Impact of component outages on ECCS/ECI unavailability
Description
A general methodology has been developed which provides a quantitative basis for setting Limiting Conditions of Operation (LCO) governing Emergency Core Cooling System (ECCS) component outages. The analysis represents an extension of the techniques of the Reactor Safety Study and specifically addresses scheduled test and non-routine maintenance outages which impact the unavailability of the Emergency Coolant Injection (ECI) mode of the ECCS. The methodology can provide a basis for limiting both the short-term effects of outages, in terms of conditional unavailability constraints, and the long-term effects, measured by the average state of the system over a time interval. The methodology is not meant to replace engineering judgement in establishing LCOs, but to provide a framework for its application. No attempt has been made to optimize LCOs, nor are any specific recommendations made for establishing them, either directly or in terms of criteria. The objective is to present a possible approach and to demonstrate the viability of the probabilistic risk analysis methodology in addressing a specific problem in the licensing and regulatory decision-making process
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- Probabilistic analysis of nuclear reactor safety
- Journal Page Range
- p. XII.7.1-XII.7.11.
Conference
- Title
- Probabilistic analysis of nuclear reactor safety.
- Dates
- 8 - 10 May 1978.
- Place
- Los Angeles, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10487559
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ECCS; FAILURES; PWR TYPE REACTORS; RELIABILITY
- Descriptors DEC
- REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS