EPRI seismic qualification research program
Conference
·
· IEEE Trans. Nucl. Sci.; (United States)
OSTI ID:5913732
The utility industry, through the Seismic Qualification Utilities Group (SQUG), has accomplished a major stride toward the acceptance of the use of earthquake experience data as a basis for demonstrating the seismic adequacy of equipment in nuclear plants. The approach has been developed to address the seismic qualification issues raised by the U.S. Nuclear Regulatory Commission's Unresolved Safety Issue (USI) A-46. It appears that within limitations established by a third-party panel of experts the use of earthquake experience data is a technically acceptable generic alternative to the traditional practice of seismic qualification by piece-by-piece tests or analyses. Recognizing the great potential benefits of the experience-based generic qualification approach, the Electric Power Research Institute (EPRI) has established a research program with the main objective of providing utilities with additional data and methods to allow wider application of the experience approach to equipment in operating plants. As part of the EPRI Seismic Center, the seismic qualification program is also being used in the resolution of the Eastern U.S. seismicity issue.
- Research Organization:
- Electric Power Research Inst., 3412 Hillview Ave., Palo Alto, CA 94303
- OSTI ID:
- 5913732
- Report Number(s):
- CONF-851010-
- Conference Information:
- Journal Name: IEEE Trans. Nucl. Sci.; (United States) Journal Volume: NS-33:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evolution of the SQUG methodology for seismic verification 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
·
Sun Dec 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6780497
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
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
CERTIFICATION
EARTHQUAKES
ELECTRIC UTILITIES
EPRI
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE TESTING
POWER PLANTS
PUBLIC UTILITIES
REACTOR COMPONENTS
RESEARCH PROGRAMS
SEISMIC EFFECTS
SEISMIC EVENTS
SEISMICITY
TESTING
THERMAL POWER PLANTS
US NRC
US ORGANIZATIONS
220200* -- Nuclear Reactor Technology-- Components & Accessories
CERTIFICATION
EARTHQUAKES
ELECTRIC UTILITIES
EPRI
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE TESTING
POWER PLANTS
PUBLIC UTILITIES
REACTOR COMPONENTS
RESEARCH PROGRAMS
SEISMIC EFFECTS
SEISMIC EVENTS
SEISMICITY
TESTING
THERMAL POWER PLANTS
US NRC
US ORGANIZATIONS