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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.
Stanley Rosen, Richard D. Ivany, John F. Kapinos, Suk K. Sim
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 89-94
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34444
Articles are hosted by Taylor and Francis Online.
Combustion Engineering’s advanced light water reactor, System 80+, is an evolutionary upgrade of the proven System 80® nuclear steam supply system design. While both plants are rated at 3817 MW(thermal), System 80+ incorporates a number of design enhancements, including direct vessel injection for the safety injection (SI) system and other changes to the reactor cooling system. The results of a best-estimate small-break loss-of-coolant accident (LOCA) study that addresses utility investment protection concerns is presented. Specifically, the size piping break that can be tolerated without the liquid or two-phase fluid level falling below the top of the active core is addressed. Using best-estimate analytical procedures, and assuming no single failure, the active core remains covered with substantial margin for breaks up to 0.254-m (10-in.) diameter. This reduces the possibility of core damage due to a small LOCA. A large-break, cold-leg LOCA licensing analysis is also presented that addresses the reflood capability after the end of SI tank discharge without credit for a low-pressure SI pump system. This analysis confirms that the improved high-pressure SI system provides adequate reflood capability to satisfy the U.S. Nuclear Regulatory Commission LOCA licensing criteria.