Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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DEVELOPMENT OF AN INTEGRATED RISK ASSESSMENT FRAMEWORK FOR INTERNAL/EXTERNAL EVENTS AND ALL POWER MODES

  • Yang, Joon-Eon (Integrated Safety Assessment Division Korea Atomic Energy Research Institute)
  • Received : 2012.05.08
  • Published : 2012.06.25
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Abstract

From the PSA point of view, the Fukushima accident of Japan in 2011 reveals some issues to be re-considered and/or improved in the PSA such as the limited scope of the PSA, site risk, etc. KAERI (Korea Atomic Energy Research Institute) has performed researches on the development of an integrated risk assessment framework related to some issues arisen after the Fukushima accident. This framework can cover the internal PSA model and external PSA models (fire, flooding, and seismic PSA models) in the full power and the low power-shutdown modes. This framework also integrates level 1, 2 and 3 PSA to quantify the risk of nuclear facilities more efficiently and consistently. We expect that this framework will be helpful to resolve the issue regarding the limited scope of PSA and to reduce some inconsistencies that might exist between (1) the internal and external PSA, and (2) full power mode PSA and low power-shutdown PSA models. In addition, KAERI is starting researches related to the extreme external events, the risk assessment of spent fuel pool, and the site risk. These emerging issues will be incorporated into the integrated risk assessment framework. In this paper the integrated risk assessment framework and the research activities on the emerging issues are outlined.

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References

  1. OECD/NEA CSNI WGRISK, "Use and Development of Probabilistic Safety Assessment," NEA/CSNI/R (2007)12, 2007
  2. U.S. NRC, Regulatory Guide 1.174, "An Approach for using Probabilistic Risk Assessment in risk Informed Decisions on Plant Specific Changes to the Licensing Basis," Revision 1
  3. G. Apostolakis, "A Regulator's Perspective on Nuclear Power Plant Safety for the Future," International Forum on Safe Nuclear Power Plants, Korea Advanced Institute of Science & Technology, Apr. 2012
  4. D.I. Kang, S.H. Han, K.Y. KIM, An approach to the construction of a one top fire event PSA model, Nuclear Engineering and Design, Volume 239, Pp, 2514-2520, 2009 https://doi.org/10.1016/j.nucengdes.2009.07.026
  5. W.S. Jung, Y.H. LEE, J.E. YANG., Development of a new quantification method for a fire PSA, Reliability Engineering and System Safety, Volume 94, Pp, 1650-1657, 2009 https://doi.org/10.1016/j.ress.2009.04.004
  6. Woo Sik Jung, et al., "A fast BDD algorithm for large coherent fault tree analysis, Reliability Engineering and System Safety, Volume 83, Pp, 369-374, 2004 https://doi.org/10.1016/j.ress.2003.10.009
  7. Joon-Eon YANG, et al., "Development of A New Framework for the Integrated Risk Assessment of All Modes/All Hazards", Korean Nuclear Society 2009 Autumn Meeting, Gyeongju, Korea, 2009
  8. Sang Hoon HAN, et al., "Improved Features in a PSA Software AIMS-PSA", Korean Nuclear Society 2010 Spring Meeting, Pyeongchang, Korea, 2010
  9. Sang Hoon Han, et al., "PC Workstation-Based Level 1 PRA Code Package KIRAP," Reliability Eng. & Systems Safety 30, 313-322, 1990 https://doi.org/10.1016/0951-8320(90)90101-R
  10. Seok-Jung HAN, A Development of Interfacing System between Level 2 and Level 3 PSA for Integrated Analysis of Full Scope PSA, Korean Nuclear Society 2011 Autumn Meeting, Gyeongju, Korea, 2011
  11. Kwang Il Ahn and et.al., Development of a Computer Code, CONPAS, for an Integrated Level 2 PSA, Journal of the Korean Nuclear Society, Vol.30(1), pp58-74, 1998
  12. American National Standards Institute (ANSI), External Events in PRA Methodology, ANSI/ANS 58.21-2007, 2007.
  13. American Society of Mechanical Engineers (ASME), Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, AMSE/ANS RA-Sa-2009, 2009.
  14. US Nuclear Regulatory Commission, PRA Procedure Guide: A Guide to the performance of Probabilistic Risk Assessments for Nuclear Power Plants, NUREG/CR-2300, 1983.
  15. Jeong-Moon Seo, In-Kil Choi, and Hyun-Me Rhee, "A Study of the Historical Earthquake Catalog and Gutenberg- Richter Parameter Values of the Korean Peninsula, Nuclear Engineering and Technology, Vol. 42, No. 1, 2010
  16. Min-Kyu Kim and In-Kil Choi, "A tsunami PSA methodology and application for NPP site in Korea" Nuclear Engineering and Design, V.244, 2012.
  17. In-Kil Choi1, Young-SunChoun, MinKyu Kim, JinsuoNie, Joseph I. Braverman, and Charles H. Hofmayer, "Identification and Assessment of Aging-Related Degradation Occurrences in Nuclear Power Plants" Nuclear Engineering and Technology, V.44, No. 3, 2012. (SCIE)
  18. Committee on the Safety and Security of Commercial Spent Nuclear Fuel Storage, National Research Council, Safety and Security of Commercial Spent Nuclear Fuel Storage: Public Report, published by National Academies, ISBN 0309096472, USA, 2006.
  19. Kwang Il Ahn, The Current State of the Arts on Safety Issues Related to SFP and Considerations for Regulation Improvement, KAERI/AR-885/2011, Korea Atomic Energy Research Institute (KAERI), March 2011 (in Korean).
  20. IAEA Safety Series No.118, Safety Assessment for Spent Fuel Storage Facilities, IAEA, Vienna, 1994.
  21. T.E. Collins and G. Hubbard, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants, NUREG-1738, U.S. Nuclear Regulatory Commission, January 2001.
  22. V.L. Sailer, K.R. Perkins, J.R. Weeks, and H.R. Connell, Severe Accidents in Spent Fuel Pools in Support of Generic Safety Issue 82, NUREG/CR-4982 and BNL-NUREG-52093. Brookhaven National Laboratory, Upton, N.Y., July 1987.
  23. Jeffrey Cardoni, MELCOR Model for an Experimental 17${\times}$17 Spent Fuel PWR Assembly, SAND2010-8249, November 2010.
  24. MAAP5-Modular Accident Analysis Program for LWR Power Plants, Fauske & Associates, Inc., November 2008.
  25. D. Chanin and M.I. Young, Code Manual for MACCS2, NUREG/CR-6613, SAND97-0594, Prepared for U.S. Nuclear Regulatory Commission, May 1998.
  26. U.S. NRC, "Second Status Paper on the Staff's Proposed Regulation Structure for New Plant Licensing and Update on Policy Issues Reacted to Nuclear Plant Licensing," SECY 05-0006, 2005.
  27. K. N. Flemming, "On the Issue of Integrated Risk - A PRA Practitioners Perspectives", Proceedings of the ANS International Topical Meeting on Probabilistic Safety Analysis, San Francisco, CA., USA, Sep. 11-15, 2005.
  28. PLG, Inc., "Seabrook Station Probabilistic Safety Assessment, Sec 13.3 Risk of Two Unit Station," PLG-0300, 1983.
  29. S. A. Arndt, Method and Strategies for Future Reactor Safety Goals, Ph.D. Thesis, The Ohio State University, 2010.
  30. T. Hakada, "Seismic PSA Method for Multiple Nuclear Power Plants in a Site," Reliability Engineering and System Safety, V.92, No.7, 2007, pp.883-894. https://doi.org/10.1016/j.ress.2006.04.022
  31. Development of the Integrated Risk Assessment Technology for Multiple Units, KAERI, Research Plan Report (FY2012-2015), 2012.