원자력 발전소 지진사건 확률론적 안전성 분석의 인간신뢰도분석

Abstract

After the Fukushima accident, the safety assessment of NPPs has been proposed by regulators using PSA, one of the safety assessment methods. Institutes such as ASME and IAEA suggest performing seismic event HRAs because earthquakes increase the task that operators must perform manually. For example, there is the operator action of restoring functions or, relay chatter recovery. Seismic event HRA should be carried out to the operator, taking into account the impact of the earthquake. Previously, seismic event HRAs were simply applied to the probability of an internal event human error. Such an analysis does not take into account the effects of the driver from the earthquake. Therefore, it is possible to overestimate or underestimate the probability of operator error. The particular guideline was developed based on the experience of carrying out the selected EPRI seismic event HRA by selecting the seismic event HRA methodology. In the EPRI seismic event HRA methodology, a qualitative assessment by a feasibility assessment is performed, and a quantitative assessment by screening assessment is performed. The EPRI seismic event HRA methodology provides assessment items, but does not provide evaluation criteria or methods. The particular guideline developed can be applied to reduce differences between analysts and to improve consistency in the analysis results. It was also proposed that the EPRI seismic event HRA methodology be applied to the OPR1000 plant and the EPRI seismic event HRA methodology be performed for the actual plant.