Analyses of systems availability and operator actions to support the development of severe accident procedures
- 1. Westinghouse Electric Corp., Pittsburgh, PA (United States). Nuclear and Advanced Technology Div.
- 2. Westinghouse Nuclear and Advanced Technology Div., Rue de Stalle, 73, Brussels (Belgium)
Description
This paper reports on traditional analyses of severe accidents, such as those presented in Probabilistic Risk Assessment (PRA) studies of nuclear power stations, that have generally been performed on the assumption that all means of cooling the reactor core are lost and that no operator actions to mitigate the consequences or progression of the severe accident are performed. The assumption to neglect the availability of safety systems and operator actions which do not prevent core melting can lead to erroneous conclusions regarding the plant severer accident profile. Recent work in severe accident management has identified the need to perform analyses which consider all systems availabilities and operator actions, irrespective of their contribution to the prevention of core melting. These new analyses indicate that the traditional analyses result in overfly pessimistic predictions of the time of core melting and the subsequent potential for recovery of core cooling prior to core melting. Additionally, since the traditional analyses do not model all of the operator actions which are prescribed, the impact of additional severe accident operator actions on the progression and consequences of the accident cannot be reliably identified. Further, the more detailed analysis can change the focus of the importance of various system to the prevention of core damage and the mitigation of severe accident consequences. Finally, the simplicity of the traditional analyses can have a considerable impact on severe accident decision making, particularly in the evaluation of alternate plant design features and the priorities for research studies
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. 1012-1017.
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
- 23058144
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; EMERGENCY PLANS; LOSS OF COOLANT; MELTDOWN; PERFORMANCE TESTING; PERSONNEL; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; RELIABILITY; RESEARCH PROGRAMS; RISK ASSESSMENT; SAFETY ANALYSIS; TESTING
- Descriptors DEC
- ACCIDENTS; ENGINEERED SAFETY SYSTEMS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; SAFETY
Optional Information
- Secondary number(s)
- CONF-890405--.