Review insights on the probabilistic risk assessment for the Limerick Generating Station
Technical Report
·
OSTI ID:6776445
In recognition of the high population density around the Limerick Generating Station site and the proposed power level, the Philadelphia Electric Company, in response to NRC staff requests, conducted and submitted between March 1981 and November 1983 a probabilistic risk assessment (PRA) on internal event contributors and a severe accident risk assessment on external event contributors to assess risks posed by operation of the plant. The applicant has developed perspectives using PRA models on the safety profile of the Limerick plant and has altered the plant design to reduce accident vulnerabilities identified in these PRAs. The staff's review of the Limerick PRA has particularly emphasized the dominant accident sequences and the resulting insights into demonstration of compliance with regulatory requirments, unique design features and major plant vulnerabilities to assess the need for any additional measures to further improve the safety of the LGS. The staff's review insights and PRA safety review conclusions are presented in this report.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Technology
- OSTI ID:
- 6776445
- Report Number(s):
- NUREG-1068; ON: TI84901884
- Country of Publication:
- United States
- Language:
- English
Similar Records
Limerick probabilistic risk analysis highlights
Review of the Limerick Generating Station Probabilistic Risk Assessment
Probabilistic risk assessment familiarization training
Conference
·
Fri Dec 31 23:00:00 EST 1982
· Proc. Am. Power Conf.; (United States)
·
OSTI ID:6686565
Review of the Limerick Generating Station Probabilistic Risk Assessment
Technical Report
·
Mon Jan 31 23:00:00 EST 1983
·
OSTI ID:6342094
Probabilistic risk assessment familiarization training
Conference
·
Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6923043
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
BWR TYPE REACTORS
ENVIRONMENTAL IMPACTS
HAZARDS
HEALTH HAZARDS
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
POWER REACTORS
RADIATION HAZARDS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
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
BWR TYPE REACTORS
ENVIRONMENTAL IMPACTS
HAZARDS
HEALTH HAZARDS
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
POWER REACTORS
RADIATION HAZARDS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS