The extended living probabilistic safety assessment

Author(s):  
Marko Čepin

The term living probabilistic safety assessment was defined soon after the initial probabilistic safety assessments were implemented. The objective of this article is to present the extended living probabilistic safety assessment and its applications considering realistic nuclear power plant models, including the low power and shutdown plant operating states. One of the key objectives is to compare the suitability of conventional and additional risk measures, core damage frequency and conditional core damage frequency, respectively. The methods are presented considering all states of the plant from the full power operation to the low power and shutdown states. The example models of the nuclear power plants and the results of the living probabilistic safety assessment of the plant operating states are discussed. The results show that the risk of low power and shutdown states is generally smaller than the risk of full power operation, but the low power and shutdown plant operating states differ significantly among each other regarding the risk level. The deficiency of living probabilistic safety assessment applied to the plant shutdown states is connected with significantly increased human effort for the analyses, with a significantly greater amount of results and with increased uncertainty of some parameters due to the larger dynamics of actions in the plant shutdown versus the full power operation states. The benefit of the living probabilistic safety assessment applied to the plant low power and shutdown states lays in consideration of all states and potential identification of risk significant states and directions for possible safety improvements.

2010 ◽  
Vol 25 (3) ◽  
pp. 222-228
Author(s):  
Giustino Manna ◽  
Irina Kuzmina ◽  
Jaroslav Holy

Many probabilistic safety assessment studies completed to the date have demonstrated that the risk dealing with low power and shutdown operation of nuclear power plants is often comparable with the risk of at-power operation, and the main contributors to the low power and shutdown risk often deal with human factors. Since the beginning of the nuclear power generation, human performance has been a very important factor in all phases of the plant lifecycle: design, commissioning, operation, maintenance, surveillance, modification, decommissioning and dismantling. The importance of this aspect has been confirmed by recent operating experience. This paper provides the insights and conclusions of a workshop organized in 2007 by the IAEA and the Joint Research Centre of the European Commission, on Harmonization of low power and shutdown probabilistic safety assessment for WWER nuclear power plants. The major objective of the workshop was to provide a comparison of the approaches and the results of human reliability analyses and gain insights in the enhanced handling of human factors.


Author(s):  
Xu Yiquan ◽  
Zhuo Yucheng ◽  
Yang Yajun ◽  
Fu Hao

For china advanced passive (CAP) pressurized water reactor (PWR) nuclear power plant, spent fuel damage risk potentially induced by internal events is assessed. Spent fuel damage frequency (FDF) is quantified by event tree and fault tree model using probabilistic safety assessment (PSA) software RiskSpectrum. For different operation conditions total FDF is 2.05×10−9 per reactor-year which is much lower than core damage frequency (about 2.41×10−7 per reactor-year). By assumption of completely radioactivity releasing, large radioactive release frequency caused by FDF is one order of magnitude lower than that caused by core damage (about 2.38×10−8 per reactor-year). Since the multiple prevention and mitigation measures in CAP PWR nuclear power plant responding to spent fuel pool accidents, the risk of spent fuel pool is much lower than that of reactor core, and the safety goals of nuclear safety guide can be satisfied.


2012 ◽  
Vol 27 (2) ◽  
pp. 189-197
Author(s):  
Giustino Manna ◽  
Jaroslav Holy ◽  
Irina Kuzmina

Since the beginning of the nuclear power generation, human performance has been a very important factor in all phases of the plant lifecycle: design, commissioning, operation, maintenance, surveillance, modification, and decommissioning. This aspect has been confirmed by the operating experience. A workshop was organized by the IAEA and the Joint Research Centre of the European Commission, on Harmonization of low power and shutdown probabilistic safety assessment for WWER nuclear power plants. One of the major objectives of the Workshop was to provide a comparison of the approaches and results of human reliability analyses for WWER 440 and WWER 1000, and gain insights for future application of human reliability analyses in Low Power and Shutdown scenarios. This paper provides the insights and conclusions of the workshops concerning human reliability analyses and human factors.


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