Risk-Based Inspection Guide for Crystal River Unit 3 Nuclear Power Plant

Technical Report · Sat Jun 01 04:00:00 EDT 1991

DOI:https://doi.org/10.2172/5746846· OSTI ID:5746846

Smith, B. W. ^[1]; Dukelow, J. S. ^[1]; Vo, T. V. ^[1]; Harris, M. S. ^[1]; Gore, B. F. ^[1]; Hunt, S. T. ^[1]

---

1. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

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.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Reactor Regulation; Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USNRC; USDOE
• 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

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AUXILIARY SYSTEMS
BLACKOUTS
BOILERS
COOLING SYSTEMS
CRYSTAL RIVER-3 REACTOR
ECCS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
HIGH PRESSURE COOLANT INJECTION
LOSS OF COOLANT
LOW PRESSURE COOLANT INJECTION
POWER REACTORS
POWER SYSTEMS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
STEAM GENERATORS
SYSTEMS ANALYSIS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS