Generic safety insights for inspection of boiling water reactors

Conference · Thu Jan 01 00:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5534844

Higgins, J C; Taylor, J H; Fresco, A N; Hillman, B M

As the number of operating nuclear power plants (NPPs) increases, safety inspection has increased in importance. Over the last 2 yr, probabilistic risk assessment (PRA) 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 approx. 25% of the US nuclear power plants have completed PRAs, and also, inspectors want PRA-based tools for these plants. This paper describes the Brookhaven National Lab. program to develop generic boiling water reactor (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)
• OSTI ID: 5534844
• Report Number(s): CONF-870601-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 54; Conference: Annual meeting of the American Nuclear Society, Dallas, TX, USA, 7 Jun 1987
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
INSPECTION
REACTOR SAFETY
BNL
ECCS
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
ERRORS
FAILURES
HUMAN FACTORS
PLANNING
PROBABILITY
QUALITY ASSURANCE
REACTOR OPERATION
REACTOR OPERATORS
RISK ASSESSMENT
TRAINING
NATIONAL ORGANIZATIONS
OPERATION
PERSONNEL
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled