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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 ·
OSTI ID:10168877
 [1];  [2];  [3];  [4];  [5]
  1. Structural Mechanics Consulting, Inc., Yorba Linda, CA (United States)
  2. Sandia National Labs., Albuquerque, NM (United States)
  3. Degenkolb (H.J.) Associates, San Francisco, CA (United States)
  4. Stanford Univ., CA (United States)
  5. Anco Engineers, Inc., Culver City, CA (United States)
+ Show Author Affiliations
In December 1980, the US Nuclear Regulatory Commission (NRC) designated ``Seismic Qualification of Equipment in Operating Plants`` as an Unresolved Safety Issue (USI), A-46. The objective of USI A-46 is to develop alternative seismic qualification methods and acceptance criteria that can be used to assess the capability of mechanical and electrical equipment in operating nuclear power plants to perform the intended safety functions. A group of affected utilities formed the Seismic Qualification Utility Group (SQUG) to work with the NRC in developing a program methodology to enable resolution of the A-46 issue. To assist in developing a program methodology, SQUG and the NRC jointly selected and supported a five-member Senior Seismic Review and Advisory Panel (SSRAP) in June 1983 to make an independent assessment of whether certain classes of equipment in operating nuclear power plants in the United States have demonstrated sufficient ruggedness in past earthquakes so as to render an explicit seismic qualification unnecessary. SSRAP operated as an independent review body with all of its findings submitted concurrently to both SQUG and the NRC. During their period of involvement, SSRAP issued several draft reports on their conclusions. This document contains the final versions of these reports; namely, ``Use of Seismic Experience and Test Data to Show Ruggedness of Equipment in Nuclear Power Plants,`` dated February 1991 and ``Review Procedure to Assess Seismic Ruggedness of Cantilever Bracket Cable Tray Supports,`` dated March 1, 1991.
Research Organization:
Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Organization:
Nuclear Regulatory Commission, Washington, DC (United States)
DOE Contract Number:
AC04-76DP00789
OSTI ID:
10168877
Report Number(s):
SAND--92-0140; ON: DE92019328
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200
220900
BATTERY CHARGERS
COMPONENTS AND ACCESSORIES
COMPRESSORS
EARTHQUAKES
ELECTRIC CABLES
ELECTRIC MOTORS
ELECTRICAL EQUIPMENT
EVALUATION
FREQUENCY DEPENDENCE
GROUND MOTION
NUCLEAR POWER PLANTS
PUMPS
REACTOR SAFETY
SEISMIC EFFECTS
SEISMIC ISOLATION
SOIL-STRUCTURE INTERACTIONS
SUPPORTS