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Evans, R.C.; Whitesel, R.N.
Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs1994
Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs1994
AbstractAbstract
[en] The purpose of organization and management development activities in the commercial nuclear power industry is to foster high levels of power plant performance and safety through improved human performance. The NRC has been working to develop assessment tools to assay the effects of organizational factors on plant safety. The utility industry has been working on initiatives targeting individual accountability, the improvement of plant performance and the elimination of the items identified through the NRC assessment process. Organization and management activities do not focus on industry organizational charts, but on the personnel processes and dimensions (factors) that affect safety and economic performance. As individual terms these activities are often combined and referred to as organizational factors. As an area of study, organizational factors has become more prominent as the industry emphasis has switched in recent years from hardware issues related to safety and economics, to personnel-related issues. Beyond the obvious safety objectives affected by improved human performance, plant performance improvements, in areas such as capacity factors, can be achieved through improved human performance. For example, it is estimated that as many as half of the unplanned reactor scrams are caused by personnel errors. The integrated effect of these scram-initiating errors is conservatively estimated to be 100 lost capacity days per year. The financial impact of these events is estimated to be $100M per year
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Monteleone, S. (comp.) (Brookhaven National Lab., Upton, NY (United States)); Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States); 586 p; Apr 1994; p. 293-299; 21. water reactor safety information meeting; Bethesda, MD (United States); 25-27 Oct 1993; Also available from OSTI as TI94011188; NTIS; GPO
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