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.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- BNL-NUREG-39945; CONF-870601-20
- DOE Contract Number:
- Resource Type:
- 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
- Research Org:
- Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA)
- Country of Publication:
- United States
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 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
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