Generic safety insights for inspection of boiling water reactors
As the number of operating nuclear power plants (NPP) increases, safety inspection has increased in importance. However, precisely what is important, and what is not important. What should one focus inspection efforts on. Over the last two years Probabilistic Risk Assessment (PR) techniques have been developed to aid in the inspection process. Broad interest in generic PRA-based methods has arisen in the past year, since only about 25% of the US nuclear power plants have completed PRAs, and also, inspectors want PRA-based tools for these plants. This paper describes the BNL program to develop generic BWR PRA-based inspection insights or inspection guidance designed to be applied to plants without PRAs.
- Research Organization:
- Brookhaven National Laboratory (BNL), Upton, NY (United States); US Nuclear Regulatory Commission (NRC), Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6175293
- Report Number(s):
- BNL-NUREG-39945; CONF-870601-20; ON: DE87012117
- Resource Relation:
- Conference: Annual meeting of the American Nuclear Society, Dallas, TX, USA, 7 Jun 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
INSPECTION
REACTOR SAFETY
PROBABILISTIC ESTIMATION
RISK ASSESSMENT
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210700* - Nuclear Power Plants- Regulation & Licensing
220900 - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled