This paper discusses some technical issues related to applying Probabilistic Safety Assessment (PSA) to a novel Nuclear Power Plant (NPP) design. These aspects include: initiating events, passive systems modeling, reliability and common-cause failure (CCF) data, modeling of novel design features, modeling of preventive maintenance and technical specifications, human reliability analysis (HRA), modeling of instrumentation and control (I&C), external hazards, PSA supporting studies and interpretation of PSA results for new plants.

Volume Subject Area:
Nuclear Safety and Security
Topics:
Design, Probabilistic safety assessment, Modeling, Human reliability analysis, Nuclear power stations, Failure, Hazards, Instrumentation, Maintenance, Reliability
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