An evaluation of internal event level 1 PRA methods used in NUREG-1150

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:6324022

Camp, A L; Cramond, W R

As part of the effort to support NUREG-1150, Sandia National Laboratories and its subcontractors have developed innovative techniques for efficiently performing internal event Level I probabilistic risk assessments. This methodology is one of the alternatives for industry to use in performing individual plant evaluations in the future. While this new methodology was very successful, there are some areas where improvements can be made. This paper evaluates the strengths and weaknesses of the methodology and makes some important recommendations for modifications in order to provide insights to future users. 10 refs.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6324022
• Report Number(s): SAND-88-1455C; CONF-890405-12; ON: DE89005232; TRN: 89-008351
• Resource Relation: Conference: International topical meeting on probability, reliability and safety assessment, Pittsburgh, PA, USA, 2 Apr 1989; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
RISK ASSESSMENT
EVALUATION
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
HUMAN FACTORS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
PERFORMANCE
REACTOR ACCIDENTS
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
US NRC
ACCIDENTS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
THERMAL POWER PLANTS
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US ORGANIZATIONS
WATER COOLED REACTORS
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220900* - Nuclear Reactor Technology- Reactor Safety