Journal of the Korean Society of Safety (한국안전학회지)

The Korean Society of Safety (한국안전학회)
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Vital Area Identification Rule Development and Its Application for the Physical Protection of Nuclear Power Plants

원자력발전소의 물리적방호를 위한 핵심구역파악 규칙 개발 및 적용

  • Received : 2017.04.21
  • Accepted : 2017.05.18
  • Published : 2017.06.30
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Abstract

US national research laboratories developed the first Vital Area Identification (VAI) method for the physical protection of nuclear power plants that is based on Event Tree Analysis (ETA) and Fault Tree Analysis (FTA) techniques in 1970s. Then, Korea Atomic Energy Research Institute proposed advanced VAI method that takes advantage of fire and flooding Probabilistic Safety Assessment (PSA) results. In this study, in order to minimize the burden and difficulty of VAI, (1) a set of streamlined VAI rules were developed, and (2) this set of rules was applied to PSA fault tree and event tree at the initial stage of VAI process. This new rule-based VAI method is explained, and its efficiency and correctness are demonstrated throughout this paper. This new rule-based VAI method drastically reduces problem size by (1) performing PSA event tree simplification by applying VAI rules to the PSA event tree, (2) calculating preliminary prevention sets with event tree headings, (3) converting the shortest preliminary prevention set into a sabotage fault tree, and (4) performing usual VAI procedure. Since this new rule-based VAI method drastically reduces VAI problem size, it provides very quick and economical VAI procedure. In spite of an extremely reduced sabotage fault tree, this method generates identical vital areas to those by traditional VAI method. It is strongly recommended that this new rule-based VAI method be applied to the physical protection of nuclear power plants and other complex safety-critical systems such as chemical and military systems.

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References

  1. IAEA, Nuclear Security Series No. 13-Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities, INFICRC 225/Rev. 5, 2011.
  2. IAEA, Nuclear Security Series No. 16-Identification of Vital Areas at Nuclear Facilities, 2012.
  3. EPRI, Probabilistic Consequences Analysis of Security Threats-A Prototype Vulnerability Assessment Process for Nuclear Power Plants, 1007975, Final Report, 2004.
  4. G.B. Varnado and D.W. Whitehead, Vital Area identification for U.S. Nuclear Regulatory Commission Nuclear Power Reactor Licensees and New Reactor Applicants, SAND-5644. Sandia National Laboratories, 2008.
  5. C. K. Park, W. S. Jung, J. E. Yang and H.G. Kang, "A PSA-based Vital Area Identification Methodology", Reliability Engineering and System Safety, Vol. 2, No. 2, pp. 133-140, 2003.
  6. J.J. Ha, W.S. Jung and C.K. Park, "The Application of PSA Techniques to the Vital Area Identification of Nuclear Power Plants", Nuclear Engineering and Technology, Vol. 37, No. 3, pp. 259-264, 2005.
  7. W. S. Jung, Y. H. Lee and J. E. Yang, "Development of a New Quantification Method for a Fire PSA", Reliability Engineering and System Safety, Vol. 94, pp. 1650-1657, 2009. https://doi.org/10.1016/j.ress.2009.04.004
  8. Y. H. Lee, W. S. Jung, M. J. Hwang and J. E. Yang, "Vital Area Identification of Nuclear Facilities by using PSA", Journal of the Korean Society of Safety, Vol. 24, No. 5, pp.63-68, 2009.
  9. Y. H. Lee, W. S. Jung and J. H. Lee, "Vital Area Identification Analysis of A Hypothetical Nuclear Facility Using VIPEX", Journal of the Korean Society of Safety, Vol. 26, No. 4, pp.87-95, 2011.