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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.
Robert P. Martin
Nuclear Technology | Volume 211 | Number 12 | December 2025 | Pages 2889-2902
Review Article | doi.org/10.1080/00295450.2024.2431778
Articles are hosted by Taylor and Francis Online.
The U.S. Nuclear Regulatory Commission (NRC) is actively updating its regulatory framework with industry stakeholder input under a program called the Licensing Modernization Project (LMP). Improvements are expected to better align the reactor licensing process with the needs of advanced reactor technologies by adopting technology-inclusive language, reducing prescriptive rules, and expanding the role of risk-informed and performance-based issue resolution.
This paper presents a technology-inclusive evaluation model that integrates both risk-based and deterministic features, drawing on data from historical licensing practices, U.S. and international safety standards, and industry case studies. The safety case content of a risked-informed safety analysis report (SAR), such as one consistent with the LMP model in the United States, is expected to logically connect risk insights with the resolution of safety and technical issues. While a mix of deterministic safety and quantitative risk-based evaluation models is explicitly addressed in the NRC’s draft rule [Code of Federal Regulations, Title 10, “Energy,” Part 53, “Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors” (10 CFR 53)], this paper identifies preferred applications for best-estimate plus uncertainty evaluation models in risk-informed SARs for safety margin management, supporting streamlined regulatory review for advanced reactor technologies.