Published October 1994 | Version v1
Report

Containment performance observations and insights of LWRs based on the IPEs

  • 1. Brookhaven National Lab., Upton, NY (United States)

Description

Generic Letter 88-20, open-quotes Individual Plant Examination for Severe Accident Vulnerabilities - 10CFR 50.54(f),close quotes requesting the IPEs, was issued by the NRC on November 23, 1988. U.S. licensee were requested to conduct an Individual Plant Examination (IPE) in order to identify potential severe accident vulnerabilities at their plant and to implement cost-effective plant improvements to reduce or eliminate these vulnerabilities. Supplements to the Generic Letter forwarded technical insights obtained by the NRC staff through its Containment Performance Improvement (CPI) program. These insights were deemed important enough by the staff to bring to the attention of the licensees for use, as they deemed appropriate, in the IPEs which they were preparing. Coupled to their Level 1 results, licensees were requested to report the results of their analyses regarding containment performance. These results included those related to the general methodology used, plant data, plant features, plant damage states, models and methods used in the accident progression analysis, containment failure characterization, containment event trees and their end states, and radionuclide release characterization. At this time, most of the IPEs have been submitted by the licensees. In a follow-up effort to support regulatory activities, the NRC staff with assistance from Brookhaven National Laboratory, has initiated a program involving a global examination of the containment performance results documented in the IPEs. The objective is to identify insights of potential generic safety significance relative to plant design, operation and maintenance, as well as to assess response to the previously forwarded CPI insights

Additional details

Publishing Information

Imprint Title
Transactions of the twenty-second water reactor safety information meeting
Imprint Pagination
129 p.
Journal Page Range
p. 99.
Report number
NUREG/CP--0139

Conference

Title
22. water reactor safety information meeting.
Dates
24-26 Oct 1994.
Place
Bethesda, MD (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26067110
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT SYSTEMS; INSPECTION; NUCLEAR POWER PLANTS; REACTOR SAFETY; WATER COOLED REACTORS
Descriptors DEC
CONTAINMENT; ENGINEERED SAFETY SYSTEMS; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; SAFETY; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-9410216--.