Lessons Learned from the Fukushima Nuclear Accident for Improving Safety of U.S. Nuclear Plants (2014) / Chapter Skim
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Appendix I: Probabilistic Risk Assessment
Appendix I: Probabilistic Risk Assessment
Pages 349-355
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From page 349... ...
nuclear plants I.1 RISK ASSESSMENT Numerous definitions exist on the meaning of risk and risk assessment. A working definition of risk is the "set of triplets" definition (Kaplan and Garrick, 1981)
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From page 350... ...
In practice, these can be assembled into a variety of forms to represent the risk of the system being evaluated. I.2 PROBABILISTIC RISK ASSESSMENT PRA is a process of probabilistic evidential and inferential analysis of the response of events, systems, or activities to different challenges based on the fundamental rules of logic and plausible reasoning.
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From page 351... ...
and introduce additional measures to ensure safety if the result of the PRA suggested that it was appropriate to do so. The Nuclear Power Engineering Corporation and the Japanese Nuclear Energy Safety Organization (JNES)
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From page 352... ...
to study a method to assess the characteristics of tsunamis for nuclear plant design in Japan. In response, the JSCE published "Tsunami Assessment Method for Nuclear Power Plants in Japan" in 2002.2 The paper proposed a deterministic method for evaluating tsunami hazards.
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From page 353... ...
The private sector and academia perform research relating to the science of PRA, with the private sector's contributions pertaining mainly to reactor design. TEPCO's PRA expertise resides in the technical specification groups at its plants, which are responsible for onsite risk management.
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From page 354... ...
PRAs have become increasingly important in developing risk-informed information to support license amendments. They are also used to update a plant's technical specifications and the safety parameter displays in the 4 Licenses, Certifications, and Approvals for Nuclear Power Plants.
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From page 355... ...
The use of plant-specific PRAs in training varies from plant to plant; operators in many plants are now being trained on plant-specific simulators using actual accident sequences derived from that plant's PRA. The USNRC has developed independent risk models for each nuclear plant under the Standardized Plant Analysis Risk (SPAR)
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