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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.
Mansur A. Alammar, Ronald V. Furia, Jimmy H. Chin, Chandrakant B. Mehta
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 353-366
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34148
Articles are hosted by Taylor and Francis Online.
The development of the Oyster Creek RETRAN licensing model is presented. A three-step program was followed, namely:Step 1. Model benchmark against start-up tests: The objective here was to assure model stability and to qualify different segments of the model against plant data. A best-estimate model was thus established at this stage. Nine start-up tests were used.Step 2. Assurance that the model has built-in conservatism with respect to the reload transients it is designed to analyze. Here, a sensitivity study was carried out on a number of parameters for the limiting reload transient for Oyster Creek [turbine trip without bypass (TTWOB)]. The impact on the critical power ratio was used as the primary measure. Results from this study were used in establishing a conservative set of parameters, an uncertainty margin, and a proper choice of code options. The implementation of these results established the licensing model.Step 3. Testing the licensing model response against vendor’s analyses for typical reload transients, namely, TTWOB, main steam isolation valve closure without scram, and feedwater controller failure in maximum demand. This methodology has been submitted for U.S. Nuclear Regulatory Commission approval.