Impact of surveillance test interval extension on the core-melt frequency: a methodological approach
- 1. Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)
- 2. Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Garching (Germany)
- 3. Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia
Description
The objective of this paper is to compare the traditional method used to determine the risk impact associated with the extension of a surveillance test interval (STI) with a computerized one, such as Living PSA (LPSA) or a Risk Monitor System (RMS), over the base-line risk of the facility. PSA techniques and methods (also called traditional methods) have been used in order to show all necessary steps hat should be performed during the risk calculations associated with an STI extension, considering the contributions due to accident sequences which demand the safety injection system, common cause failures and human errors. The discussion is centered on the importance of having a on-line computerized system, LPSA or RMS, that can calculate, in a simple fashion, changes in the base-line risk due to a continuous change in plant configurations and their operating procedures as compared to the procedure for calculating the risk level increase due to STI extension without a LPSA or RMS. (author). 10 refs
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics
- Imprint Pagination
- 838 p.
- Journal Page Range
- p. 646-651.
Conference
- Title
- Meeting on reactor physics and thermal hydraulics.
- Acronym
- 11. ENFIR
- Dates
- 18-22 Aug 1997.
- Place
- Pocos de Caldas, MG (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28075979
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENTS; INSPECTION; MELTDOWN; NUCLEAR ENGINEERING; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR MAINTENANCE; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTORS; RELIABILITY; RISK ASSESSMENT; SYSTEMS ANALYSIS; TESTING
- Descriptors DEC
- ENGINEERING; MAINTENANCE; REACTOR COMPONENTS; SAFETY
Optional Information
- Notes
- Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.