Use of PRA (probabilistic risk assessment) to support a safety system functional inspection
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:6529298
- TENERA, San Jose, CA (USA)
Safety system functional inspections (SSFIs) have become important tools for both the regulator and utilities to assure that plant systems important to safety will function as designed. The Washington Public Power Supply System (WPPSS) has initiated an SSFI program to verify that the design-basis documentation of plant systems is adequate. This paper describes the application of probabilistic risk assessment (PRA) methods to support the SSFI of the WNP-2 alternating current (ac) power system. Performing SSFIs can be a very resource-intensive process. The application of PRA methods to focus the SSFI on the components important to safety allowed WPPSS to efficiently utilize their resources and reduce the cost of the overall SSFI effort.
- OSTI ID:
- 6529298
- Report Number(s):
- CONF-891103--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AC SYSTEMS
ACCIDENTS
BWR TYPE REACTORS
CORE SPRAY SYSTEMS
DESIGN
DIESEL ENGINES
ECCS
EFFICIENCY
ELECTRONIC CIRCUITS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENGINES
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
HEAT ENGINES
INSPECTION
INTERNAL COMBUSTION ENGINES
MAINTENANCE
NATIONAL ORGANIZATIONS
PERFORMANCE TESTING
POWER SYSTEMS
POWER TRANSMISSION LINES
QUALITY ASSURANCE
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
REACTORS
RISK ASSESSMENT
SURVEILLANCE
SWITCHING CIRCUITS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL REACTORS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WNP-2 REACTOR
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AC SYSTEMS
ACCIDENTS
BWR TYPE REACTORS
CORE SPRAY SYSTEMS
DESIGN
DIESEL ENGINES
ECCS
EFFICIENCY
ELECTRONIC CIRCUITS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENGINES
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
HEAT ENGINES
INSPECTION
INTERNAL COMBUSTION ENGINES
MAINTENANCE
NATIONAL ORGANIZATIONS
PERFORMANCE TESTING
POWER SYSTEMS
POWER TRANSMISSION LINES
QUALITY ASSURANCE
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
REACTORS
RISK ASSESSMENT
SURVEILLANCE
SWITCHING CIRCUITS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL REACTORS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WNP-2 REACTOR