The Impact of SAG on the Level 2 PSA Results of the ChinShan Nuclear Power Plant

• Main Authors: Kuan-Fu Chen, 陳冠甫
• Other Authors: Min Lee
• Format: Others
• Language: zh-TW
• Published: 2005
• Online Access: http://ndltd.ncl.edu.tw/handle/98977122217331435692

碩士 === 國立清華大學 === 工程與系統科學系 === 93 === Probability Safety Assessment (PSA) is a systematic approach to estimate the risk of nuclear power plants (NPPs). PSA has been widely utilized by nuclear utilities, nuclear industry, and nuclear regulators to enhance the safety of NPPs. Over the past few years, Severe Accident Guidelines (SAGs), which delineate the mitigation actions of core meltdown accidents of NPP, are developed to support operators and staffs in the Technical Support Center (TSC) during the emergency responses of core melt accidents. The proper executions of SAGs could decrease the failure probability of containment and reduce the amount of radionuclide released to the environment during the accident. It can be expected that the implementation of SAGs will reduce the risk of the operation of NPPs. However, SAGs are not available when the conventional Level-2 PSA analyses are performed. In this study the mitigation actions of SAGs are incorporated into the Level-2 PSA of a General Electric designed Boiling Water Reactor (BWR) with Mark I containment. The plant analyzed is ChinShan Nuclear Power Plant of Taiwan Power Company (TPC). The purposes of the study are to assess the impact of SAGs on the risk of NPP and to identify the importance measure of these mitigation actions. MAAP code calculations are performed to verify and validate the mitigation actions specified in SAGs. This thesis summarizes the results of the study.