Ключові слова
TLAA, аналіз безпеки, довгострокова експлуатація, ефекти старіння, управляння старінням, періодична переоцінка безпеки
Як цитувати
Shugailo, O.- i, Kazymyrska, O., Brik, D., Chumel, B., & Banko, S. (2021). Основні вимоги до TLAA та практика їх застосування в Україні та світі. Ядерна та радіаційна безпека, (2(90), 29-41. https://doi.org/10.32918/nrs.2021.2(90).04
Анотація
Управління старінням розглядається як один з основних факторів забезпечення безпеки ядерних установок на етапах проєктної та довгострокової експлуатації. Тому аналізу стану питання управління старінням приділяється відповідна увага і в Україні й у світі. Однією з основних складових робіт з управління старінням є виконання аналізів старіння, що визначають строк служби, так званих – TLAA (Time Limited Ageing Analysis). Фактично саме результати TLAA можуть бути інтерпретовані як строк продовження експлуатації конкретного елемента або конструкції. У цій статті наведені основні результати аналізу практики застосування TLAA у країнах Європи та США, досвіду України щодо переходу до довгострокової експлуатації на основі TLLA, виконано співставлення національних та міжнародних підходів до вимог TLAA, а також зроблено відповідні висновки.
Посилання
1. IAEA Safety Standards Series No. SSR-2/2 (Rev. 1). Safety of Nuclear Power Plants: Commissioning and Operation. International Atomic Energy Agency. Vienna, 2016.
2. IAEA Safety Standards Series No. SSG-48. Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2018 65 p.
3. 10 CFR Part 54. Requirements for Renewal of Operating Licenses for Nuclear Power Plants.
4. NEI 95-10. Industry Guidelines for Implementing the Requirements of 10 CFR 54 – The License Renewal Rule, Revision 6. Washington: Nuclear Energy Institute, June 2005.
5. IAEA Safety Standards Series. Specific Safety Guide No. SSG-25. Periodic Safety Review for Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2013, 106 p.
6. NRG-report NRG-22701/10.103460. Conceptual document LTO «Bewijsvoering» KCB. 9 September 2011.
7. Safety Reports Series No. 82. Ageing Management for Nuclear Power Plants: International Generic Ageing Lessons Learned (IGALL). International Atomic Energy Agency. Vienna, 2015, 87 p.
8. SSMFS 2008:17. The Swedish Radiation Safety Authority’s Regulations Concerning the Design and Construction of Nuclear Power Reactors.
9. NUREG-1801. Generic Aging Lessons Learned (GALL) Report, Rev. 2. Office of Nuclear Reactor Regulation, 2010.
10. IAEA Safety Standards Series No NS-G-2.12. Ageing Management for Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2009, 48 p.
11. 10 CFR Part 50. Domestic Licensing of Production and Utilization Facilities.
12. NEI 95-10, Revision 6. Industry Guidelines for Implementing the Requirements of 10 CFR 54 – The License Renewal Rule. Nuclear Energy Institute, June 2005.
13. NUREG-1800. Rev. 2. Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. Office of Nuclear Reactor Regulation, 2010.
14. Instrucción IS-22 Sobre Gestión del Envejecimiento y Operación a Largo Plazo de Centrales Nucleares. Consejo de Seguridad Nuclear, 2009.
15. Guía de Seguridad 1.10 (Rev. 1). Revisiones Periódicas de la Seguridad de las Centrales Nucleares. Madrid, Consejo de Seguridad Nuclear, 2008.
16. IAEA Safety Reports Series No. 57. Safe Long Term Operation of Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2008, 33 p.
17. Decree No. 162. Requirements for Safety Assessment pursuant to the Atomic Act. 2017.
18. Guide YVL A.8/20. Ageing Management of a Nuclear Facility. Radiation and Nuclear Safety Authority (STUK). May 2014.
19. HAEA Guideline 1.28 Regulatory Process of the License Renewal. Budapest, 2013.
20. HAEA Guideline 4.14. Version 2. Activities to be Implemented by the Operator to Support the License Application for Operation beyond Design Lifetime. Budapest, 2013.
21. NP 306.2.210-2017. General Requirements for Aging Management of Elements and Structures and Long-Term Operation of Nuclear Power Plants..
22. SOU-N NAEK 080:2014. Operation of the Technological Complex. Long-term Operation of NPP Power Units. General Provisions.
23. SOU-N NAEK 141:2017. Engineering, Scientific and Technical Support. Aging Management of Elements and Structures of the NPP Power Unit. General Requirements.
24. PNAE G-7-002-86. Standards for Strength Calculations of NPP Equipment And Piping. Energoatomizdat, 1989.
25. RD EO 0606-2005. Method for Brittle Fracture Resistance Calculating of NPP Reactor Vessels with VVER (MRKR-SKhR).
26. TAREG 2.01/00. Justification of Neutron Embrittlement Degree of WWER-1000 and WWER-440/213 RPVs in order to Assess their Integrity. Technical Report No. TAREG2.01-00 / SC-31.0260 / DIA / R / TR / 08 01 001–01. Reassessment of Reactor Witness Samples Database (WWER-1000 & WWER-440/213). Part 2: VVER-440/213 (final version). RRC Kurchatov Institute, Moscow, 2008.
27. Report No. 09-09-4928. Report on the Implementation of the State Review on Nuclear and Radiation Safety of the Decision to Extend the Operation Life of the Reactor Pressure Vessel of Power Unit No. 1 of Rivne NPP with Supporting Materials.
28. U213-R-1921. Reactor Pressure Vessel. Calculation of Brittle Fracture Resistance. Power Unit No. 1 of Rivne NPP.
29. Report on the implementation of research work. Analysis of WWER-1000/320 Containment and Tendons under Design-Basis and Beyond Design-Basis Accidents. Determination of the Minimum Allowed Tension of Tendons in the Containment Prestressing System Considering the new Seismic Level under a Combination of Design-Basis Accident and Operating-Basis Earthquake. (Task 24 of the Agreement 257586 dated March 29, 2016, stage 1)». Kyiv, 2019, 126 p.
30. 1087-12-03.00-PR. Report on the Results of Elements and Structures of the Localizing Safety System of the Containment System Verification Calculations for Power Unit No. 3 of the Rivne NPP. LLC «Fundamentstroymaks», Dnepropetrovsk, 2014.
31. 190-130-R-18. On the Life-Time Extension of the Structures of the Containment System of the Confining Safety System of Power Unit No. 3 of the Rivne NPP.
32. Technical Report. Analytical Recommendations Study and Acting Time Limited Aging Analysis (TLAA) Experience. (Under the Service Agreement No. 01/051-20 between SSTC NRS and Techneo Global LLC).
33. Shugailo O., Grebenyuk Yu., Zeleny O., Ryzhov D., Shugailo Ol-r., Brick D., Cherniak Ya. (2020). Experience Gained and Lessons Learned on Transition of Ukrainian NPPs Power Units to Long-Term Operation Activity. Nuclear and Radiation Safety, 1 (85), 15 - 28. doi: 10.32918 / nrs.2020.1 (85).02.
2. IAEA Safety Standards Series No. SSG-48. Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2018 65 p.
3. 10 CFR Part 54. Requirements for Renewal of Operating Licenses for Nuclear Power Plants.
4. NEI 95-10. Industry Guidelines for Implementing the Requirements of 10 CFR 54 – The License Renewal Rule, Revision 6. Washington: Nuclear Energy Institute, June 2005.
5. IAEA Safety Standards Series. Specific Safety Guide No. SSG-25. Periodic Safety Review for Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2013, 106 p.
6. NRG-report NRG-22701/10.103460. Conceptual document LTO «Bewijsvoering» KCB. 9 September 2011.
7. Safety Reports Series No. 82. Ageing Management for Nuclear Power Plants: International Generic Ageing Lessons Learned (IGALL). International Atomic Energy Agency. Vienna, 2015, 87 p.
8. SSMFS 2008:17. The Swedish Radiation Safety Authority’s Regulations Concerning the Design and Construction of Nuclear Power Reactors.
9. NUREG-1801. Generic Aging Lessons Learned (GALL) Report, Rev. 2. Office of Nuclear Reactor Regulation, 2010.
10. IAEA Safety Standards Series No NS-G-2.12. Ageing Management for Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2009, 48 p.
11. 10 CFR Part 50. Domestic Licensing of Production and Utilization Facilities.
12. NEI 95-10, Revision 6. Industry Guidelines for Implementing the Requirements of 10 CFR 54 – The License Renewal Rule. Nuclear Energy Institute, June 2005.
13. NUREG-1800. Rev. 2. Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. Office of Nuclear Reactor Regulation, 2010.
14. Instrucción IS-22 Sobre Gestión del Envejecimiento y Operación a Largo Plazo de Centrales Nucleares. Consejo de Seguridad Nuclear, 2009.
15. Guía de Seguridad 1.10 (Rev. 1). Revisiones Periódicas de la Seguridad de las Centrales Nucleares. Madrid, Consejo de Seguridad Nuclear, 2008.
16. IAEA Safety Reports Series No. 57. Safe Long Term Operation of Nuclear Power Plants. International Atomic Energy Agency. Vienna, 2008, 33 p.
17. Decree No. 162. Requirements for Safety Assessment pursuant to the Atomic Act. 2017.
18. Guide YVL A.8/20. Ageing Management of a Nuclear Facility. Radiation and Nuclear Safety Authority (STUK). May 2014.
19. HAEA Guideline 1.28 Regulatory Process of the License Renewal. Budapest, 2013.
20. HAEA Guideline 4.14. Version 2. Activities to be Implemented by the Operator to Support the License Application for Operation beyond Design Lifetime. Budapest, 2013.
21. NP 306.2.210-2017. General Requirements for Aging Management of Elements and Structures and Long-Term Operation of Nuclear Power Plants..
22. SOU-N NAEK 080:2014. Operation of the Technological Complex. Long-term Operation of NPP Power Units. General Provisions.
23. SOU-N NAEK 141:2017. Engineering, Scientific and Technical Support. Aging Management of Elements and Structures of the NPP Power Unit. General Requirements.
24. PNAE G-7-002-86. Standards for Strength Calculations of NPP Equipment And Piping. Energoatomizdat, 1989.
25. RD EO 0606-2005. Method for Brittle Fracture Resistance Calculating of NPP Reactor Vessels with VVER (MRKR-SKhR).
26. TAREG 2.01/00. Justification of Neutron Embrittlement Degree of WWER-1000 and WWER-440/213 RPVs in order to Assess their Integrity. Technical Report No. TAREG2.01-00 / SC-31.0260 / DIA / R / TR / 08 01 001–01. Reassessment of Reactor Witness Samples Database (WWER-1000 & WWER-440/213). Part 2: VVER-440/213 (final version). RRC Kurchatov Institute, Moscow, 2008.
27. Report No. 09-09-4928. Report on the Implementation of the State Review on Nuclear and Radiation Safety of the Decision to Extend the Operation Life of the Reactor Pressure Vessel of Power Unit No. 1 of Rivne NPP with Supporting Materials.
28. U213-R-1921. Reactor Pressure Vessel. Calculation of Brittle Fracture Resistance. Power Unit No. 1 of Rivne NPP.
29. Report on the implementation of research work. Analysis of WWER-1000/320 Containment and Tendons under Design-Basis and Beyond Design-Basis Accidents. Determination of the Minimum Allowed Tension of Tendons in the Containment Prestressing System Considering the new Seismic Level under a Combination of Design-Basis Accident and Operating-Basis Earthquake. (Task 24 of the Agreement 257586 dated March 29, 2016, stage 1)». Kyiv, 2019, 126 p.
30. 1087-12-03.00-PR. Report on the Results of Elements and Structures of the Localizing Safety System of the Containment System Verification Calculations for Power Unit No. 3 of the Rivne NPP. LLC «Fundamentstroymaks», Dnepropetrovsk, 2014.
31. 190-130-R-18. On the Life-Time Extension of the Structures of the Containment System of the Confining Safety System of Power Unit No. 3 of the Rivne NPP.
32. Technical Report. Analytical Recommendations Study and Acting Time Limited Aging Analysis (TLAA) Experience. (Under the Service Agreement No. 01/051-20 between SSTC NRS and Techneo Global LLC).
33. Shugailo O., Grebenyuk Yu., Zeleny O., Ryzhov D., Shugailo Ol-r., Brick D., Cherniak Ya. (2020). Experience Gained and Lessons Learned on Transition of Ukrainian NPPs Power Units to Long-Term Operation Activity. Nuclear and Radiation Safety, 1 (85), 15 - 28. doi: 10.32918 / nrs.2020.1 (85).02.
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