Evolution of the SQUG methodology for seismic verification of nuclear plant equipment
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6780497
In 1980, the US Nuclear Regulatory Commission (NRC) established Unresolved Safety Issue (USI) A-46, Seismic Qualification of Equipment in Operating Nuclear Power Plants to evaluate the seismic adequacy of equipment in plants that were designed prior to the development of current seismic qualification criteria. In 1982, the Seismic Qualification Utility Group (SQUG), then consisting of [approximately]15 utilities, took the lead in developing a cost-effective method of resolving USI A-46 based on the performance of equipment in actual earthquakes. The NRC accepted the SQUG approach and defined implementation requirements in 1987. With Electric Power Research Institute (EPRI) support, SQUG has since developed additional data, evaluation criteria, implementation procedures, and training programs to apply the SQUG methodology to resolve USI A-46. This paper describes the evolution of this work.
- OSTI ID:
- 6780497
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
Similar Records
The evolution of the seismic qualification utility group methodology for assessing seismic adequacy of nuclear plant equipment
Part 1, Use of seismic experience and test data to show ruggedness of equipment in nuclear power plants; Part 2, Review procedure to assess seismic ruggedness of cantilever bracket cable tray supports
Part 1, Use of seismic experience and test data to show ruggedness of equipment in nuclear power plants; Part 2, Review procedure to assess seismic ruggedness of cantilever bracket cable tray supports
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Proceedings of the American Power Conference; (United States)
·
OSTI ID:7116921
Part 1, Use of seismic experience and test data to show ruggedness of equipment in nuclear power plants; Part 2, Review procedure to assess seismic ruggedness of cantilever bracket cable tray supports
Technical Report
·
Mon Jun 01 00:00:00 EDT 1992
·
OSTI ID:10168877
Part 1, Use of seismic experience and test data to show ruggedness of equipment in nuclear power plants; Part 2, Review procedure to assess seismic ruggedness of cantilever bracket cable tray supports
Technical Report
·
Mon Jun 01 00:00:00 EDT 1992
·
OSTI ID:7112181
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