Fault tree analysis on BWR core spray system
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
Fault Trees which describe the failure modes for the Core Spray System function in the Browns Ferry Nuclear Plant (BWR 1065MWe) were developed qualitatively and quantitatively. The unavailability for the Core Spray System was estimated to be 1.2 x 10-3/demand. It was found that the miscalibration of four reactor pressure sensors or the failure to open of the two inboard valves (FCV 75-25 and 75-53) could reduce system reliability significantly. It was recommended that the pressure sensors would be calibrated independently. The introduction of the redundant inboard valves could improve the system reliability. Thus this analysis method was verified useful for system analysis. The detailed test and maintenance manual and the informations on the control logic circuits of each active component are necessary for further analysis. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
14771899.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 112 p.
- Report number
- JAERI-M--82-060
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 14771899
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- BROWNS FERRY-1 REACTOR; CORE SPRAY SYSTEMS; FAILURE MODE ANALYSIS; FAULT TREE ANALYSIS; PROBABILITY; REACTOR SAFETY; SYSTEMS ANALYSIS
- Descriptors DEC
- BWR TYPE REACTORS; ECCS; ENRICHED URANIUM REACTORS; MIXED SPECTRUM REACTORS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS