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NRC adopts ROP updates
The Nuclear Regulatory Commission has approved a significant overhaul of its Reactor Oversight Process (ROP) baseline inspection program that stresses a leaner, more risk-focused inspection process.
This adoption comes just over a month after NRC officials published their findings on the proposed ROP changes. The changes would reduce the number of hours spent annually on direct inspections at U.S. nuclear power plants by 38 percent.
Milos I. Atz, Robert A. Joseph, Edward A. Hoffman
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1602-1622
Research Article | doi.org/10.1080/00295450.2023.2287307
Articles are hosted by Taylor and Francis Online.
Advanced nuclear reactors offer various operational advantages over existing light water reactors but could produce types of spent nuclear fuel (SNF) with a wide variety of forms and characteristics depending on how many different concepts are deployed. Each advanced reactor SNF type potentially poses unique management challenges. New planning efforts will be necessary to anticipate how the management requirements of advanced reactor SNF will affect the deployment of an integrated waste management system. This paper applies a framework of high-level facility deployment milestones to a generic SNF management system, reviewing them together with the advanced reactor SNF characteristics and management requirements. This allows for the investigation of factors that influence facility and system deployment, and ultimately, the identification of challenges facing the deployment of different kinds of SNF management facilities.
The back end of the once-through fuel cycle is examined for four advanced reactor system technology types: sodium-cooled fast reactors, high-temperature gas-cooled reactors, liquid-fuel molten salt reactors, and lead-cooled fast reactors. It is observed that milestones earlier in the facility deployment process (e.g., siting and facility design) are more impacted by the uniqueness of advanced reactor SNF characteristics than others (e.g., construction and testing). Ultimately, none of the differences are seen as fundamentally disqualifying in a technical sense; however, they should be considered early, potentially as part of reactor design, to avoid issues in the future.