摘要: An investigation of nonsafety-grade control system failures at Oconee 1 that could lead to rapid steam generator overfill, reactor overcooling, or reactor overheating (inadequate core cooling) has been completed. The safety implic... 展开 An investigation of nonsafety-grade control system failures at Oconee 1 that could lead to rapid steam generator overfill, reactor overcooling, or reactor overheating (inadequate core cooling) has been completed. The safety implications of such control system failures were assessed by performing detailed plant-specific examinations of the interaction between control and safety systems, determining the relative importance of these interactions, and recommending plant design and operation guidelines based on their relative importance. The probabilities of certain events have been estimated to ensure the credibility of this study, and guidance has been provided to broaden the results of this plant-specific analysis to encompass all Babcock and Wilcox pressurized water reactors. 收起