Activities of Cofrentes Nuclear Power Plant related to PSA and its applications
Creators
Description
By February 1988 the Spanish Council for Nuclear Safety (CSN), asked IBERDROLA as utility in charge for the performance of a PSA (Probabilistic Safety Analysis) at the Cofrentes Nuclear Power Plant, with the following scope: PSA (level 1) for internal events with the reactor starting at nominal conditions. Analysis of fire inside the plant (core damage) and analysis of internal and external floods (core damage). The paper summarizes the structure of some methodologies used, modularization of failure trees, utilization of methodology FIVE (Fire Vulnerability Evaluation Methodology) developed by EPRI to the Cofrentes case, complementary analyses complying with the appendix R to 10 CFR 50, analysis of event frequency of rotated fuel elements, and development and qualification of a model for Cofrentes through the code MAAP3.OB-BWR
Additional details
Additional titles
- Original title (Spanish)
- Actividades de C.N. Cofrentes relacionadas con APS y aplicaciones
Publishing Information
- Journal Title
- Revista de la Sociedad Nuclear Espanola
- Journal Volume
- 121
- Journal Page Range
- p. 31-35.
- ISSN
- 0214-1159
- CODEN
- RSESEJ
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- Spain
- INIS RN
- 25002739
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- COFRENTES REACTOR; COMPUTER CODES; CORE FLOODING SYSTEMS; PROBABILITY; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT; SITE CHARACTERIZATION
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY