Seismic PSA of nuclear power plants a case study
Creators
- 1. Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
Seismic Probabilistic Safety Assessment (Seismic PSA) analysis is an external event PSA analysis. The objective of seismic PSA for the plants is to examine the existence of plant vulnerabilities against postulated earthquakes by numerically assessing the plant safety and to take appropriate measures to enhance the plant safety. Seismic PSA analysis integrates the seismic hazard analysis, seismic response analysis, seismic fragility analysis and system reliability/ accident sequence analysis. In general, the plant consists of normally operating and emergency standby systems and components. The failure during an earthquake (induced directly by excessive inertial stresses or indirectly following the failure of some other item) of an operating component will lead to a change in the state of the plant. In that case, various scenarios can follow depending on the initiating event and the status of other sub-systems. The analysis represents these possible chronological sequences by an event tree. The event trees and the associated fault trees model the sub-systems down to the level of individual components. The procedure has been applied for a typical Indian nuclear power plant. From the internal event PSA level I analysis significant contribution to the Core Damage Frequency (CDF) was found due to the Fire Water System. Hence, this system was selected to establish the procedure of seismic PSA. In this report the different elements that go into seismic PSA analysis have been discussed. Hazard curves have been developed for the site. Fragility curve for the seismically induced failure of Class IV power has been developed. The fragility curve for fire-water piping system has been generated. Event tree for Class IV power supply has been developed and the dominating accident sequences were identified. CDF has been estimated from these dominating accident sequences by convoluting hazard curves of initiating event and fragility curves of the safety systems. (author)
Availability note (English)
Available from INIS in electronic formFiles
37081602.pdf
Files
(2.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 57 p.
- Report number
- BARC--2006/E/015
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 37081602
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- EARTHQUAKES; FAULT TREE ANALYSIS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; SEISMIC EFFECTS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENERGY SYSTEMS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SAFETY; SEISMIC EVENTS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS
Optional Information
- Notes
- 21 refs., 16 figs., 4 tabs., 2 ills.