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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.
Ge-Ping Yu, Bau-Shei Pei, Ying-Pang Ma
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 147-159
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34237
Articles are hosted by Taylor and Francis Online.
A best-estimate transient analysis performed with the RETRAN-02 code is used to demonstrate that two reactor trip setpoints can be modified to improve plant operating margin and eliminate unnecessary reactor trips in the Maanshan three-loop Westinghouse pressurized water reactor. The trip setpoint relaxation analyses involve the steam generator water level and turbine trip. Analytical results show that for a loss-of-secondary-heat-sink event, the steam generator low-low-level reactor trip signal (SGLLRTS) setpoint can be adjusted down from 17 to 5% narrow-range water level span at low power level (<50%) without opening the primary-side power operated relief valves (PORVs). The effects of the automatic control rod on a loss-of-normalfeedwater transient are discussed. The reactor can be tripped by other signals if the SGLLRTS is inhibited at high power level. The turbine trip reactor trip signal setpoint can be lowered from 10 to 30% power. American National Standard design conditions and the prevention of pressurizer PORV opening to avoid a small loss-of-coolant accident are considered the safety criteria for the relaxation of trip setpoints.