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
- Country of Publication:
- United States
- Language:
- English
Similar Records
Development and use of risk-based inspection guides
Inspection guidance for the Rancho Seco plant derived from generic PRA information
Generic safety insights for inspection of boiling water reactors
Technical Report
·
Wed May 31 20:00:00 EDT 1989
·
OSTI ID:6118971
Inspection guidance for the Rancho Seco plant derived from generic PRA information
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5534846
Generic safety insights for inspection of boiling water reactors
Conference
·
Wed Dec 31 19:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5534844
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONNECTICUT YANKEE REACTOR
DATA BASE MANAGEMENT
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
INSPECTION
MANAGEMENT
POWER REACTORS
PROBABILISTIC ESTIMATION
PROBABILITY
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONNECTICUT YANKEE REACTOR
DATA BASE MANAGEMENT
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
INSPECTION
MANAGEMENT
POWER REACTORS
PROBABILISTIC ESTIMATION
PROBABILITY
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS