DOI QR코드

DOI QR Code

Development of a regulatory framework for risk-informed decision making

  • Received : 2019.03.27
  • Accepted : 2019.06.30
  • Published : 2020.01.25

Abstract

After the Fukushima Daiichi accidents, public concerns on nuclear safety and the corresponding burden of nuclear power plant licensees are increasing. In order to secure public trust and enhance the rationality of current safety regulation, we develop a risk-informed decision making (RIDM) framework for the Korean regulatory body. By analyzing all the regulatory activities for nuclear power plants in Korea, eight action items are selected for RIDM implementation, with appropriate procedures developed for each. For two items in particular - the accident sequence precursor analysis (ASPA) and the significance determination process (SDP) - two customized risk evaluation software has been developed for field inspectors and probabilistic safety assessment experts, respectively. The effectiveness of the proposed RIDM framework is demonstrated by applying the ASPA procedure to 35 unplanned scrams and the SDP to 24 findings from periodic inspections.

Keywords

References

  1. IAEA, Risk Informed Regulation of Nuclear Facilities: Overview of the Current Status, 2005. TECDOC-1436.
  2. US Nuclear Regulatory Commission, Achieving Modern Risk-Informed Regulation, 2018. SECY-18-0060.
  3. G. Saji, Safety goals in risk-informed, performance-based regulation, Reliab. Eng. Syst. Saf. 80 (2003) 163-172. https://doi.org/10.1016/S0951-8320(03)00026-7
  4. M. Yamamoto, Preparation status for the pilot program of the new nuclear regulatory inspection, in: OECD/NEA Workshop for the Introduction of ROP, 2018. June 21.
  5. Korea Institute of Nuclear Safety, Policy Report for Risk-Informed Regulation, September 2010. KINS/AR-911.
  6. Korea Institute of Nuclear Safety, Technical Guidelines on General Requirements for Risk-Informed Application for Amendment on Reactor Facilities, 2007. KINS/GT-N24.
  7. US Nuclear Regulatory Commission, An approach for plant-specific, riskinformed decisionmaking: technical specifications, Regul. Guide 1 (177) (1998).
  8. US Nuclear Regulatory Commission, An approach for plant-specific risk-informed decisionmaking for inservice inspection of piping, Regul. Guide 1 (178) (1998).
  9. Korea Institute of Nuclear Safety, Establishment of Implementation Program for Graded Regulation Using Risk and Performance Information, 2011, 2011-0002049.
  10. Y. J. Lee, H. S. Kim and T. W. Kim, "PSA lessons learned from maintenance rule," in Transactions of the Korean Nuclear Society Autumn Meeting, October 2005.
  11. Ministry of Science and Technology, Nuclear Safety Policy Statement, September 1994.
  12. US Nuclear Regulatory Commission, Risk-Informed Regulation Implementation Plan, 2001. SECY-01-0218.
  13. Korea Institute of Nuclear Safety, Development of Regulatory PSA Model Utilization Framework, 2018. KINS/GR-628.
  14. US Nuclear Regulatory Commission, Risk Assessment Review Group Report to the U.S. Nuclear Regulatory Commission, 1978. NUREG/CR-0400.
  15. US Nuclear Regulatory Commission, NRC INSPECTION MANUAL Chapter 0609, SIGNIFICANCE DETERMINATION PROCESS, 2015.
  16. US Nuclear Regulatory Commission, Risk Assessment of Operational Events Handbook - Volume 1 - Internal Events Revision 2.0, 2013.
  17. Korea Atomic Energy Research Institute, Development of Basic Regulatory Framework for APR1400 Level 1 PSA, 2018. KAERI/RR-4383.
  18. S.H. Han, H.G. Lim, S.C. Jang, J.E. Yang, AIMS-psa: a software for integrated PSA, in: 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), October 2016.
  19. B.O.Y. Lydell, Retrospective review of experience with using the NUPRA software, Reliab. Eng. Syst. Saf. 30 (1990) 339-353. https://doi.org/10.1016/0951-8320(90)90103-T
  20. D. Wakefield, S. Epstein, Y. Xiong, K. Nouri, RISKMAN(R), celebrating 20+ years of excellence!, in: International Conference on Probabilistic Safety Assessment and Management (PSAM2010), April 2010.
  21. US Nuclear Regulatory Commission, Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Vol. 1 Summary Manual, vol. 1, 2008. NUREG/CR-6952.
  22. W.S. Jung, S.H. Han, J.J. Ha, Advanced features of the fault tree solver FTREX, in: Korean Nuclear Society Conference, 2005.