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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
Truong V. Vo, Timothy M. Mitts, Tyrone R. Blackburn, Hanh K. Phan
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 179-193
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35248
Articles are hosted by Taylor and Francis Online.
A risk assessment of potential events at Susquehanna Steam Electric Station (SSES) is described wherein a loss of cooling occurs in a spent-fuel pool (SFP). This evaluation was performed as part of the evaluation of potential generic issue 93-01, regarding the safety impact of incidents involving the loss of SFP cooling (SFPC). The analysis investigates allegations and concerns identified in a Title 10, Part 21 Code of Federal Regulations (10 CFR 21) report filed by two former contract employees, who alleged that SSES has design deficiencies associated with SFPC that make it susceptible to unsafe conditions. The evaluation estimates the likelihood of a loss-of-SFPC event at SSES and the associated probability of the SFP heating up to nearboiling conditions. The evaluation also includes an assessment for such near-boiling events for their contribution to core damage and an estimate of order-of-magnitude core damage frequency. The analysis addresses SSES plant conditions that existed prior to the 10 CFR 21 report and also current plant conditions. Data for this analysis were obtained from the SSES licensee and from other relevant data sources, including probabilistic risk assessment information. Background for the evaluations performed, the methodology used in the evaluation, the data and modeling used for the analyses, the analysis techniques and results, and conclusions are presented.