Relay chatter and its effects on nuclear plant safety
Creators
- 1. FTA Associates, Oakland, CA (USA)
- 2. Future Resources Associates, Inc., Berkeley, CA (USA)
Description
This paper describes a limited scope probabilistic risk assessment (PRA) that was conducted for the U.S. Nuclear Regulatory Commission. The PRA addressed the effect of a strong-motion earthquake on the control and instrumentation systems at a nuclear power plant. Accident sequences were generated that incorporated seismically induced failure modes of relays, pressure switches, circuit breakers, motor operated valves, instrumentation, control systems and electrical systems. Specifically, the effects of chattering of relay contacts and pressure switch on contacts during a major earthquake were studied. Special emphasis was placed on identifying circuits that could seal-in due to the effect of relay contacts chatter. In this paper, the authors emphasize qualitative insights that were obtained from the PRA
Additional details
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structual mechanics in reactor technology
- Imprint Pagination
- 199 p.
- Series
- Volume P. Probabilistic safety assessment.
- Journal Page Range
- p. 127-132.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21068252
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CIRCUIT BREAKERS; EARTHQUAKES; FAILURE MODE ANALYSIS; NUCLEAR POWER PLANTS; OVERVOLTAGE; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR SAFETY; SEISMIC EFFECTS; US NRC; ZION-1 REACTOR
- Descriptors DEC
- ELECTRIC POTENTIAL; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; EQUIPMENT PROTECTION DEVICES; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890855--.