Simplified Model of Safety Determination Process for a Country with its First Operating Nuclear Power Plants

The two inputs are evaluated and given a color designation based on their safety significance. The performance indicators (PIs) in ROP program were developed from a very large statistical basis given operating experience from 100 reactors over a long period of time. The inspection findings are evaluated in terms of changes in core damage frequency using simplified PRA models and in some cases more complex models. The aim of this paper is to develop a simplified risk assessment approach for inspection findings which does not use PRA directly, but may use direct calculation approach. Thus, it would be helpful for inspectors to determine the safety significance of inspection findings. The objective of this study was to develop a simplified risk assessment approach for inspection findings using direct risk calculation model to determine the safety significance. Risk and categorization scheme are developed to put inspection finding into corresponding ΔCDF category