Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Development of an Accident Sequence Precursor Methodology and its Application to Significant Accident Precursors

  • Jang, Seunghyun (Department of Nuclear Engineering, Hanyang University) ;
  • Park, Sunghyun (Department of Nuclear Engineering, Hanyang University) ;
  • Jae, Moosung (Department of Nuclear Engineering, Hanyang University)
  • Received : 2016.12.07
  • Accepted : 2017.01.13
  • Published : 2017.04.25
Download PDF
⟨ Previous Next ⟩

Abstract

The systematic management of plant risk is crucial for enhancing the safety of nuclear power plants and for designing new nuclear power plants. Accident sequence precursor (ASP) analysis may be able to provide risk significance of operational experience by using probabilistic risk assessment to evaluate an operational event quantitatively in terms of its impact on core damage. In this study, an ASP methodology for two operation mode, full power and low power/shutdown operation, has been developed and applied to significant accident precursors that may occur during the operation of nuclear power plants. Two operational events, loss of feedwater and steam generator tube rupture, are identified as ASPs. Therefore, the ASP methodology developed in this study may contribute to identifying plant risk significance as well as to enhancing the safety of nuclear power plants by applying this methodology systematically.

Keywords

References

  1. D. Markberry, C. Hunter, G. DeMoss, U.S. Nuclear Regulatory Commission Accidents Sequence Precursor (ASP) Program Summary Description, Washington, DC, 2008.
  2. U.S. Nuclear Regulatory Commission, Reactor Safety Study: An Assessment of Accident Risksin U.S. Commercial Nuclear Power Plants, WASH-1400 (NUREG-75/014), Washington, DC, 1975.
  3. W. Minarick, C.A. Kukielka, Union Carbide Corp., Nuclear Div., Oak Ridge Natl. Lab., and Science Applications, Inc., Precursors to Potential Severe Core Damage Accidents: 1969-1979, A Status Report, NUREG/CR-2497, Vols. 1 and 2 (ORNL/NSIC-18/V1 and V2), Washington, DC, 1982.
  4. W.B. Cottrell, J.W. Minarick, P.N. Austin, E.W. Hagen, and J.D. Harris, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab., and Science Applications International Corp., Precursors to Potential Severe Core Damage Accidents: 1980-1981, A Status Report, NUREG/CR-3591, Vols. 1 and 2 (ORNL/NSIC-217/V1 and V2), Washington, DC, 1984.
  5. R.J. Belles, J.W. Cletcher, D.A. Copinger, B.W. Dolan, J.W. Minarick, M.D. Muhlheim, Precursors to Potential Severe Core Damage Accidents: 1998, A Status Report, NUREG/CR-4674 (ORNL/NOAC-232, Vol. 27), Washington, DC, 2000.
  6. D. Lochbaum, Accident Sequence Precursors for Nuclear Reactors, Union of Concerned Scientists: Nuclear Energy Activist Toolkit [Internet]. 2015. Available from: http://allthingsnuclear.org/dlochbaum/accident-sequence-precursors-for-nuclear-reactors [cited: Feb 10, 2015].
  7. U.S. Nuclear Regulatory Commission, Status of the Accident Sequence Precursor (ASP) Program and the Development of Standardized Plant Analysis Risk (SPAR) Model, SECY-15-0124, Washington, DC, 2015.
  8. M. Hulsmans, P. De Gelder, Probabilistic analysis of accident precursors in the nuclear industry, J. Hazard. Mater. 111 (2004) 81-87. https://doi.org/10.1016/j.jhazmat.2004.02.029
  9. T. Uchida, H. Takahashi, M. Fukuda, M. Sugawara, Accident Sequence Precursor Analysis at INS/NUPEC, NEA/CSNI/R (2003) 11, Nuclear Energy Agency of the OECD (NEA), 2003.
  10. International Atomic Energy Agency, Use of Plant Specific PSA to Evaluate Incidents at Nuclear Power Plants, IAEA-TECDOC-611, International Atomic Energy Agency (IAEA), 1991.
  11. R.B. Solanki, S.K. Gupta, Application of PSA Based Operational Event Analysis to Indian Nuclear Power Plants, 2010 2nd International Conference on Reliability, Safety and Hazard - Risk-Based Technologies and Physics-of-Failure Methods (ICRESH-2010), Mumbai, 2010.
  12. R. Beutler, G. Schoen, R. Schulz, K. Theiss, I.S. Kim, A. Perez-Mulas, M. Khatib-Rahbar, Risk-Based Analysis of Operational Events for Swiss Nuclear Power Plants, NEA/CSNI/R (2003) 11, Nuclear Energy Agency of the OECD (NEA), 2003.
  13. M.B. Sattison, T.A. Thatcher, J.K. Knudsen, J.A. Schroeder, N.O. Siu, Advanced Accident Sequence Precursor Analysis Level 1 Models, NUREG/CP-0149 Vol. 2, Washington, DC, 1996.
  14. Korea Hydro & Nuclear Power, Ulchin Units 5&6 Final Probabilistic Safety Assessment Report, KHNP, Korea, 2002.
  15. Korea Institute of Nuclear Safety, 2002-2003 Operational Aspects of Nuclear Power Plants in Korea, KINS/ER-035 Vol. 3, 4, KINS, Korea, 2003-2004.
  16. Korea Institute of Nuclear Safety, 2004-2014 Safety and Operational Status of Nuclear Power Plants in Korea, KINS/ER-035 Vol. 5-15, KINS, Korea, 2005-2015.
  17. KEPCO Engineering & Construction company, Inc., SAREX User Manual Version 1.2, KEPCO-ENC, Korea, 2011.

Cited by

  1. Limitations of traditional tools for beyond design basis external hazard PRA vol.370, pp.None, 2020, https://doi.org/10.1016/j.nucengdes.2020.110899