occurrences.

25. Subsequent to the UGPR shutdown for decommissioning all nuclear materials shall be removed from the site, and the UGPR shall be brought into the nuclear-safe state.

26. Bringing of the UGPR into the nuclear-safe state shall be confirmed by the nuclear safety statement for the UGPR shut down for decommissioning. Nuclear safety conditions for particular UGPR systems, components and equipment containing nuclear materials shall be specified in the nuclear safety statement. Nuclear safety conditions shall be substantiated in the UGPR SAR.

Experimental research required to determine the NM confinement zones and to obtain quantitative data on the NM mass, composition and state shall be carried out in order to confirm the UGPR bringing into the nuclear-safe state. In case of impossibility to carry out experimental research the UGPR bringing into the nuclear-safe state shall be substantiated through the use of the calculation and analytical method based on the conservative approach.

27. All requirements for qualification of the workers (personnel) and documentation shall remain the same as for the operating UGPR until the UGPR is brought into the nuclear-safe state. Frequency and scope of the maintenance works for the UGPR systems and components and the required number of the workers (personnel) shall be substantiated in the UGPR SAR.

28. In the course of the UGPR preparation for decommissioning the operating organization shall ensure timely:

removal of radioactive media from the UGPR  equipment, systems and rooms;

decontamination of the UGPR equipment, systems, rooms and civil structures.

29. In the course of the UGPR preparation for decommissioning the operating organization shall arrange the UGPR CERE. Any data obtained in the course of CERE shall be documented and stored.

30. The CERE results shall be presented in the CERE report which shall contain the following:

the list of the examined UGPR buildings, structures, systems and components;

information on the measuring methodologies, methods and hardware used in the course of examination;

technical condition of the UGPR buildings, structures, systems and components;

data required to assess the remaining life, operability and reliability of the UGPR systems and components necessary for the UGPR decommissioning;

characteristics of the radiation situation in the rooms and at the UGPR site;

information on amount and characteristics of radioactive substances contained in the UGPR systems and components, their chemical composition, physical state, specific (volumetric) and total activity;

radionuclide composition, physical and chemical state, activity, confinement zones of the nuclear materials;

adjusted information on the locations, amount (volume, weight, activity) and radionuclide composition of radioactive wastes at the UGPR site.

31. The operating organization shall ensure updating of the UGPR decommissioning program with due regard for the CERE results.

 

VI. Requirements for safety assurance in
decommissioning of uranium-graphite production reactors
implemented during development of the
uranium-graphite production reactor decommissioning project

 

32. The UGPR decommissioning design documentation shall be developed for the selected UGPR decommissioning option based on the UGPR decommissioning program with due regard for the CERE results.

33. The following shall be defined in the UGPR decommissioning design documentation:

boundaries of the decommissioned UGPR site;

sequence and scope of the UGPR decommissioning stages;

characteristics of the end state after the UGPR decommissioning including the list of new nuclear facilities arranged at the decommissioned UGPR site;

criteria for achievement of the prescribed end state after the UGPR decommissioning and requirements for the methods of its confirmation.

34. The following shall be specified in the UGPR decommissioning design documentation for the UGPR decommissioning stages:

safe decommissioning conditions established with due regard for peculiarities of the works at this UGPR decommissioning stage;

sequence and scope of the works for dismantling of physical barriers;

sequence and scope of the works for implementation of the administrative and technical solutions aimed to ensure safety in the course of the UGPR decommissioning, particularly for arrangement of additional physical barriers and strengthening (efficiency enhancement) of the existing ones;

types, objects, procedure and frequency of radiological control in the course of the UGPR decommissioning, the controlled parameters, their permissible values and requirements for the radiological control hardware;

assessment of quantity (volume, weight and activity) and radionuclide composition of radioactive wastes, classes of removed radioactive wastes;

assessment of quantity (volume, weight and activity) of the materials for restricted use;

technical solutions and administrative arrangements for intermediate storage of any radioactive wastes generated in the course of decommissioning;

solutions for minimization of the removed RW quantity (weight, volume) generated in the course of the UGPR decommissioning, RW conditioning and storage, minimization of radioactive substance releases into the environment;

assessment of individual and collective exposure doses for the workers (personnel) in the course of each type of works for the UGPR decommissioning;

assessment of individual and collective exposure doses for the workers (personnel) and the persons from the critical population groups in case of accidents;

quantitative assessment of RSb releases and discharges into the environment in the course of the works at this stage;

the list of radiation-hazardous works with indication of the personnel size necessary to perform these works and the requirements for qualification of the workers (personnel);

criteria (characteristics) of the decommissioning stage completion.

35. The UGPR decommissioning design documentation shall provide for the engineering features and administrative arrangements required for:

minimization of radiation exposure for the workers (personnel) in the course of the UGPR decommissioning;

dismantling of the UGPR buildings, structures, systems and components contaminated with radionuclides, particularly for fragementation of large-scale equipment;

decontamination of the UGPR equipment, systems, rooms and civil structures;

preservation of the UGPR systems and components with indication of the zone boundaries and the preservation periods;

classification of wastes generated in the course of dismantling and decontamination of the UGPR equipment, systems and civil structures as radioactive ones;

safe handling of the removed radioactive wastes in the course of their collection, segregation, processing, conditioning, storage, transportation and storage of special radioactive wastes;

radiological control arrangement;

accounting and control of radioactive substances and radioactive wastes;

non-exceedance of the established permissible limits of RSb releases and discharges;

handling of graphite stack, particularly in presence of any RW containing nuclear materials in the stack;

safe handling of the materials intended for restricted use;

fire and explosion safety assurance in the course of the UGPR decommissioning;

elimination of radioactive contamination at the UGPR site;

protection against external impacts;

physicalprotection assurance.

36. Technical and administrative solutions for radiological control provided in the UGPR decommissioning design documentation shall ensure detection of any exceedance of the reference and permissible levels for the controlled radiation safety parameters.

37. The operating organization shall ensure development of the UGPR decommissioning SAR based on the UGPR decommissioning program and the UGPR decommissioning design documentation.

38. Technical and administrative solutions for safety assurance in the course of the UGPR decommissioning provided in the UGPR decommissioning design documentation shall be presented and substantiated in the UGPR decommissioning SAR. Requirements for the structure and contents of the UGPR decommissioning SAR are given in Appendix 3 to these Rules.

39. Prior to commencement of the UGPR decommissioning works the operating organization shall develop the emergency response plan in case of any potential accidents in the course of the UGPR decommissioning. The action plan for protection of the personnel in case of accidents shall be updated with due regard for analysis of any potential accidents in the course of the UGPR decommissioning.

 

VII. Requirements for safety assurance in
decommissioning of uranium-graphite production reactors
implemented during decommissioning of
uranium-graphite production reactors

 

40. Any activities for the UGPR decommissioning shall be carried out in accordance with the UGPR decommissioning program and the UGPR decommissioning design documentation. Any changes to the decommissioning work sequence, procedure and technology provided in the design documentation shall be introduced only subject to availability of the relevant safety analysis.

41. Technical condition monitoring, maintenance and repair of the UGPR buildings, structures, systems and components required for safe decommissioning of the UGPR shall be carried out in the course of the UGPR decommissioning.

42. The radiological control scope, methods and means at all UGPR decommissioning stages shall comply with the federal rules and regulations in the area of atomic energy use establishing the requirements for safety assurance in the course of RW handling and sanitary standards and rules in the area of radiation safety assurance and shall ensure inter alia:

individualdosimetric monitoring for the workers (personnel) performing the UGPR decommissioning works;

integrity and operability monitoring for the physical barriers;

radiological process control including control of RW radiation characteristics, monitoring of amounts and radionuclide composition of any RSb releases and discharges into the environment;

monitoring of the radiation situation in the rooms and at the UGPR site.

43. The operating organization shall ensure development of the administrative and technical documentation for the UGPR decommissioning required to implement the UGPR decommissioning program and design documentation, including:

the decommissioning regulations, the  regulations (guidelines) for work performance, repair and maintenance of the UGPR systems, equipment, buildings and structures in the course of decommissioning works;

operation manuals for the equipment and systems of the decommissioned UGPR.

44. The administrative and technical documentation for the UGPR decommissioning shall establish the procedure, rules and techniques for safe performance of the decommissioning works.

45. The UGPR decommissioning works shall be carried out in accordance with the developed administrative and technical documentation for the UGPR decommissioning.

46. Any incidents in the course of the UGPR decommissioning including accidents shall be investigated in accordance with the requirements of the federal rules and regulations in the area of atomic energy use "Provision on the procedure for investigation and registration of any operational occurrences at the nuclear fuel cycle facilities" (NP-047-11) approved by Order of the Federal Environmental, Industrial and Nuclear Supervision Service dated December, 23, 2011 No. 736 (registered by Ministry of Justice of the Russian Federation on January, 19, 2012, registration number No. 22965; Bulletin of Federal Agency Regulations, 2012, No.15) with amendments introduced by Order of Federal Environmental, Industrial and Nuclear Supervision Service dated July, 15, 2013 No. 310 (registered by Ministry of Justice of the Russian Federation on August, 14, 2013; registration number No. 29388; Russian Newspaper, 2013, No.187). The operating organization shall ensure submittal of the information on any operational occurrences in the course of the UGPR decommissioning to the state regulatory authority for safety in atomic energy use as well as development and implementation of the measures intended to prevent repeated operational occurrences.

47. Prior to commencement of each UGPR decommissioning stage the operating organization shall:

update the emergency response plan (guidelines) for the decommissioned UGPR with due regard for the accidents possible at this UGPR decommissioning stage;

ensure development (updating) of the administrative and technical documentation required to perform the works at the UGPR decommissioning stage;

ensure the required number of the workers (personnel) and their training for safe performance of the works at the UGPR decommissioning stage;

establish the reference levels for radioactive contamination of the surfaces and air in the UGPR rooms, dose rates in the UGPR decommissioning work areas, releases and discharges of radioactive substances into the environment in the course of the UGPR decommissioning.

48. The operating organization shall ensure safety of all RSb and RW handling works, physical protection, accounting and control of radioactive substances and radioactive wastes generated in the course of the UGPR decommissioning at all stages of the UGPR decommissioning.

49. In case any nuclear materials, radioactive substances and radioactive wastes are detected in the course of the UGPR decommissioning works the operating organization shall ensure:

determination of the basic characteristics (physical state, density, radionuclide composition, activity) and amount (volume, weight) of the detected nuclear materials, radioactive substances and radioactive wastes;

accounting and control of the detected nuclear materials, radioactive substances and radioactive wastes, physical protection in accordance with the requirements of the federal rules and regulations in the area of atomic energy use.

50. Any works for handling of unaccounted nuclear materials, radioactive substances and radioactive wastes shall be performed subsequent to safety analysis for these works. NM handling works shall be carried out in accordance with special-purpose programs approved by the operating organization and defining safe conditions for performance of these works, particularly:

nuclear safety conditions in the course of works;

NM collection methods and means;

NM storage places and conditions prior to their removal from the UGPR site;

measures for accounting, control and physical protection of nuclear materials;

NM transportation conditions and means.

51. Subsequent to completion of the UGPR decommissioning stage the operating organization shall assess compliance of the work results with the decommissioning stage completion criteria (characteristics) established in the design documentation.

52. Subsequent to completion of each UGPR decommissioning stage the operating organization shall ensure inclusion of the following information into the UGPR decommissioning database:

performed works for dismantling and decontamination of the UGPR buildings, structures, systems and equipment, elimination of radionuclide contamination of the UGPR site;

the applied dismantling and decontamination techniques and methods;

performed works for arrangement of additional physical barriers;

individual exposure doses for the workers (personnel) at the completed decommissioning stage;

RW generation sources and places;

qualitative and quantitative composition of radioactive wastes in accordance with the classification established by the regulations in the area of atomic energy use;

the applied processing and conditioning methods for the removed radioactive wastes;

types of containers and (or) primary packages used for the removed RW handling;

performed RW handling works (if any).

 

VIII. Completion of the works for decommissioning of
uranium-graphite production reactors

 

53. The UGPR decommissioning works shall be completed subsequent to confirmation of the end state achievement after the UGPR decommissioning prescribed in the UGPR decommissioning design documentation. The operating organization shall arrange the final examination of the UGPR in order to confirm achievement of the prescribed end state.

54. Radiation and engineering examination upon completion of the UGPR decommissioning works shall be performed in accordance with the UGPR decommissioning design documentation.

55. Results of the final UGPR examination shall be documented and shall contain the following:

values of the characteristics defined in the decommissioning design documentation obtained in the course of examination and results of their comparison with the criteria for the end state achievement after the UGPR decommissioning;

values of the radiation situation characteristics obtained in the course of examination;

conclusion on compliance (non-compliance) of the actual decommissioned UGPR state with the end state after the UGPR decommissioning prescribed in the decommissioning design documentation.

56. Subsequent to completion of the UGPR decommissioning works the operating organization shall ensure integrity of the decommissioning information including:

the Concept;

the UGPR decommissioning program;

the UGPR CERE report;

the UGPR decommissioning design documentation;

the UGPR decommissioning SAR;

results of the final examination.

 

 

 

 

 

Appendix 1 to
Federal rules and regulations
in the area of atomic energy
use "Safety rules for
decommissioning of
uranium-graphite production reactors"
approved by
Order of the Federal
Environmental,
Industrial and Nuclear Supervision Service
dated September, 8, 2017 No. 357

 

ABBREVIATIONS

 

LRW

-

Liquid Radioactive Wastes

CERE

-

Comprehensive Engineering and Radiation Examination

SAR

-

Safety Analysis Report

UGPR

-

Uranium-Graphite Production Reactor

RW

-

Radioactive Wastes

RSb

-

Radioactive Substances

SRW

-

Solid Radioactive Wastes

NM

-

Nuclear Materials

 

 

 

 

 

Appendix 2 to
Federal rules and regulations
in the area of atomic
energy use "Safety rules for
decommissioning of
uranium-graphite production reactors"
approved by
Order of the Federal Environmental,
Industrial and Nuclear
Supervision Service
dated September, 8, 2017 No. 357

 

TERMS AND DEFINITIONS

 

The terms established by the federal laws as well as federal rules and regulations in the area of nuclear energy use are used in these Rules. In addition, the terms listed below are used for the purposes of these Rules.

Uranium-graphite production reactor decommissioning database – the set of documented and structured data on the UGPR operation, the CERE results, results of experimental research and calculations, design data required for planning and performance of works for the UGPR preparation for decommissioning and decommissioning, as well as on the results of works performed at all stages of the UGPR decommissioning.

Selected uranium-graphite production reactor decommissioning option - the particular UGPR decommissioning option selected based on comparison of the possible UGPR decommissioning options.

Abandonment of the uranium-graphite production reactor - the UGPR decommissioning option providing for decontamination of the UGPR buildings, structures, systems and components contaminated with radionuclides to the permissible level in accordance with the effective radiation safety standards and (or) their dismantling, management of generated RW and other hazardous wastes as well as preparation of the decommissioned UGPR site for further restricted or unrestricted use.

Disposal of the uranium-graphite production reactor - the UGPR decommissioning option providing for arrangement of the special RW preservation station or the RW repository at the UGPR site.

Preservation of the uranium-graphite production reactor systems and components - the system of administrative and technical arrangements aimed to ensure operable state of the temporarily idle UGPR systems and components required in the course of decommissioning works within the time period prescribed in the UGPR decommissioning program or project.

Concept of the uranium-graphite production reactor decommissioning - the document where the procedure and arrangements for the UGPR decommissioning aimed to minimize the radiation exposure for the workers (personnel), the public and the environment due to the planned UGPR decommissioning works and to assure safe termination of its operation shall be specified for the selected UGPR decommissioning option.

Site of the decommissioned uranium-graphite production reactor – the territory where the UGPR buildings and structures are located, with the boundaries defined in the UGPR decommissioning design documentation.

Uranium-graphite production reactor - structures and complexes with the graphite-moderated nuclear reactor, the required systems, devices and equipment for industrial production of nuclear materials located within the specified territory.

System of the uranium-graphite production reactor - the set of the UGPR components intended to perform the assigned functions.

Safe decommissioning conditions for the uranium-graphite production reactor - requirements for the quantity, characteristics, operability of the UGPR systems and components, frequency, scope and other conditions of maintenance and repair, monitoring and testing of the UGPR systems and components established in the UGPR decommissioning design documentation and to be adhered to in order to ensure safety in the course of the UGPR decommissioning.

Physical barrier - obstruction on the way of ionizing radiation, NM, RSb and RW propagation.

Components of the uranium-graphite production reactor - equipment, devices, instruments, pipelines, cables, civil structures of the UGPR and others items ensuring performance of the prescribed functions independently or within the systems and considered in the design documentation as structural units for reliability and safety analysis.

Stage of the uranium-graphite production reactor decommissioning - the set of administrative and technical arrangements and works specified in the UGPR decommissioning design documentation, implemented within a certain period of time and aimed to achieve the UGPR state prescribed in the UGPR decommissioning program and design documentation after completion of all planned works.

Nuclear-safe state of the uranium-graphite production reactor - the UGPR state after removal of spent nuclear fuel from its site when occurrence of any self-sustaining chain fission reaction is prevented.

 

 

 

 

 

Appendix 3 to
Federal rules and regulations
in the area of atomic energy use "Safety rules
for decommissioning of
uranium-graphite production
reactors"
approved by
Order of the Federal Environmental,
Industrial and
Nuclear Supervision Service dated
September, 8, 2017 No. 357

 

REQUIREMENTS
FOR THE STRUCTURE AND CONTENTS OF THE SAFETY ANALYSIS REPORT FOR
DECOMMISSIONING OF
URANIUM-GRAPHITE PRODUCTION REACTORS

 

I. Structure of the safety analysis report for
decommissioning of uranium-graphite production reactors

 

1. The UGPR decommissioning SAR shall include the following chapters:

Introduction;

Selected UGPR decommissioning option;

Characteristics of the UGPR location area and site;

Sources of ionizing radiation and radiation situation in the rooms and at the UGPR site;

Radiation safety;

Buildings, structures, systems and components used for the UGPR decommissioning;

Safety analysis for the UGPR decommissioning;

Arrangement of the UGPR decommissioning works;

Accounting and control;

Physical protection;

Completion of the UGPR decommissioning works;

 

II. Contents of individual chapters of the
safety analysis report for decommissioning of
uranium-graphite production reactors

 

Introduction

 

2. The following shall be specified in the chapter "Introduction":

information on the operating organization and developers of the SAR;

brief information on the UGPR siting, construction and operation history, information on the decision with regard to the UGPR decommissioning;

basic safety assurance principles in the course of the UGPR decommissioning;

brief description of the UGPR including description of its main buildings and structures, structural peculiarities of the civil structure components and schemes, particularly within the UGPR cavity;

information on the main works performed in order to prepare the UGPR for decommissioning including the data on the UGPR bringing into the nuclear-safe state;

basic information on qualitative and quantitative composition of radioactive substances, special and removable radioactive wastes located at the UGPR site;

the list of federal laws, federal rules and regulations in the area of atomic energy use and other regulations containing the requirements taken into consideration for development of the UGPR decommissioning design documentation.

 

Selected decommissioning option for the
uranium-graphite production reactor

 

3. The selected UGPR decommissioning option shall be described in the chapter "Selected decommissioning option for the uranium-graphite production reactor", particularly:

the UGPR decommissioning stages defined in the UGPR decommissioning design documentation and their duration;

safety assurance measures at each UGPR decommissioning stage;

the state of the decommissioned UGPR upon completion of the works at each UGPR decommissioning stage including the radiation and technical condition of the main UGPR systems and components.

4. The basic technical and administrative solutions related to safety assurance for the workers (personnel) and the public shall be described. Description of the arrangements shall contain the following brief information:

doses for the workers (personnel) performing the UGPR decommissioning works and exposure doses for the public in the course of the UGPR decommissioning;

administrative arrangements and engineering features provided in the UGPR decommissioning design documentation for each decommissioning stage and aimed to reduce exposure doses for the workers (personnel) and the public;

the scope of radiological control with indication of the applied methods and hardware;

regulation and restriction of access of the workers (personnel) to the UGPR rooms referred to the controlled access area;

arrangement of emergency planning for the UGPR decommissioning.

5. Technical solutions aimed to minimize the amount of the generated radioactive wastes, reduction of RSb releases and discharges into the environment and exposure doses for the workers (personnel) and the public at all UGPR decommissioning stages in accordance with the optimization principle shall be briefly described.

 

Characteristics of the location area and site
of the uranium-graphite production reactor

 

6. Information on geographical, topographical, hydrological, meteorological, geological and geotechnical conditions of the decommissioned UGPR location shall be provided in the chapter "Characteristics of the location area and site of the uranium-graphite production reactor".

7. The following shall be specified in the geographical position description:

administrative location of the UGPR site (republic, territory, region);

name of the administrative center;

distance to the administrative center;

distance to the nearest administrative boundaries;

position of the UGPR site in relation to natural and artificial benchmarks (populated localities, rivers, airports, railway stations);

the nearest industrial facilities (plants, chemical works, gas and oil pipelines, food processing facilities);

the nearest military facilities;

distance to the recreation areas and nature reserves.

8. Characteristics of the UGPR location area required to assess natural and human-induced impacts on safety of the UGPR decommissioning works in accordance with the federal rules and regulations in the area of atomic energy use establishing the requirements for consideration of external natural and human-induced impacts on the nuclear facilities shall be provided.

9. The consolidated list of external impacts shall be presented, and the methods and methodologies used to calculate probability of their occurrence shall be specified.

10. Information on the UGPR location area required to assess the impact of the decommissioned UGPR on the public and the environment shall be presented.

 

Sources of ionizing radiation and radiation
situation in the rooms and at the site of the
uranium-graphite production reactor

 

11. Information on the radiation situation in the rooms and at the UGPR site as well as estimated quantitative assessment of its changes in the course of the works at each UGPR decommissioning stage shall be provided in the chapter "Sources of ionizing radiation and radiation situation in the rooms and at the site of the uranium-graphite production reactor" based on the CERE results.

12. Radionuclide content in the main UGPR systems and components shall be specified, particularly for:

the reactor plant;

the spent fuel pool;

the process cavities;

RW storage facilities and repositories;

special ventilation and sewage systems;

other UGPR buildings, structures, systems and components contaminated with radionuclides.

Information on radionuclide contamination of the UGPR site as well as information on any sealed radionuclide sources used in the course of the UGPR decommissioning shall be presented.

13. Information on the ionizing radiation sources determining the radiation situation in the rooms and at the UGPR site shall be specified. Information on the radionuclide composition and activity of the sources as well as the input data used for their determination shall be provided. The charts of the exposure dose rates in the rooms and at the UGPR site and distribution of radioactive contamination (surface activity) on the surfaces of the UGPR rooms shall be provided.

14. The sources of radionuclide ingress into the air of the UGPR rooms considered in development of the protective measures and assessment of the exposure doses for the workers (personnel) and the public in the course of the UGPR decommissioning shall be described. Models, parameters and input data required to calculate concentration of radioactive gases and aerosols in the UGPR rooms shall be provided.

15. Characteristics of radioactive wastes used as the input data to develop the systems for handling of all removable RW types accumulated in the course of the UGPR operation or generated in the course of the UGPR decommissioning shall be specified.

16. Information on the concentration (activity) of radionuclides used to calculate the dose rates in the UGPR rooms shall be provided. The mathematical models and input data used for the calculations (for example, flow rates, concentrations, energy spectra) included into development of the RW handling systems shall be described.

 

Radiation safety

 

17. The radiation protection principles adopted in the UGPR decommissioning project shall be specified in the chapter "Radiation safety".

18. Information on the ways to ensure radiation safety in the course of the UGPR decommissioning, particularly in case of design basis accidents shall be provided.

19. Quantitative values of the parameters used to identify occurrence of a near-accident situation or accident shall be presented.

20. Engineering features and administrative measures for protection of the workers (personnel), the public and the environment against any impermissible radiation exposure shall be described.

21. Design peculiarities of the systems and equipment used in the course of the UGPR decommissioning enabling to reduce exposure doses for the workers (personnel) in accordance with the optimization principle shall be specified.

22. Radiation criteria used to develop the administrative arrangements and engineering features provided in the course of radiation-hazardous works in order to reduce exposure doses for the workers (personnel) in accordance with the optimization principle shall be specified.

23. The input data, methods and calculation models as well as any assumptions adopted  to assess exposure doses for the workers (personnel) and the public shall be provided.

The following data shall be provided:

assessment of individual doses for the workers (personnel) in the course of each type of radiation-hazardous works at each stage of the UGPR decommissioning;

assessment of the maximum annual effective exposure dose for the persons from the critical population group in the course of the UGPR decommissioning.

24. Engineering features provided in the design documentation in order to reduce the dose rate in the controlled access area rooms and the period of the personnel (workers) stay in these rooms shall be described.

25. The boundaries of the controlled access area and segregation of its rooms into non-attended rooms, the rooms for temporary and permanent stay of the personnel shall be specified.

26. Information on the software tools and (or) calculation methods used to analyze radiation safety for the workers (personnel) and the public shall be provided; calculation results including the estimated radiation level in the attended and periodically attended rooms as well as in the uncontrolled access area rooms in the course of the UGPR decommissioning works shall be specified.

27. Sequence of dismantling of physical barriers and (or) arrangement of additional physical barriers at each stage of the UGPR decommissioning shall be presented.

28. The main parameters of the controlled access area ventilation systems, the plan of the rooms where air purification is carried out and the purification equipment is installed, the pipeline routing scheme, locations and technical characteristics of the valves and filters shall be described. It should be substantiated that the provided technical solutions for air purification from radioactive gases and aerosols ensure the required air purity maintenance and non-exceedance of the RSb release norms.

29. The means for determination of air purification efficiency, replacement and transportation of used filters (filtering elements) shall be described. Characteristics of the applied air treatment means as well as the criteria established for replacement of filters (filtering elements) shall be specified. Purification coefficients adopted for the radiation safety analysis shall be specified.

30. Amounts and particle sizes of radioactive aerosols to be generated in the course of the UGPR decommissioning works shall be assessed based on the fragmentation techniques provided in the design documentation for the UGPR buildings and structures and the data on particular equipment used for this purpose.

31. Criteria for selection of radiological monitoring hardware, development of the sampling point scheme and location of the equipment (instruments) shall be specified. The radiological control hardware provided in the UGPR decommissioning design documentation shall be described, including the following:

continuous monitoring devices based on stationary automated systems and stationary instruments;

in-process monitoring devices based on portable, transportable and (or) mobile instruments and units;

laboratory analysis devices based on laboratory units, means for sampling and preparation of radioactive samples for analyses;

devices for individual dosimetric monitoring of the workers (personnel).

The description shall include the information on alarm units, recording devices and location of the sensors, indication (reading) and warning devices (instruments).

32. The means for collection, storage, processing, systematization and presentation of the data on radiation contamination of the rooms and the UGPR site, the environment as well as exposure doses for the workers (personnel) in the course of the UGPR decommissioning shall be described.

33. The organizational structure of the radiation safety service engaged in safety assurance in the course of the UGPR decommissioning as well as the procedure for interaction of this department with any other units of the operating organizations and divisions of the organizations performing the works and rendering the services to the operating organization with regard to the UGPR decommissioning shall be described.

34. Technical and administrative arrangements for control of the personnel (workers) stay in the controlled access area and compliance with the radiation-hazardous work performance guidelines shall be described.

35. The main areas of activity for radiological control shall be specified with indication of the technical and administrative solutions aimed to reduce exposure doses for the workers (personnel) and the public in the course of the UGPR decommissioning, including the solutions provided to control:

integrity and operability of the physical barriers;

exposure doses for the workers (personnel);

releases and discharges of radioactive substances into the environment;

in the rooms and at the UGPR site;

in case of any accidents with due regard for potential accident development scenarios accompanied with releases of radioactive substances into the environment as well as monitoring of the radiation situation in the accident zone.

It should be demonstrated that the radiological control system ensures measurement of the radiation parameters within all required measurement ranges and in all required energy ranges of gamma-, beta- and alpha-radiation.

36. The following information shall be presented in the radiological control description and substantiation:

the objects of control;

measuring equipment used for control including their metrological support;

scope (controlled parameters, types and quantity of sensors, the measurement range, the basic error) and frequency of control.

The procedural guidelines used to assess the external and internal exposure doses for the workers (personnel) shall be specified.

37. Information on availability of any medical and sanitary rooms and types of the radiological control equipment (instruments, devices) used in these rooms shall be specified. Personal protection equipment, its characteristics, usage and maintenance shall be described. Information on availability of any airlocks, rooms of duty dosimetricians and outgoing radiological control stations, laboratory units for radio - and spectrometric analysis, storage facilities for working clothes, personal respiratory protection equipment, decontamination means for the equipment and skin of the workers (personnel), the emergency set of personnel protection equipment, tools and equipment used for confinement and mitigation of accidents at the decommissioned UGPR shall be provided.

 

Buildings, structures, systems and components
used for decommissioning of the
uranium-graphite production reactor

 

38. The list of the UGPR buildings, structures, systems and components shall be presented in the chapter "Buildings, structures, systems and components used for decommissioning of the uranium-graphite production reactor". The following shall be specified for the buildings, structures, systems and components to be used in the course of the UGPR decommissioning:

technical condition category of the buildings, structures, systems and components as well as the data used as the basis for conclusion on their technical condition categories;

information on the remaining life of the buildings and structures necessary to assess their capability to perform the functions related to safety assurance in the course of the UGPR decommissioning;

arrangements and adopted solutions aimed to extent the useful life of the buildings, structures, systems and components for the period of the UGPR decommissioning works.

39. Technical condition monitoring methods and hardware for the buildings, structures, systems and components of the decommissioned UGPR shall be described.

40. Description of the methods and equipment for dismantling and decontamination of the decommissioned UGPR buildings, structures, systems and components shall be provided. Information on provision of any new systems and equipment required for safety assurance in the course of the UGPR decommissioning works shall be presented.

41. Methods and equipment for handling of all RW types and materials for restricted use shall be described.

42. Any systems and components required for the UGPR decommissioning and provided in the UGPR decommissioning design documentation shall be described and substantiated. Description of the systems shall include:

purpose and design basis;

description of equipment and components;

control and monitoring;

reliability analysis.

43. All systems and components where formation of explosive gas concentrations is possible shall be listed, the design pressure shall be specified, and their explosion safety shall be substantiated. The instrumentation (including gas analyzers) and any technical and administrative solutions provided in the design documentation for prevention of explosions and mitigation of their consequences shall be described.

44. Ventilation systems of each UGPR building and facility where radioactive aerosols can be generated and (or) RW handling works are performed shall be described. The description shall include the volumes of the buildings, the expected flow rates in the ventilation systems, characteristics of the filters and calculation criteria used to determine these values. Normal operation mode of each ventilation system at all stages of the UGPR decommissioning and peculiarities of the system operation in case of design basis accidents shall be described.

45. Design concentrations of radioactive gases and aerosols in the UGPR rooms shall be specified for all UGPR decommissioning modes including design basis accidents.

46. It should be demonstrated (based on the capacity calculations for the ventilation and gas treatment systems) that the systems ensure non-exceedance of the permissible limits with regard to releases of radioactive substances in all design UGPR decommissioning modes including design basis accidents.

47. Any LRW handling systems and equipment provided in the UGPR decommissioning design documentation shall be described and substantiated. The main characteristics of the LRW handling systems in all UGPR decommissioning modes and in case of design basis accidents shall be specified.

48. The expected amount (volume, activity, weight) and radionuclide composition of the liquid radioactive wastes generated at each decommissioning stage and within the entire UGPR decommissioning period shall be specified.

49. Information on the design capacity of the systems for handling of LRW and liquid radioactive media in all design modes (under normal UGPR decommissioning conditions and in case of any accidents) shall be provided. Handling techniques for all LRW and liquid radioactive media shall be described.

50. Parameters and assumptions used to calculate releases of radioactive substances shall be presented, the expected RSb discharge amount and the estimated short-term maximum potential daily RSb discharge from the UGPR to the environment shall be specified.

51. Systems and equipment for handling of all removable SRW types shall be described. Their design capacity and structural materials shall be specified. The expected SRW amount, their sources, physical form, class, radionuclide composition and specific activity shall be provided. The input data used to obtain the above-mentioned values shall be presented, and the types and characteristics of the containers used for SRW handling shall be described.

52. The schemes of the processing, conditioning, storage areas, loading and transportation of different removable RW categories shall be provided.

53. Arrangements provided for decontamination of RW containers and their transportation to the storage facilities shall be specified.

 

Safety analysis for decommissioning of the
uranium-graphite production reactor

 

54. Safety analysis performed in accordance with the list of initiating events for design basis accidents and the list of beyond design basis accidents as well as safety criteria adopted for the UGPR decommissioning project shall be provided in the chapter "Safety analysis for decommissioning of the uranium-graphite production reactor".

55. The list of initiating events for design basis accidents provided in the UGPR decommissioning design documentation shall be presented; this list shall be developed with due regard for the following:

external impacts of natural and human-induced origin possible at the decommissioned UGPR site;

failures of any systems and components required for safe decommissioning of the UGPR;

human errors.

56. The list of initiating events provided in the UGPR decommissioning design documentation shall be substantiated with due regard for the results of analysis of any operational occurrences possible in the course of the UGPR decommissioning.

57. Analysis results for any radiological consequences of operational occurrences possible in the course of the UGPR decommissioning including design basis accidents shall be provided in accordance with the list of initiating events, particularly the following shall be specified for each analyzed operational occurrence:

description of the initial state for any systems and components required for safe decommissioning of the UGPR;

description of the operational occurrence development scenario;

the set of input data used for the analysis including references to their sources;

description of the calculation methods and (or) software tools used for the analysis;

radiation exposure values for the UGPR workers (personnel), the public and the environment in case of any operational occurrence obtained on the basis of the conservative approach.

58. The list of beyond design basis accidents shall be provided; it shall be demonstrated that this list is compiled with due regard for qualitative and (or) quantitative assessment of potential severity of:

consequences of the initiating events of design basis accidents with coincident human errors;

external and internal impacts not considered for design basis accidents.

Sequences of events and failures that can have the most severe consequences shall be provided based on this assessment, and all beyond design basis accident development ways resulting in unacceptable radiation exposure for the workers (personnel), the public and the environment shall be specified.

59. The following shall be specified for each beyond design basis accident included into the list:

description of the initial state for any systems and components required for safe decommissioning of the UGPR;

description of the beyond design basis accident development paths;

the set of input data used for the analysis including references to their sources;

description of the calculation methods and (or) software tools used for the analysis;

numerical radiation exposure values for the UGPR workers (personnel), the public and the environment in case of any beyond design basis accident obtained on the basis of the realistic (non-conservative) approach.

60. Description of any validated calculation methods and software tools used for safety analysis shall contain brief information on their application scope and restrictions, the implemented mathematical models and calculation errors as well as references to the relevant validation documents. It should be demonstrated for any calculation methods and software tools not validated in accordance with the established procedure that their checking and verification have been arranged in order to confirm their applicability and assess their accuracy.

61. General conclusions on the main results of safety analysis for the UGPR decommissioning shall be made including the conclusion on the UGPR safety assurance in case of design basis accidents.

 

Arrangement of the works for decommissioning of
the uranium-graphite production reactor

 

62. Information on preparation and arrangements of the works for the UGPR decommissioning shall be presented in the chapter "Arrangement of the works for decommissioning of the uranium-graphite production reactor". It should be demonstrated how the organizational structure of the operating organization and the provided set of arrangements ensure implementation of the technical and administrative solutions prescribed in the UGPR decommissioning design documentation.

63. The particular solutions provided by the operating organization for transportation of the removable radioactive wastes from the UGPR site for disposal in the existing RW repositories or location of the removable radiative wastes in the existing RW storage facilities prior to their handover for disposal shall be described.

64. The organizational chart of the operating organization department engaged in the activities for the UGPR decommissioning support shall be provided. The information shall contain the list of units or organizations engaged by the operating organization for performance of particular types of works related to the UGPR decommissioning, the data on distribution of liabilities and authorities among these units.

65. The procedure and arrangements provided in the operating organization for registration of the information in the UGPR decommissioning database shall be specified.

66. Information on the adopted quality assurance system shall be provided including control of the UGPR decommissioning works and the procedures for data collection and analysis.

67. The list and description of the natural phenomena observation programs implemented at the UGPR decommissioning stages shall be provided, including the information on the following programs:

geodetic monitoring;

seismic monitoring;

monitoring of the ground and surface water regime;

meteorological observations;

geotechnical control.

Descriptions of the observation programs shall include:

lists of observed processes, phenomena and factors as well as types of observations;

location and elevations of the measurement points, measuring methods and means;

the procedure for analysis of the obtained information and the reporting formats.

68. Information on any arragements for maintenance and repair of the buildings, structures, systems and components required for the UGPR decommissioning shall be provided.

69. Information on development and availability of the action plans for protection of the workers (personnel) and the public in case of any radiation accident and the main arrangements provided in these plans shall be presented. Information on availability of the plan (guidelines) for mitigation of any accidents at the decommissioned UGPR and the main arrangements provided in this plan (guidelines) shall be presented.

 

Accounting and control

 

70. Information on accounting and control of radioactive wastes, radioactive substances and nuclear materials (if any) shall be presented in the chapter "Accounting and control" including the following information:

areas of RW location for temporary storage;

description of the calculation methods, methodologies and instrumentation used for RW accounting and control;

the list of accounting and reporting documents.

 

Physical protection

 

71. Information on the basic administrative and technical solutions aimed to prevent any unauthorized actions of the workers (personnel) or other persons in relation to radioactive substances, radioactive wastes, systems and equipment of the decommissioned UGPR shall be presented in the chapter "Physical protection".

72. The information presented in this chapter shall confirm compliance with the requirements of the regulatory documents for physical protection in the course of the UGPR decommissioning.

73. Any changes in the scope of physical protection for the decommissioned UGPR according to implementation of its decommissioning stages provided in the UGPR decommissioning design documentation shall be presented.

 

Completion of the works for decommissioning of the
uranium-graphite production reactor

 

74. The chapter "Completion of the works for decommissioning of the uranium-graphite production reactor" shall include the list and brief description of the main arrangements required to complete the UGPR decommissioning, particularly:

the schedule of arrangements for preparation and performance of the final UGPR examination with indication of the brief information on the methods provided in the UGPR decommissioning design documentation in order to confirm achievement of the prescribed end state;

the procedure for documenting of the final UGPR examination results;

measures for safe keeping of the documents related to the UGPR decommissioning.

 

 

 

 

 

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