Inspection guidance for the Rancho Seco plant derived from generic PRA information
This paper reports the first application of generic probabilistic risk assessment (PRA) information to the development of guidance for use in planning US Nuclear Regulatory Commission inspection activities at nuclear power plants lacking plant-specific PRA's. A methodology is presented for using the results of PRAs for similar (surrogate) plants, along with plant-specific information about the target and surrogate plants to infer important failure modes for systems and components of the target plant. This methodology, and the rationale on which it is based, is presented in the context of its application to Babcock and Wilcox (B and W) plants. The Rancho Seco plant has been analyzed using PRA information from two surrogate plants: Arkansas Nuclear One Unit 1 (ANO-1) and Oconee. Analysis results have been used to develop plant-specific Rancho Seco information for potential use by inspectors at NRC Region 5.
- Research Organization:
- Pacific Northwest Labs., Richland, WA
- OSTI ID:
- 5534846
- Report Number(s):
- CONF-870601-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 54; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
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Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AC SYSTEMS
DC SYSTEMS
DESIGN
DOCUMENTATION
ECCS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FEEDWATER
HIGH PRESSURE COOLANT INJECTION
HYDROGEN COMPOUNDS
INSPECTION
LOW PRESSURE COOLANT INJECTION
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXYGEN COMPOUNDS
PLANNING
POWER PLANTS
POWER REACTORS
POWER SYSTEMS
PROBABILITY
PWR TYPE REACTORS
RANCHO SECO-1 REACTOR
REACTOR PROTECTION SYSTEMS
REACTORS
RISK ASSESSMENT
THERMAL POWER PLANTS
US NRC
US ORGANIZATIONS
USES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS