Published March 1996
| Version v1
Report
An assessment of seismic margins in nuclear plant piping
Creators
- 1. Energy Technology Engineering Center, Canoga Park, CA (United States)
- 2. Nuclear Regulatory Commission, Washington DC (United States)
Description
Interim results of an ongoing program to assist the U.S. Nuclear Regulatory Commission (NRC) in developing regulatory positions on the seismic analyses of piping and overall safety margins of piping systems are reported. Results of: (1) reviews of seismic testing of piping components performed as part of the Electric Power Research Institute (EPRI)/NRC Piping and Fitting Dynamic Reliability (PFDR) Program, and (2) assessments of safety margins inherent in the ASME Code, Section III, piping seismic design criteria as revised by the 1994 Addenda are reported. The reviews indicate that the margins inherent in the revised criteria may be less than acceptable and that modifications to these criteria may be required
Additional details
Publishing Information
- Imprint Title
- Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues
- Imprint Pagination
- 236 p.
- Journal Page Range
- p. 1-12.
- Report number
- NUREG/CP--0149-Vol.3
Conference
- Title
- 23. water reactor safety information meeting.
- Dates
- 23-25 Oct 1995.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27068505
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DIAGRAMS; EVALUATION; NUMERICAL DATA; PIPES; SEISMIC EFFECTS; WATER COOLED REACTORS
- Descriptors DEC
- DATA; INFORMATION; REACTORS
Optional Information
- Secondary number(s)
- CONF-9510156--Vol.3.