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PSA Application on the Tokai Reprocessing Plant

  • Michihiko Ishida
  • Takafumi Nakano
  • Kazuyuki Morimoto
  • Ichiro Nojiri

Abstract

Probabilistic Safety Assessment (PSA) methodology has been applied on the Tokai Reprocessing Plant (TRP) to evaluate relative importance of safety functions that prevent the progress of events causing to postulated accidents.

Based on results of safety reassessments of the TRP that was carried out in 1999, event trees were developed to model sequences of postulated accidents. Event trees were quantified by using the results of fault tree analysis and human reliability analysis. In the quantification, the reliability data generally used in PSA of nuclear power plants were mainly used. Operating experiences of the TRP were also utilized to evaluate both component/system reliability and human reliability.

The relative importance of safety functions was evaluated by using two major importance measures, Fussell-Vesely and Risk Achievement Worth both generally used in PSA of nuclear power plants.

Through these evaluations, some useful insights into the safety of the TRP have been obtained. The results of the relative importance measures would be utilized to qualify component/equipment as important safety function.

Keywords

Nuclear Power Plant Importance Measure Fault Tree Analysis Safety Function Probabilistic Safety Assessment 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    H. Nakamura et al, “Safety Evaluation of Tokai Reprocessing Plant (TRP) — Report of Safety evaluation of Tokai Reprocessing Plant-” JNC TN8440 99-002, (1999).Google Scholar
  2. 2.
    USNRC, “PRA Procedures Guide — A Guide to the Performance of Probabilistic Risk Assessment for Nuclear Power Plant”, NUREG-2300, (1982).Google Scholar
  3. 3.
    INTERNATIONAL ATOMIC ENERGY AGENCY, “Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities.” IAEA-TECDOC-1267, (2002).Google Scholar
  4. 4.
    A.D. Swain and H.E. Guttmann, “Handbook of Human-Reliability Analysis with Emphasis on Nuclear Power Plant Applications, Final Report”, NUREG/CR-1278, (1983)Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Michihiko Ishida
    • 1
  • Takafumi Nakano
    • 1
  • Kazuyuki Morimoto
    • 1
  • Ichiro Nojiri
    • 1
  1. 1.Tokai Reprocessing Center, Tokai WorksJapan Nuclear Cycle Development Institute(JNC)Tokai-MuraJapan

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