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Title: Risk-based inspection guide for Crystal River Unit 3 Nuclear Power Plant

Technical Report ·
OSTI ID:5746846

The Level 1 probabilistic risk assessment (PRA) for Crystal River Unit 3 (CR-3) has been analyzed to identify plant systems and components important to minimizing public risk, as measured by system contributions to plant core damage frequency, and to identify the primary failure modes for these components. 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 to risk importance are: Low Pressure Injection, AC Power, Service Water, Demineralized Water, High Pressure Injection, DC Power, Emergency Feedwater, Reactor Coolant Pressure Control, and Power Conversion. This ranking is based on the Fussell-Vesely measure of risk importance, i.e., the fraction of the total core damage frequency which involves failures of the system of interest. 3 refs., 9 figs., 13 tabs.

Research Organization:
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Radiation Protection and Emergency Preparedness; Pacific Northwest Lab., Richland, WA (USA)
Sponsoring Organization:
USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
5746846
Report Number(s):
NUREG/CR-5467; PNL-7108; ON: TI91014266
Country of Publication:
United States
Language:
English