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Technical Paper

Formulation of a Single Operational Model for Risk-Informed Applications from the Decoupled Levels 1 and 2 PSA Models

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Pages 155-169 | Published online: 10 Apr 2017

References

  • “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Regulatory Guide 1.174, U.S. Nuclear Regulatory Commission (Jan. 1998).
  • M. A. CARUSO et al., “An Approach for Using Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Reliab. Eng. Syst. Safe., 63, 231 (1999).
  • I. B. WALL, J. J. HAUGH, and D. H. WORLEGE, “Recent Applications of PSA for Managing Nuclear Power Plant Safety,” Prog. Nucl. Energy, 30, 3-4, 367 (2001).
  • “Severe Accident Risks: AnAssessment for Five U.S. Nuclear Power Plants,” NUREG-1150, Vols. 1 and 2, U.S. Nuclear Regulatory Commission (Dec. 1990).
  • “PSA Applications Guide,” EPRI TR-105396, Electric Power Research Institute (Aug. 1995).
  • S. HIRSCHBERG, “Prospects for Probabilistic Safety Assessment,” Nucl. Saf., 33, 3, 365 (1992).
  • M. RICHNER, S. ZIMMERMANN, and D. J. WAKEFIELD, “Integrated Level 1/Level 2 PSA Models and Release Frequency Importance,” Proc. 6th Int. Conf. Probabilistic Safety Assessment and Management (PSAM 6), San Juan, Puerto Rico, June 20-23, 2002.
  • R. HIMANEN and H. SJOVALL, “An Integrated Approach to Living Level 2 PSA,” Proc. 6th Int. Conf. Probabilistic Safety Assessment and Management (PSAM 6), San Juan, Puerto Rico, June 20-23, 2002.
  • “Ulchin Units 3&4 Final Level 1 Probability Safety Assessment,” Korea Electric Power Company (1995).
  • “Ulchin 3 & 4 Full Scope Level 2 PSA,” Korea Electric Power Company (Aug. 1996).
  • P. J. FULFORD, R. R. SHERRY, D. M. BUCHEIT, and Y. C. CHOU, “Computerizing the Level 2 PSA/PRA,” IAEA-SM-321/20, pp. 233–243, International Atomic Energy Agency (June 1991).
  • K. I. AHN et al., “Development of a Computer Code, CONPAS, for an Integrated Level 2 PSA,” J. Korean Nucl. Soc., 30, 1, 58 (Feb. 1998).
  • M. KHATIB-RAHBAR,A. S. KURITZKY, R. VIJAYKUMAR,E. G. CAZZOLI, U. SCHMOCKER, and W. WERNER, “Insights and Comparisons of the Level 2 Results of Recent Probabilistic Safety Analyses,” Nucl. Eng. Des., 162,175 (1996).
  • K. I. AHN et al., “A Comparative Assessment of the Current Containment Event Tree Methodologies,” J. Korean Nucl. Soc., 26, 4, 611 (Dec. 1994).
  • W. T. PRATT, V. MUBAYI, H. NOURBAKHSH, T. BROWN, and J. GREGORY, “An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events,” NUREG/CR-6595, BNL-NUREG-52539, Brookhaven National Laboratory (1999).
  • “Generic Framework for IPE Back-End (Level 2) Analysis, Volume 2: PWR Implementation Guidelines,” NSAC-159, Nuclear SafetyAnalysis Center (Oct. 1991).
  • R. SUMMITT, “Response Surface Approach for Level 2 Analysis,” Proc. Int. Topl. Mtg. Probabilistic Safety Assessment (PSA ’96), Park City, Utah, September 29-October 3, 1996, p. 1143, American Nuclear Society (1996).
  • S. KAPLAN, “Matrix Theory Formalism for Event Tree Analysis: Application to Nuclear Risk Analysis,” RiskAnal., 2, 9 (1981).
  • E. D. GORHAM et al., “Evaluation of Severe Accident Risks: Methodology for the Containment, Source Term, Consequence, and Risk Integration Analyses,” NUREG/CR-4551, SAND86-1309, Vol. 1, Rev. 1, Sandia National Laboratories (Dec. 1993).
  • M. C. CHEOK, G. W. PARRY, and R. R. SHERRY, “Use of Importance Measures in Risk-Informed Regulatory Applications,” Reliab. Eng. Syst. Safe., 60, 213 (1998).
  • K.-I. AHN and Y.-H. JIN, “A Formal Approach for Quantitative Treatment of Modeling Uncertainties in Safety Analysis,” Nucl. Technol., 116, 146 (1996).
  • K. I. AHN, J. E. YANG, and J. J. HA, “A Formal Guidance for Handling Different Uncertainty Sources Employed in the Level 2 PSA,” J. Korean Nucl. Soc., 36, 1, 83 (Feb. 2004).
  • S. H. HAN et al., “KIRAP Release 2.0 User’s Manual,” KAERI/TR-361/93, Korea Atomic Energy Research Institute (1993).
  • W. S. JUNG, J. E. YANG, and J. J. HA, “A New Method to Evaluate Alternate AC Power Source Effects in Multi-Unit Nuclear Power Plants,” Reliab. Eng. Syst. Safe., 82, 2, 165 (2003).
  • C. L. SMITH, S. T. WOOD, K. J. KVARFORDT, P. H. McCABE, R. D. FOWLER, C. L. HOFFMAN, K. D. RUSSELL, and E. LOIS, “Testing, Verifying, and Validating SAPHIRE Versions 6.0 and 7.0,” NUREG/CR-6688, pp. 3334, U.S. Nuclear Regulatory Commission (Sep. 2000).

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