Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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THE APPLICATION OF PSA TECHNIQUES TO THE VITAL AREA IDENTIFICATION OF NUCLEAR POWER PLANTS

  • Published : 2005.06.01
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Abstract

This paper presents a vital area identification (VAI) method based on the current fault tree analysis (FTA) and probabilistic safety assessment (PSA) techniques for the physical protection of nuclear power plants. A structured framework of a top event prevention set analysis (TEPA) application to the VAI of nuclear power plants is also delineated. One of the important processes for physical protection in a nuclear power plant is VAI that is a process for identifying areas containing nuclear materials, structures, systems or components (SSCs) to be protected from sabotage, which could directly or indirectly lead to core damage and unacceptable radiological consequences. A software VIP (Vital area Identification Package based on the PSA method) is being developed by KAERI for the VAI of nuclear power plants. Furthermore, the KAERI fault tree solver FTREX (Fault Tree Reliability Evaluation eXpert) is specialized for the VIP to generate the candidates of the vital areas. FTREX can generate numerous MCSs for a huge fault tree with the lowest truncation limit and all possible prevention sets.

Keywords

References

  1. IAEA, 'Physical Protection of Nuclear Material and Nuclear Facilities,' INFCIRC/225/Rev. 4 (1998).
  2. C.K. Park, W.S. Jung, J.E. Yang, H.G. Kang, 'A PSA-based Vital Area Identification Methodology Development,' Reliability Engineering & System Safety, 82, 2, pp. 133-140, (2003). https://doi.org/10.1016/S0951-8320(03)00139-X
  3. C.K. Park, W.S. Jung, J.E. Yang, H.G. Kang, 'Development of a PSA-based Vital Area Identification Methodology for the Physical Security of Nuclear Power Plants,' Proceedings of the 7th International Conference on Probabilistic Safety Assessment and Management, Berlin, Germany, Jun. 12-19 (2004).
  4. N. Rasmussen, et aI., 'Reactor Safety Study: An Assessment of Accident Risk in U.S. Commercial Nuclear Plants,' WASH-1400, NUREG-75/014, U.S. Nuclear Regulatory Commission (1975).
  5. D.D. Boozer and R.B. Worrell, 'A Method for Determining the Susceptibility of a Facility to Sensor System Nullification by Insiders,' SAND77-1916C, Feb. (1978).
  6. G.B. Varnado and N.R. Ortiz, 'Fault Tree Analysis for Vital Area Identification,' NUREG/CR-0809, SAND79-0946, Sandia Labs., USA (1980).
  7. D.W. Stack and K.A. Francis, 'Vital Area Analysis Using SETS,' NUREG/CR-1487, SNAND80-1095, Sandia Labs., USA (1980).
  8. J.M. Boudreau and R.A. Haarman, 'Reactor Sabotage Vulnerability and Vital-equipment Identification,' LA-UR-82-2831, Los Alamos National Lab., USA (1982).
  9. T.F. Bott and W.S. Thomas, 'Reactor Vital Equipment Determination Techniques,' LA-UR-83-3026, Los Alamos National Lab., USA (1983).
  10. D.F. Cameron, 'Vital Areas at Nuclear Power Plants,' LA-UR-85-558, Los Alamos National Lab., USA (1985).
  11. P.Y. Pan and T.F. Bott, 'Vital Equipment Determination Techniques Research Study,' NUREG/CP-0058-Vol.6, USA (1985).
  12. F. Rahn, 'An Approach to Risk-Informed Physical Security, Electric Power Research Institute,' EPRI TR-113787, Oct. (1999).
  13. R.B. Worrell and D.P. Blanchard, 'Top event Prevention Analysis: A Deterministic Use of PRA,' International Conference on Probabilistic Safety Assessment Methodology and Application, Seoul, Korea, Nov. 26-30 (1995).
  14. D.P. Blanchard and B.A. Brogan, 'Identification of Risk-significant Circuit Breakers Using Top Event prevention Analysis,' International Topical Meeting on Probabilistic Safety Assessment, Park City, Utah, Sep. 29 - Oct. 3 (1996).
  15. D.P. Blanchard and R.B. Worrell, 'Top Event Prevention Analysis: A Method for Identifying Combinations of Events Important to Safety,' International Topical Meeting on Probabilistic Safety Assessment. Detroit, Michigan, Oct. 6-9 (2002).
  16. R.A. White and D.P. Blanchard, 'Development of A Risk-informed IST Program at Palisades Using Top Event Prevention,' Proceedings of ICONE10 10th International Conference on Nuclear Engineering, Arlington, VA, Apr. 14-18 (2002).
  17. W.S. Jung, S.H. Han, and J.J. Ha, 'A Fast BDD Algorithm for Large Coherent Fault Trees Analysis,' Reliability Engineering and System Safety, 83, pp. 369.374, (2004) https://doi.org/10.1016/j.ress.2003.10.009
  18. W.S. Jung, S.H. Han, and J.J. Ha, 'Development of an Efficient BDD Algorithm to Solve Large Fault Trees,' Proceedings of the 7th International Conference on Probabilistic Safety Assessment and Management, Berlin, Germany, Jun. 12-19 (2004)
  19. W.E. Vesely, F.F. Goldberg, N.H. Roberts, and D.F. Haasl, Fault Tree Handbook, NUREG-0492, U.S. Nuclear Regulatory Commission, Washington, DC (1981)
  20. W. Vesely, J. Dugan, J. Fragola, J. Minarick, and J. Railsback, Fault Tree Handbook with Aerospace Applications, National Aeronautics and Space Administration (2002)
  21. R.E. Barlow and F. Proschan, Statistical Theory of Reliability and Life Testing, Holt, Rinehart and Winston, Inc., (1975)
  22. S.H. Han, 'PC-Workstation Based Level 1 PRA Code Package-KIRAP,' Reliability Engineering and System Safety, 30, pp.313-322 (1990). https://doi.org/10.1016/0951-8320(90)90101-R
  23. W.S. Jung, J.E. Yang, and J.J. Ha, 'Development of measures to estimate truncation error in fault tree analysis,' Reliability Engineering & System Safety, in Press (2005)
  24. W.S. Jung, S.H. Han, and J.J. Ha, 'Development of an analytical method to break logical loops at the system level,' Reliability Engineering & System Safety, in Press(2005)