Component fragility research program: prioritization and demonstration testing
Description
Current probabilistic risk assessment (PRA) methods for nuclear power plants utilize seismic fragilities - probabilities of failure conditioned on the severity of seismic input motion - which are based largely on limited test data and on engineering judgement. As part of the NRC Component Fragility Research Program (CFRP), the Lawrence Livermore National Laboratory (LLNL) developed procedures for fragilities testing. These procedures were applied to evaluate actual seismic capacities of motor control center (MCC) electrical devices, to develop seismic fragility curves suitable for PRA application, and to suggest various methods of improving MCC seismic performance. In other CFRP activities, LLNL used high-level qualification data to develop fragility descriptions for selected equipment, and identified candidate components for future comprehensive fragilities testing using similar procedures
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting. Volume 3. Equipment qualification, mechanical and structural research, seismic research, nuclear plant aging
- Journal Page Range
- p. 229-254.
- Report number
- NUREG/CP--0082-Vol.3
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002111
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT SYSTEMS; ECCS; ELECTRICAL EQUIPMENT; FAILURES; LAWRENCE LIVERMORE LABORATORY; PROBABILITY; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR INSTRUMENTATION; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ASSESSMENT; SEISMIC EFFECTS; TESTING
- Descriptors DEC
- CONTAINMENT; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; LAWRENCE LIVERMORE NATIONAL LA; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS