Development of insights from PRAs for non-PRA people
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7043809
- Idaho National Engineering Lab., Idaho Falls (United States)
A probabilistic risk assessment (PRA) of the Savannah River K-Reactor was completed in 1990. The PRA estimated the frequency of core damage accidents caused by operational occurrences during power operation of the reactor. The US Department of Energy (DOE) requested Idaho National Engineering Laboratory (INEL) to prepare guidance based on the PRA for use by DOE personnel at the Savannah River Site (SRS). The document had the purpose of informing the DOE system engineers and site representatives about how the information in the PRA might be used to help guide their activities. Opportunities existed to develop a document somewhat different than those developed previously by other programs. The opportunities existed because the audience is different: the principal audience for the document consists of DOE engineers who have continuing oversight responsibility for activities performed by the operating contractor at the K-Reactor, but who may not be knowledgeable about PRA.
- OSTI ID:
- 7043809
- Report Number(s):
- CONF-920606--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ECCS
ENGINEERED SAFETY SYSTEMS
FAILURES
HEAVY WATER MODERATED REACTORS
IDAHO NATIONAL ENGINEERING LABORATORY
K REACTOR
LEAKS
NATIONAL ORGANIZATIONS
OPERATION
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RISK ASSESSMENT
SAFETY
SAFETY INJECTION
SAVANNAH RIVER PLANT
SHUTDOWN
SPECIAL PRODUCTION REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ECCS
ENGINEERED SAFETY SYSTEMS
FAILURES
HEAVY WATER MODERATED REACTORS
IDAHO NATIONAL ENGINEERING LABORATORY
K REACTOR
LEAKS
NATIONAL ORGANIZATIONS
OPERATION
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RISK ASSESSMENT
SAFETY
SAFETY INJECTION
SAVANNAH RIVER PLANT
SHUTDOWN
SPECIAL PRODUCTION REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS