Approved by
Order of Federal
Environmental, Industrial
and Nuclear Supervision Service
No. 162 dated April 5, 2018
IN THE FIELD OF THE USE OF ATOMIC ENERGY "BASIC
REQUIREMENTS FOR THE OPERATION EXTENSION
OF A NUCLEAR POWER PLANT POWER UNIT"
(NP-017-18)
I. Purpose and scope
These federal rules and regulations in the field of nuclear energy use "Basic requirements for the operation extension of a nuclear power plant power unit" (NP-017-18) (hereinafter the Basic Requirements) have been developed in accordance with article 6 of Federal Law No. 170-FZ dated November 21, 1995 "On the Use of Atomic Energy", Provisions for development and approval of federal rules and regulations in the field of the use of atomic energy approved by Resolution of the Russian Federation Government No. 1511 dated December 1, 1997 (Collected Acts of the Russian Federation, 1977, No. 49, article 5600; 2012, No. 51, article 7203), and establish the requirements for extending the operating life of the NPP power unit, including integrated survey of the NPP power unit during the preparation for extending its operating life, criteria of operation possibility of the NPP power unit during the additional operating life, requirements for extending the operating time of the NPP components outside the designated operating life of the NPP power unit, requirements for justification of the additional operating life of the NPP power unit, requirements for preparation of NPP power unit for additional operating life.
2. These Basic requirements must be met when organizing and performing preparation works of the NPP power unit for operation on expiry of its designated or previous additional operating life. For the NPP power units for which the works (or part of the works) for preparing the NPP power unit for operation after the expiry of the designated operating life were performed before putting into effect these Basic requirements, the procedure for conformation of nuclear power plants with the Basic requirements, including the time limits and scope of required measures must be determined in each specific case in operation license conditions of the NPP power unit during the additional operation life.
3. The list of abbreviations is given in Appendix 1, and terms and definitions are given in Appendix 2 to these Basic requirements.
II. General
4. The operator must perform safety assessment of the NPP power unit at least 5 years before the end of the designated or additional operating (service) life, based thereof it must decide on the possibility of continuing its operation or decommissioning. The specified decision must be taken with the participation of the developers of RP and NPP designs.
5. The decision on possibility of continuation of operation of the NPP power unit after the end of its designated additional operating life must be taken by the operator based on:
results of assessments of the residual life of irreplaceable components of the NPP power unit, and the building constructions, buildings, structures and status of their foundations <1>;
--------------------------------
<1> The concepts "building constructions", "buildings", "structures", "foundations of buildings and structures", "mechanical safety" must be applied in the meanings established by Federal Law No 384-FZ dated December30, 2009 "Technical regulation on safety of buildings and structures" (Collection of legislative acts of the Russian Federation, 2010, No. 1, art. 5; 2013, No. 27, art. 3477; 2008, No. 30 (p.
results of the safety assessment of NPP power unit, including periodic safety assessments;
results of the executed integrated survey of the NPP power unit;
data on change of characteristics of the NPP deployment site (including data on change of seismicity) for the previous period of operation;
analysis of operating experience;
conformity of the NPP power unit to the requirements of FRR and regulatory legal acts in force at the time of assessment, regulating safety assurance during operation of the NPP power unit;
possibility of safety assurance of temporary storage of SNF generated in the period of additional operating life;
possibility of safety assurance during handling of radioactive waste generated during the additional operating life;
possibility of safety assurance of the NPP power unit during its decommissioning.
6. The operator after taking the decision on the possibility of continuing operation of the NPP power unit based on the results of the integrated survey must develop the preparation program of the NPP power unit for extension of operating life, stipulating:
performing safety analysis of the NPP power unit for conformity to the requirements of FRR and other regulatory legal acts;
justification of the residual life of important to safety building constructions, buildings, structures and state assessment of the foundations;
justification of the residual life of the NPP power unit components in the period of additional operating life;
measures for replacement of the components that had come to the end of its service life or residual life that may not be determined;
measures for elimination (or compensation of the negative influence on the safety of NPP power unit) of available non-conformities to FRR requirements;
measures for modernization of the NPP power unit for safety assurance of its operation;
measures for radiation measurement of the rooms, equipment and piping;
list of tests of the NPP power unit systems and components in compliance with the requirements of FRR;
development (updated) of the life management program of the building constructions, buildings, structures, systems and components of the NPP power unit in the period of additional operating life considering the scheduled measures for replacement and/or upgrade of the NPP power unit systems and components;
development (update) of the measures for state monitoring of the building constructions, buildings, structures and their foundations as well as the NPP power unit systems and components in the period of additional operating life;
development of an individual operating non-destructive testing program of the metal of equipment, piping and other components of the NPP considering the provisions of FRR stipulating the requirements for monitoring the base metal, weld joints and deposited surfaces during operation of equipment, pipelines and other NPP power unit components for the period of additional operating life;
development (update) of SAR of the NPP power unit (ISAR of the NPP power unit), justifying the safety of the NPP power unit for the entire period of additional operating life;
correction of the operating documentation.
7. If the operating organization reveals any factors following the nuclear facility safety analysis that prevent its safe operation within the additional service life and cannot be eliminated, the works must be performed to prepare the NPP power unit for decommissioning.
III. Integrated survey of the NPP power unit
8. The operator must organize the integrated survey of the NPP power unit for assessment of the actual state of the NPP power unit, determination of residual life of its components, and for developing the preparation program of the NPP power unit for extension of the operating life.
9. The integrated survey works of the NPP power unit must be performed in the procedure and within the time limits stipulated by the operator with the participation of the developers of the RP and NP designs.
10. The program of integrated survey of the NPP power unit overall as well as its systems and components, building constructions, buildings, structures and their foundations must be developed before the integrated survey of the NPP power unit.
11. The NPP power unit integrated survey program must contain:
list of important to safety systems and components, building constructions, buildings, structures and their foundations subject to survey;
stages of integrated survey;
methods and forms of integrated survey;
scope of preparatory works.
12. The integrated survey program of the NPP power unit must be approved by the operator and agreed with the developers of the RP and NP designs.
13. The following must be determined during the integrated survey of the NPP power unit:
technical condition of building constructions, buildings, structures important to safety, NPP power unit systems and components;
components having reached the end of its service life and subject to replacement;
components, the service life thereof has not reached the end and operation thereof may be continued for a specific time period;
components, the service life thereof has not reached the end, but replacement thereof is required in the designated or additional operating life of the NPP power unit according to the replacement schedule;
components, the service life thereof has not been determined and for which the determination of the residual life or replacement must be required;
radiation situation in the rooms of the NPP power unit, at its site and in the sanitary-protective area;
rooms, equipment and piping subject to decontamination;
possibility of assuring storage safety of SNF and radioactive waste generated in the period of additional (repeat additional) operating life;
possibility of safe handling of radioactive waste.
14. Results of the comprehensive examination of the NPP power unit must be given in the report approved by the operator containing:
list of examined systems and components, building constructions, buildings, structures and their foundations as well as brief information about them;
list of systems and (or) components of the NPP power unit subject to replacement;
list of building constructions, buildings, structures of the systems and /or components of the NPP power unit, for which additional measures are required for assuring he required technical condition and residual life;
list of NPP power unit systems and/or components which may be continued in the period of additional operating life.
composition of the works, methods and scopes of integrated equipment of the NPP power unit, including the organization of condition monitoring of the NPP power unit components, methods and scope of monitoring (monitoring of operation modes, metal state monitoring, technical certification, verifications, tests, sampling, checkout and calibration);
results of monitoring;
assessment of the technical condition categories of the construction examination of the condition of buildings, structures and their structural components;
decision criteria on replacement of the NPP power unit component or on extension of its operation;
general conclusions on actual technical condition of the NPP unit.
IV. Nuclear power plant power unit operation possibility criteria
in the period of additional operating life
15. The operation of NPP power unit in the period of additional or repeat additional operating life may be extended if:
the NPP power unit conforms to the requirements of FRR and/or required technical and/or organizational measures have been taken directed at rectification or compensation of the non-conformities rendering or capable of rendering negative influence on the safe operation of the NPP power unit;
the operator had developed and executes the life management programs important to safety of the building constructions, buildings, structures, systems and components of the NPP power unit;
life of the irreplaceable components of the NPP has not been exhausted and is sufficient for the period of additional or repeat additional operating life;
hardware and monitoring methods of their residual life are provided for in the life management programs important to safety of building constructions, buildings, structures, system and components of the NPP power unit;
an individual standard program of operating non-destructive testing of the metal of equipment, piping and other NPP components in the period of additional operating life of the power unit;
technical condition of the NPP power unit in the period of additional operating life conforms to the designs of RP and NPP;
radiation situation in the rooms of the NPP power unit, at its site and in the sanitary-protective area conforms to the regulatory requirements;
possibility of temporary safe storage of SNF and ensuring safety when handling radioactive waste generated during the additional operating life have been provided for;
SAR of the NPP power unit (In-depth Safety Assessment of Nuclear Power Plant Power Unit) for the period of additional operating life has been developed.
16. The following must be taken into account on justification of the possibility of extension (repeat extension) of the operating life of the NPP power unit and on justification of the residual life of the NPP components:
metal degradation mechanisms of irreplaceable systems and components, concrete and reinforcement of building constructions, buildings, structures including the degradation mechanisms not considered in the designs of RP and NPP;
degradation of insulation and protection characteristics of irreplaceable cables, electrical equipment, stationary facilities of I&C*A equipment, radiation monitoring systems;
degradation of anticorrosive plating of metal of the reactor vessel, equipment and piping;
reduction of the thickness of walls important to safety of equipment and piping due to corrosion and erosion.
17. Justification results of the residual life of NPP components considering the Basic requirements of the degradation mechanisms of materials listed in the item 16 of these Basic requirements must be given in SAR of the NPP power unit (ISAR (in-depth safety analysis report) of the NPP power unit).
18. The list of building constructions, buildings, structures, systems and components of the NPP power unit must be defined and justified when extending the operating life of the NPP power unit following integrated survey of the NPP power unit for organizing additional monitoring of the technical state and state of the design materials with specification of the monitoring areas. For the period of repeat additional operating life of the NPP power unit the specified list must be updated based on the actual state of the components established following the integrated survey of the NPP power unit.
19. The scope and periodicity of surveys and technical state monitoring important to safety of the building constructions, buildings, structures and their foundations as well as non-destructive test of the condition of metal of the NPP power unit systems and components must be established based on their actual state and residual life. The scope and monitoring periodicity must be justified.
20. For NPP components belonging to safety classes 1 and 2 in accordance with Federal Rules and Regulations in the use of nuclear energy "General provisions for safety assurance of nuclear power plants" NP-001-15 (hereinafter NP-001-15) approved by Order No. 522 dated December 17, 2015 of Federal Environmental, Industrial and Nuclear Supervision Service (registered by the Ministry of Justice of the Russian Federation on February 2, 2016, registration No. 40939, official internet portal for legal information www.pravo.gov.ru 2016, No. 0001201602050003), the periodicity of surveys and technical state monitoring of the building constructions, buildings, structures and their foundations as well as non-destructive test of the condition of metal of the NPP power unit systems and components must be established based on their actual state and must be performed at least once in four years.
V. Requirement for extension of the operating life
of the NPP power unit components important to safety
21. The residual lifetime of the NPP power unit components important to safety must be determined with due regard for actual operating conditions of the NPP power unit and actual technical state of the NPP power unit components on the date of survey.
22. The residual life of the NPP power unit components belonging to safety class 1, 2 and 3 in accordance with NP-001-15 must be confirmed based on:
the national standards and codes of practices mandatory for use for meeting the requirements of Federal Law No. 384-FZ dated December 30, 2009 "Technical Regulations on Safety of Buildings and Structures";
FRR, establishing the requirements for justification of strength and management of NPP equipment and piping life;
the national standards and codes of practices mandatory for use for meeting the requirements of the FRR, establishing the requirements for justification of strength and NPP equipment and piping life;
standards used in the life management programs of the NPP power unit systems and components (if there is justification of the possibility of their use in the period of additional operation life of the NPP power unit).
23. For VVER reactor vessels the duration of the additional operating life must be confirmed by the justification that to the end of the additional (repeat additional) operating life the fracture toughness values of the base metal and metal of welded joints located in the exposure zone must allow without damage withstand all operation and emergency loads conditioned by the entry of cold water into the reactor vessels as well as the loads during hydraulic tests. The confirmation of the minimum fracture toughness values of the base metal and metal of welded joints must be based on data received on the surveillance specimens or templates.
24. The operator must organize restoration of the values of mechanical properties of the base metal and metal of the welded joints of the reactor vessel or limit the period of additional (repeat additional) operating life by the time during which resistance to brittle failure of the reactor vessel must be provided if impossible to provide resistance to brittle failure of the VVER reactor vessel for the entire additional (repeat additional) operating life following radioactive and thermal embrittlement.
25. The efficiency of the restoration measures of the mechanical property values of the base metal and metal of welded joints of the VVER reactor vessel must be justified before taking the decision on extension of the NPP power unit operation time.
26. On justification of brittle fracture resistance of VVER type reactor vessel it is required to consider:
radiation and thermal embrittlement of the base metal and metal of welded joints for the entire period of operation, including in the period of additional (repeat additional) operation period;
influence of the modernization of reactor emergency core cooling system on the permitted value of brittle to ductile transition of the base metal and metal of welded joints;
monitoring results of the surveillance specimens or templates of the base metal and metal of welded joints;
monitoring results of the reactor vessel metal during integrated survey;
undergrowth of detected defects in the period of additional (repeat additional) operating life;
corrosive damages of the reactor vessel metal (for the surfaces not protected by anticorrosive plating).
27. The duration of additional (repeat) additional operating period of the steel structures of RBMK and EGP-6 type reactors must be justified by the results of works performed confirming that to the end of the period of additional (repeat additional) operating life, the resistance to breaking of steel structures must be justified on most favorable combination of operating and seismic loads.
28. It is required to consider the following on justification of the resistance to breaking of steel structures of RBMK and EGP-6 type reactors:
monitoring results of the available specimens of base metal and metal of welded joints of the steel structures, and specimens of metal cut out directly from the steel structures of this NPP power unit or its analog;
monitoring results of the steel structures during integrated survey;
undergrowth of detected defects in the period of additional (repeat additional) operating life;
radiation and thermal embrittlement of the base metal and metal of welded joints of the steel structures for the entire period of operation, including in the period of additional (repeat additional) operation life;
corrosive thinning of the walls of steel structures for the entire period of operation, including in the period of additional (repeat additional) operation period;
29. Duration of the additional operating life of the graphite masonry of the RBMK and EGP-6 type reactors must be confirmed by the justification that to the end of the period of additional (repeat additional) operating life during most favorable combination of operating and seismic loads the physical and mechanical properties of graphite must be sufficient for maintaining the load bearing capacity of graphite columns, and crookedness of graphite columns must not lead to malfunctions of the control system work members and reactor protection and to appearance of inadmissible loads on the components of the reactor core or reactor steel structure.
30. The reduction of graphite weight in the reactor core must not lead to inadmissible change of the neutron-physical characteristics of the reactor core must be justified when performing repair works for restoring the geometric characteristics of the graphite columns.
31. It is required to consider the following on justification of the strength and performance of graphite masonry of RBMK and EGP-6 type reactors:
results of periodic investigations of the actual characteristics of the physical and mechanical characteristics of kern, cut out from the graphite masonry of the NPP power unit or its analogs;
results of periodic in-core monitoring of the process channels, CPS channels and graphite masonry;
results of performed repair and restoration works on the graphite masonry;
results of the forecasts of physical and mechanical characteristics of graphite and deformation of the graphite columns.
Periodic investigations of the actual physical and mechanical characteristics of graphite and measurements of graphite columns must be justified in the RP design and given in SAR of the NPP power unit (ISAR of the NPP power unit).
32. For BN type reactors condition monitoring of the base metal and metal of welded joints of the reactor vessel and vessel with safety containment must be performed at the places accessible for monitoring. The places and scopes of monitoring must be justified. The monitoring results of the reactor vessel and vessel with safety containment must be considered when justifying the period of additional operating life.
33. The duration of additional (repeat additional) operating life of the systems and components important to safety of BN type reactors must be confirmed by the justification that to the end of the period of additional (repeat additional) operating life, the strength and long-term strength of these systems and components must be provided on most unfavorable combination of operating and seismic loads considering the following:
degradation of the metal properties of reactor and core structures on integrated neutron exposure, high temperatures and creep processes;
exhaustion of the deformation capability of reactor metal and core structures;
justified forecast values of the characteristics of long-term strength and stress rupture ductility of the RP equipment and piping metal.
34. The period of additional (repeat additional) operating life of the building constructions, buildings and structures of the NPP power unit and their foundations must be confirmed considering the most unfavorable combination of all types of loads corresponding to the functional purpose and design solution of the buildings or constructions for which their mechanical safety must be provided considering the following:
actual values of the geometrical dimensions of the structures and their cross-sections, settlements, tilts;
actual state of the pre-stressing system of the structure (if available);
availability of cracks, chippings and local failures;
location, nature of cracks and width of their opening following monitoring;
state of protective coatings;
vertical deflections and deformations of the structures and their foundations;
signs of failure of grip of concrete on steel;
reinforcement fracture;
anchorage condition of longitudinal and crosswise reinforcement;
degree of corrosion of concrete and reinforcement bars.
35. Period of additional (repeat additional) operating life of the NPP power unit components must not exceed the residual life of these components, defined according to the requirements of item 22 of these Basic requirements.
36. Justification of the duration of additional (repeat additional) operating life of the NPP power unit must be based on:
conformance confirmation of the NPP power unit to the requirements of FRR and/or sufficiency of adopted technical and organizational measures directed at rectification or compensation of the non-conformities rendering or capable of rendering negative influence on the safe operation of the NPP power unit;
assessments of the technical condition for the period of additional operating life of the load-bearing structures of the buildings, constructions, where the NPP power unit systems and components important to safety are located, as well as the assessments of the technical condition of the foundations of these buildings and constructions;
residual life values of the non-replaceable components of the power unit;
residual life values of replaceable components of the NPP power unit important to safety, the life thereof was not stipulated during comprehensive examination;
observation of the operation limits and safe operation conditions, justified in the designs of RP and NPP considering the upgrades and/or replacements made of the systems and components;
confirmation of the possibility for safe storage of spent nuclear fuel and radioactive waste generated during the additional operating life;
VI. Requirements for preparation of the nuclear power plant power unit
for operation during additional (repeat
additional) operating life
37. The operator when preparing the NPP power units for operation in the additional (repeat additional) operating life must:
implement in full the measures, stipulated by the preparation program of the NPP power unit for operation in the additional life period specified in the item 6 of these Basic requirements;
make the required modifications to the operation documentation and life management program of the systems and components of the NPP power unit considering the upgrade or replacement made of a part of the systems and components;
conduct additional training of the NPP power unit personnel for developing hands-on operation experience of the power unit during the additional (repeat additional) operation life.
38. The replacement or upgrade of the NPP power unit systems or components must be made in accordance with the design and/or detailed design documentation.
39. The operator must perform safety justification of the NPP power unit in accordance with FRR considering the upgrade or replacement made of a part of the systems or components.
40. Before the start of operation of the NPP power unit during the additional life the Operator must perform the required pre-commissioning works and tests for confirming the functioning of the replaceable and upgraded systems and components of the NPP power unit in accordance with the design criteria and characteristics.
41. Performance of NPP power unit preparation works for extension of the operating life must not lead to damage or loss of the performance of the systems and components of the NPP power unit, to reduction of their life or lowering of the safety level of NPP power unit operation.
The operator based on the corresponding modifications in the designs of RP and NPP power unit must update the effective process regulation of the safe operation of the NPP power unit, the operation manuals (guidelines) for operation of the systems and components, manuals and guidelines defining the actions of the employees (personnel) in case of any design basis and beyond design basis accidents, and introduce the relevant changes in the data sheets of the systems and components.
43. Subsequent to completion of the works aimed to prepare the NPP power unit for operation within the additional operation period, the operator must prepare and approve the certificate on readiness of the NPP power unit for extension of the operating life.
Appendix 1
to Federal Rules and Regulations
in the field of the use of atomic energy
"Basic requirements
for the operation extension
of the nuclear power plant power unit", approved
Order of Federal
Environmental, Industrial
and Nuclear Supervision Service
No. 162 dated April 5, 2018
|
BN |
- |
Sodium Cooled Fast Neutron Reactor |
|
CPS |
- |
Reactor Control and Protection System |
|
EGP-6 |
- |
Heterogeneous Loop Type Power Reactor with 6 Coolant Circulation Loops |
|
FRR |
- |
Federal Rules and Regulations in the Field of Atomic Energy Usein the field of the use of atomic energy |
|
I&C |
- |
instrumentation and control and automation |
|
ISAR |
- |
In-depth Safety Analysis Report |
|
NPP |
- |
Nuclear Power Plant |
|
RBMK |
- |
High Power Channel Type Reactor |
|
RF |
- |
Reactor Facility |
|
SAR |
- |
safety analysis report |
|
SNF |
- |
Spent Nuclear Fuel |
|
VVER |
- |
Water Cooled Water Moderated Power Reactor |
Appendix 2
to Federal Rules and Regulations
of Nuclear Power Industry
"Basic requirements
for the operation extension
of the nuclear power plant power unit", approved by
Order of Federal
Environmental, Industrial
and Nuclear Supervision Service
No. 162 dated April 5, 2018
The following terms and definitions are used in these Basic requirements.
1. Additional operating life - calendar duration of the NPP power unit operation in excess of the target operating life.
2. Protective characteristics - parameters characterizing the capability of cables, electrical equipment and devices to withstand mechanical, thermal and/or radiation exposures without loss of functional qualities.
3. Assigned operating (service) life of an NPP unit is the calendar service life of the NPP unit (including maintenance and repair periods) established and substantiated in NPP and reactor facility designs.
4. Residual life of a NPP power unit component - difference between the stipulated and used resource of the NPP power unit component.
5. Repeat additional operating life of a NPP power unit - calendar duration of the NPP power unit operation in excess of the previous extensions of the operating lifetime.
6. Life management program of NPP power unit components - set of documents on life management of the NPP power unit components stipulated by FRR and binding for application by the standardization documents in the field of the use of atomic energy.
7. Operating life extension of the NPP power unit - carrying out a set of activities aimed to prepare the NPP power unit for operation within the additional operating or repeat additional operating life.
8. Lifetime of an NPP unit's component is the aggregate running time of the NPP unit's component from the beginning of its operation until the moment when there is irreversible disruption of strength or operability conditions established by regulatory documents.
9. Technical condition of the NPP unit - set of features of the NPP power unit component or NPP power unit or NPP power unit overall characterizing its capacity or its unavailability to perform its functions in accordance with NPP and RP designs.