Analysis of dependent failures in the ORNL precursor study
Creators
Description
The study of dependent failures (or common cause/mode failures) in the safety assessment of potentially hazardous plant is one of the significant areas of uncertainty in performing probabilistic safety studies. One major reason for this uncertainty is that data on dependent failures is apparently not readily available in sufficient quantity to assist in the development and validation of models. The incident reports that were compiled for the ORNL study on Precursors to Severe Core Damage Accidents (NUREG/CR-2497) provide an opportunity to look at the importance of dependent failures in the most significant incidents of recent reactor operations, to look at the success of probabilistic risk assessment (PRA) methods in accounting for the contribution of dependent failures, and to look at the dependent failure incidents with the aim of identifying the most significant problem areas. In this paper an analysis has been made of the incidents compiled in NUREG/CR-2497 and events involving multiple failures which were not independent have been identified. From this analysis it is clear that dependent failures are a very significant contributor to the precursor incidents. The method of enumeration of accident frequency used in NUREG-2497 can be shown to take account of dependent failures and this may be a significant factor contributing to the apparent difference between the precursor accident frequency and typical PRA frequencies
Additional details
Publishing Information
- Imprint Title
- International topical meeting on probabilistic safety methods and applications: proceedings. Volume 1. Sessions 1-8
- Journal Page Range
- p. 6.1-6.10.
- Report number
- EPRI-NP--3912-SR-Vol.1
Conference
- Title
- International ANS/ENS topical meeting on probabilistic safety methods and applications.
- Dates
- 24 Feb - 1 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023271
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DATA PROCESSING; FAILURES; LOSS OF COOLANT; NUCLEAR POWER PLANTS; ORNL; OUTAGES; PROBABILITY; REACTOR ACCIDENTS; REACTOR COMPONENTS; RELIABILITY; RISK ASSESSMENT; SAFETY ENGINEERING; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS; US AEC; US DOE; US ERDA; US ORGANIZATIONS