Fire PSA of the French PWR 900 MWe series. Pt. 1. Detailed study of the critical zones
Description
The Institute for Radioprotection and Nuclear Safety (IRSN) has developed a Fire Probabilistic Safet Assessment of the operating French 900 MWe PWR in order to organize into a hierarchy the items of equipments and the compartments, impacting the core melt frequency following a fire, and to reinforce deterministic safety analysis with functional analysis and realistic fire scenarios. The IRSN Fire PSA is composed of two stages: the first one concerns the selection of critical zones and the second one concerns the detailed study of the critical compartments, corresponding to the development of the fire scenarios and of the fire-induced core damage sequences. The first version of the IRSN Fire PSA has been updated by integrating the specificities of the Fire Action Plan, implemented by the utility on the French 900 MWe PWR. This study shows that four compartments are preponderant. The integration of the Fire Action Plan allowed decreasing the number of preponderant compartments. The integration of the symptom-oriented procedures and the removal of conservatisms should lead to a lower core damage frequency for these preponderant compartments. The results show that fire is not a negligible risk but the implementation of the Fire Action Plan has a significant positive impact on safety. (orig.)
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 72
- Journal Issue
- 3
- Series
- Special subject: advances in fire protection of nuclear power plants
- Journal Page Range
- p. 132-135
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 38065790
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; F CODES; FIRE HAZARDS; FLAME PROPAGATION; FRANCE; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; RISK ASSESSMENT; SAFETY ANALYSIS; SENSITIVITY ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; HAZARDS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE