PRA (Probabilistic Risk Assessment) Applications Program for inspection at Oconee Unit 3

Technical Report · Thu Oct 01 00:00:00 EDT 1987

OSTI ID:5933447

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

The extensive Oconee-3 PRA performed by EPRI has been analyzed to identify plant systems and components important to minimizing public risk, 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 public risk (in person-rem per year), which identify components associated with 98% of the inspectable risk due to plant operation. External events (earthquakes, tornadoes, fires and floods) are not addressed because inspections cannot directly minimize the risks from these events; however, flooding caused by the breach of internal systems is addressed. The systems addressed, in descending order of risk importance, are: Reactor Building Spray, R B Cooling, Condenser Circulating Water, Safety Relief Valves, Low Pressure Injection, Standby Shutdown Facility-High Pressure Injection, Low-Pressure Service Water, and Emergency Feedwater. This ranking is based on the Fussel-Vesely measure of risk importance, i.e., the fraction of the total risk which involves failures of the system of interest. 8 refs., 25 tabs.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA); Nuclear Regulatory Commission, King of Prussia, PA (USA). Region I
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5933447
• Report Number(s): NUREG/CR-5006; ON: DE88001343
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
OCONEE-3 REACTOR
REACTOR SAFETY
RISK ASSESSMENT
ATWS
ENGINEERED SAFETY SYSTEMS
FAILURES
INSPECTION
LOSS OF COOLANT
PIPES
PROBABILISTIC ESTIMATION
PUMPS
TRANSIENTS
VALVES
ACCIDENTS
CONTROL EQUIPMENT
ENRICHED URANIUM REACTORS
EQUIPMENT
FLOW REGULATORS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled