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Feb 20, 2024

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Describe the NRC’s role in the licensing of individuals who operate the controls of a nuclear power plant. With regard to nuclear reactor operator license examinations, what specific ability does the senior reactor license exam measure that the reactor operator license exam does not? The NRC controls the licensing process of nuclear power plants, requiring testing and requalification to maintain the license. Application for a Reactor Operator (RO) or Senior Reactor Operator (SRO) license requires years of experience and training, both in an educational and on-the-job capacity. The training requirements are robust, including theory, physical system knowledge, and operational and emergency actions. Training programs are developed by the power plants, under the guidance and review of the NRC to ensure that these rigorous requirements are met successfully. The application process even includes mental and physical testing to ensure that the person is capable of reliable operation, beyond their skillset and scope of knowledge. The RO exam and SRO exam are similar in their intensity, and both requires 24-month recertification to maintain. Because the SRO is a more experienced and supervisory role, the testing includes their ability to act in this manner overseeing the RO. Compare the Two-Step Licensing Process (10 CFR Part 50) with the Combined License Process (10 CFR Part 52). The NRC also controls the licensing for nuclear power plants themselves, ensuring that plant designs, locations, and systems are safe and secure for the planned operations. This was originally accomplished using the Two-Step process, governed under 10 CFR Part 50. This process required a submittal and approval of a safety report for the design, which once reviewed, discussed, and approved, would allow for a construction permit to be issued. Once construction was complete, a final safety report and inspection would commence prior to the actual operating license being issued, to ensure adherence to design and quality implementation. Part 52 simplified the process, allowing the prospective licensee to apply for a combined license, which allows for construction and some authority to operate, subject to compliance with the approved design. This streamlined the application and construction process, as well as allowed for such things and standardized designs and early-construction permits. Both options are still available for applications. Describe the Maintenance Rule (10 CFR 50.65). What drove the NRC to implement the rule? What systems are included in the scope of the rule and what is the basis of their inclusion? The Maintenance Rule enforces the requirement of nuclear facilities to design, implement, and maintain a comprehensive preventative maintenance plan for their equipment and systems, for both critical and supporting systems in relation to safety. This requirement came into existence due to recurring events of shutdowns and safety issues regarding poor maintenance practices. This included direct reactor systems, such as containments and cooling, as well as non-safety systems, that could cascade into an effect on safety systems. Describe the relationship between quantitative risk assessment and the Maintenance Rule. What impact has the Maintenance Rule had on the planning of plant’s refueling outages?

Quantitative risk assessment of maintenance is imperative, requiring that the effects of planned maintenance must be analyzed from a perspective of safety and continued operation. Factors such as shutdown time affecting power generation, as well as worker health and safety effects of various maintenance tasks, all play a factor in how the maintenance schedule should be most reasonably accomplished. This influenced many licensees to carefully schedule their refueling shutdowns to maximize the maintenance availability, minimizing further down time and potential effects on personnel. Describe the seven cornerstones of the NRC oversight process. How do these seven cornerstones support the three key areas of plant performance? The cornerstones of Reactor Oversight are the major portions of plant operations and design that support the three key areas, specified as Reactor Safety, Radiation Safety, and Safeguards. Although a good summary of the main aspects of safe operation, those are broad and vague terms, and the cornerstones help to more effectively implement oversight into maintaining safety. The seven cornerstones, Initiating Events, Mitigating Systems, Barrier Integrity, Emergency preparedness, Occupational Radiation Safety, Public Radiation Safety, and Physical Protection, all allow the NRC to more specifically inspect and monitor the key areas of plant performance. Having more accurate and defined categories creates a structure in which performance can be effectively monitored, and improvements can be made while weak areas are improved. Together with the cross- cutting areas, this provides a strong framework of inspection and corrective action. NRC: Backgrounder on Nuclear Power Plant Licensing Process . (2018). Nrc.gov. https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/licensing-process-fs.html Backgrounder on Reactor Operator Licensing . (n.d.). NRC Web. https://www.nrc.gov/reading-rm/doc- collections/fact-sheets/operator-licensing.html NRC Reactor Oversight Process. (Dec, 2006). U.S. NRC. https://www.nrc.gov/docs/ML0708/ML070890365.pdf Perspectives on Reactor Safety (NUREG/CR-6042, SAND93-0971, Revision 2) . (n.d.). NRC Web. https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6042/index.html

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