Methodology and application of surrogate plant PRA analysis to the Rancho Seco Power Plant: Final report

Technical Report · Wed Jul 01 04:00:00 EDT 1987

DOI:https://doi.org/10.2172/6433631· OSTI ID:6433631

Gore, B F; Huenefeld, J C

This report presents the development and the first application of generic probabilistic risk assessment (PRA) information for identifying systems and components important to public risk at nuclear power plants lacking plant-specific PRAs. A methodology is presented for using the results of PRAs for similar (surrogate) plants, along with plant-specific information about the plant of interest and the surrogate plants, to infer important failure modes for systems of the plant of interest. This methodology, and the rationale on which it is based, is presented in the context of its application to the Rancho Seco plant. The Rancho Seco plant has been analyzed using PRA information from two surrogate plants. This analysis has been used to guide development of considerable plant-specific information about Rancho Seco systems and components important to minimizing public risk, which is also presented herein.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Safety and Projects
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6433631
• Report Number(s): NUREG/CR-4768-Vol.2; PNL-6032-2; ON: TI87012740
• Country of Publication: United States
• Language: English

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