Application of PSA for optimization of systems design and backfitting at Siemens/KWU
Description
The systems and plant design of Siemens/KWU pressurized water reactor (PWR) is based on mainly deterministic oriented requirements, with limited practicability for PSA recommendations. The PSA has been used as a supplementary tool for years with increasing importance. The actual licensing for the most recent PWR 1300 MW-Convoy plants required a PSA-Level 1. With respect to the resulting discussions the supplementary character of the PSA should be preferred over direct inclusion, e.g. due to the lack of guidelines. The consequent conversion of findings from safety research including PSA during design development results in very low core damage frequency as demonstrated for the PWR 1300 MW-Convoy. But in general the engineering insights from PSA valuation should be prioritized to absolute frequency numbers. Basing mainly on PSA-findings, an additional fourth safety level has been established to cope with beyond design accidents and/or to mitigate the consequences of severe accidents. To use the inherent safe behavior of the plant, relatively simple accident management measures are developed to prevent severe core damage and to limit the releases to the environment beyond values actually required for advanced plants
Additional details
Publishing Information
- Imprint Title
- CSNI workshop on PSA applications and limitations. Proceedings
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. 151-158.
- Report number
- NUREG/CP--0115
Conference
- Title
- Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) applications and limitations.
- Dates
- 4-6 Sep 1990.
- Place
- Santa Fe, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008694
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR CLEANING; BWR TYPE REACTORS; BYPASSES; CONTAINMENT SYSTEMS; EMERGENCY PLANS; ENVIRONMENTAL IMPACTS; FEDERAL REPUBLIC OF GERMANY; FEEDWATER; FILTERS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MANAGEMENT; MITIGATION; OPTIMIZATION; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; RADIATION DOSES; REACTOR CORE DISRUPTION; REACTOR LICENSING; RELIABILITY; RELIEF VALVES; RESEARCH PROGRAMS; RETROFITTING; RISK ASSESSMENT; SAFETY ENGINEERING; SECONDARY COOLANT CIRCUITS; VENTILATION
- Descriptors DEC
- ACCIDENTS; CLEANING; CONTAINMENT; CONTROL EQUIPMENT; COOLING SYSTEMS; DEVELOPED COUNTRIES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; EUROPE; FLOW REGULATORS; HYDROGEN COMPOUNDS; LICENSING; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VALVES; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- SAND--90-2797; CONF-9009346--.