Published March 1996 | Version v1
Report

An assessment of seismic margins in nuclear plant piping

  • 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.