Application of generic PRA (probabilistic risk assessment) insights to NRC inspection
Conference
·
OSTI ID:5360483
The United States Nuclear Regulatory Commission (NRC) has developed a program that uses probabilistic risk assessment (PRA) results to produce plant specific inspection guidelines for use by NRC inspectors. Because only about one-quarter of the operating United States (US) plants have PRAs, a generic methodology has been proposed for the production of inspection guidelines for plants without PRAs. The first application of this proposed generic method was to a plant which has a PRA, so a comparison of the inspection guidance produced by the PRA-based and generic methods could be made. An evaluation of the comparison from that application is provided.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA); Nuclear Regulatory Commission, King of Prussia, PA (USA). Region I
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5360483
- Report Number(s):
- EGG-M-20187; CONF-870820-11; ON: DE88006716
- Resource Relation:
- Conference: PSA 87: international topical meeting on probabilistic safety assessment and risk management, Zurich, Switzerland, 31 Aug 1987
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONNECTICUT YANKEE REACTOR
RISK ASSESSMENT
DATA BASE MANAGEMENT
FAULT TREE ANALYSIS
INSPECTION
PROBABILISTIC ESTIMATION
PROBABILITY
REACTOR COMPONENTS
REACTOR SAFETY
ENRICHED URANIUM REACTORS
MANAGEMENT
POWER REACTORS
PWR TYPE REACTORS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled