Generic safety insights for inspection of boiling water reactors
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5534844
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 Lab., Upton, NY
- OSTI ID:
- 5534844
- Report Number(s):
- CONF-870601-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 54
- Country of Publication:
- United States
- Language:
- English
Similar Records
Generic safety insights for inspection of boiling water reactors
Application of generic PRA (probabilistic risk assessment) insights to NRC inspection
Development and use of risk-based inspection guides
Conference
·
Wed Dec 31 19:00:00 EST 1986
·
OSTI ID:6175293
Application of generic PRA (probabilistic risk assessment) insights to NRC inspection
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5360483
Development and use of risk-based inspection guides
Technical Report
·
Wed May 31 20:00:00 EDT 1989
·
OSTI ID:6118971
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
BNL
BWR TYPE REACTORS
ECCS
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
ERRORS
FAILURES
HUMAN FACTORS
INSPECTION
NATIONAL ORGANIZATIONS
OPERATION
PERSONNEL
PLANNING
PROBABILITY
QUALITY ASSURANCE
REACTOR OPERATION
REACTOR OPERATORS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
TRAINING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BNL
BWR TYPE REACTORS
ECCS
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
ERRORS
FAILURES
HUMAN FACTORS
INSPECTION
NATIONAL ORGANIZATIONS
OPERATION
PERSONNEL
PLANNING
PROBABILITY
QUALITY ASSURANCE
REACTOR OPERATION
REACTOR OPERATORS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
TRAINING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS