Retrospective quantitative analysis of common cause failures and human interactions in Swedish PSA studies
Description
This paper reports that following recommendations from qualitative analyses comprehensive sensitivity studies of the treatment of common cause failures (CCFs) and human interactions in available Swedish Probabilistic Safety Assessment (PSA) studies for BWR-plants have been carried out. Among the issues which have been investigated in the context of CCF-contributions are: impact of lower failure multiplicities, plant-specific CCf-parameters for motor-operated valves (MOVs) and comparison between two quantification methods. Several studies concerning data variation, systematic misconfiguration of redundant components, test arrangements and treatment of multiple failures in systems with non-standard level of redundance, are in progress. Studies of human interactions have focused on errors of omission and on recovery actions. Sensitivity analyses provide guidance for future efforts and have lead to specific recommendations with respect to treatment of CCFs and human interactions within the plant-specific reference plant models to be generated in the near future
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-89448-142-8
- Imprint Title
- Probability, reliability, and safety assessment PSA '89
- Imprint Pagination
- 1300 p.
- Journal Page Range
- p. 258-269.
Conference
- Title
- international topical meeting on probability, reliability and safety assessment.
- Acronym
- PSA '89
- Dates
- 2-7 Apr 1989.
- Place
- Pittsburgh, PA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059518
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ERRORS; HUMAN FACTORS; REACTOR SAFETY; RISK ASSESSMENT; SENSITIVITY ANALYSIS; SWEDEN; SYSTEM FAILURE ANALYSIS; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EQUIPMENT; EUROPE; FLOW REGULATORS; POWER REACTORS; REACTORS; SAFETY; SCANDINAVIA; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890405--.