Application of risk-informed decision making to the steam generator overfill design basis for the Catawba Nuclear Station (PSAM 5)
- 1. Duke Energy Corp., Charlotte, NC (United States)
Description
Preventing steam generator overfill following a steam generator tube rupture (SGTR) is part of the design basis for the Catawba Nuclear Station. A small number of single failures have been identified that are more limiting, with respect to steam generator overfill, than the single failure assumed in the design basis SGTR evaluation. The purpose of this work is to assess the risk significance of these failures and evaluate the appropriateness of excluding these failures from the design basis. The risk significance of these single failures is judged by the contributions to core damage frequency (CDF) and large early release frequency (LERF) associated with their occurrence in conjunction with an SGTR event. The resulting CDF and LERF constituents are estimated to be less than lE09/RY for each single failure. It is concluded that the single failures considered in this analysis are appropriate for exclusion from the design basis for the Catawba Nuclear Station. (author)
Additional details
Publishing Information
- Publisher
- Universal Academy
- Imprint Place
- Tokyo (Japan)
- ISBN
- 4-946443-64-9
- Imprint Title
- PSAM 5: Probabilistic safety assessment and management
- Imprint Pagination
- 2820 p.
- Journal Page Range
- p. 671-677
Conference
- Title
- 5. international conference on probabilistic safety assessment and management
- Acronym
- PSAM 5
- Dates
- 27 Nov - 1 Dec 2000
- Place
- Osaka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32056392
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CATAWBA-1 REACTOR; CATAWBA-2 REACTOR; DECISION MAKING; ECCS; EMERGENCY PLANS; HUMAN FACTORS; NUCLEAR POWER PLANTS; PIPES; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR CORES; REACTOR OPERATORS; RISK ASSESSMENT; RUPTURES; STEAM GENERATORS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- ACCIDENTS; BOILERS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; NUCLEAR FACILITIES; PERSONNEL; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Vol. 2/4 Imprint:Published in 4 volumes, also available on CD-ROM can be used for Windows 95/98/2000, Macintosh and UNIX. Also published in Frontiers Science Series No.34, ISSN 0915-8502