Methodology and application of surrogate plant PRA analysis to the Rancho Seco Power Plant: Task 1, Analysis of ANO-1 and Oconee PRAs

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

OSTI ID:6439111

Gore, B F

This two-volume report presents the development and first application of a methodology for using generic PRA information to identify risk-important systems and components at a plant lacking a PRA. The methodology requires the detailed analysis of both similarities and differences between related plants. It is applied in an analysis of the Rancho Seco plant using information from PRAs for the ANO-1 and Oconee plants. It is generic, drawing upon the functional and design similarities of B and W plants, yet it incorporates considerable plant specificity through the detailed comparative analysis of systems. Volume 1 presents the analysis of the surrogate plant PRAs. Dominant cut sets leading to core melt are identified and analyzed to determine the Fussel-Vesely Importance of plant systems. In Volume 2 the dominant cut sets are further analyzed to identify and categorize important system failure modes. The Rancho Seco plant is then studied to determine the plausibility and importance of similar failure modes for: High Pressure Injection, Low Pressure Injection, Emergency Feedwater, Service Water, Vital ac power and dc Power systems. Plant-specific information is then presented identifying Rancho Seco components, power supplies, and operating modes associated with the failure modes for the first four of these systems.

• 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: 6439111
• Report Number(s): NUREG/CR-4768-Vol.1; PNL-6032-1; ON: TI87012739
• 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
ARKANSAS-1 REACTOR
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
INSPECTION
OCONEE-1 REACTOR
OCONEE-2 REACTOR
OCONEE-3 REACTOR
POWER REACTORS
PWR TYPE REACTORS
RANCHO SECO-1 REACTOR
RANCHO SECO-2 REACTOR
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
RISK ASSESSMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS