PRA (probabilistic risk assessment) applications program for inspection at Calvert Cliffs Unit 1 Nuclear Power Plant

Technical Report · Thu Jun 01 04:00:00 EDT 1989

DOI:https://doi.org/10.2172/5910160· OSTI ID:5910160

Vo, T. V.; Harris, M. S.; Gore, B. F.

The level one probabilistic risk assessment (PRA) for Calvert Cliffs Unit 1 (CC-1) has been analyzed to identify plant systems and components important to minimizing public risk, as measured by system contributions to plant core melt frequency, and to identify the primary failure modes of these components. This information has been tabulated and correlated with inspection modules from the NRC Inspection and Enforcement Manual. The report presents a series of tables, organized by system and prioritized by risk importance, which identify components associated with 98% of the inspectable risk due to plant operation. The systems addressed, in descending order of risk importance, are: reactor protection, auxiliary feedwater, dc power, ac power, power conversion, high pressure injection, room cooling, salt water, safety relief valves, and chemical volume and control. This ranking is based on the Fussel-Vesely measure of risk importance, i.e., the fraction of the total core melt frequency which involves failures of the system of interest. 10 refs., 20 figs., 36 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Radiation Protection and Emergency Preparedness; Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5910160
• Report Number(s): NUREG/CR-5187; PNL-6574; ON: TI89015502
• Country of Publication: United States
• Language: English

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ACCIDENTS
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