TY - GEN
T1 - Considerations for the Risk-Informed Performance-Based Regulatory Treatment of Non-Core Sources of Radioactivity for Advanced Reactors
AU - Grabaskas, David
AU - Chen, Ben
AU - Ferrara, Scott
AU - Christensen, Jason
AU - Andrus, Jason
N1 - Funding Information:
The current effort is supported by the U.S. Department of Energy (DOE), Advanced Reactor Demonstration Program (ARDP) Regulatory Development, Regulatory Framework Modernization area, which seeks to address potential regulatory challenges for advanced reactor vendors currently, or soon-to-be, initiating the licensing process. The current effort seeks to aid the advanced reactor industry and regulatory bodies in understanding and addressing the assessment of non-core sources of radioactivity in advanced reactor designs utilizing a RIPB pathway, such as the LMP approach. As a first step in the process, the current work seeks to identify high-level considerations and potential impediments that may require additional efforts or regulatory interaction to resolve. To achieve this goal, the project utilized the multi-step approach, outlined in Figure 1. Complete analysis details are available in ref [7], with an overview of major findings and recommendations provided in the current work.
Funding Information:
The submitted manuscript has been created by UChicago Argonne, LLC, Operator of Argonne National Laboratory ("Argonne"). Argonne, a U.S. Department of Energy Office of Science laboratory, is operated under Contract No. DE-AC02-06CH11357. This work is supported by the U.S. Department of Energy, Office of Nuclear Energy, Advanced Reactor Demonstration Program, Advanced Reactors Regulatory Development Area.
Publisher Copyright:
© 2023 Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023. All Rights Reserved.
PY - 2023
Y1 - 2023
N2 - The recently published ASME/ANS Non-LWR Probabilistic Risk Assessment (PRA) Standard, which has been endorsed by the U.S. Nuclear Regulatory Commission (NRC) in RG 1.247, allows the incorporation of all radioactive sources at the site into the plant PRA. This includes non-core sources of radioactivity, such as fuel storage, purification systems, and fuel processing systems. For those non-LWR vendors who are utilizing risk-informed performance-based (RIPD) licensing approaches, such as the Licensing Modernization Project (LMP), there is an opportunity to include the non-core sources of radioactivity within the RIPB licensing framework for regulatory decision-making. This work explores the use of a RIPB approach for the licensing of regulated material under 10 CFR parts 30-35, 40, 70, and 72, including an assessment of regulatory criteria and available guidance compared with those utilized in the LMP approach. Synergies and potential challenges are identified as part of this crosswalk and recommendations, along with items for future development, are described.
AB - The recently published ASME/ANS Non-LWR Probabilistic Risk Assessment (PRA) Standard, which has been endorsed by the U.S. Nuclear Regulatory Commission (NRC) in RG 1.247, allows the incorporation of all radioactive sources at the site into the plant PRA. This includes non-core sources of radioactivity, such as fuel storage, purification systems, and fuel processing systems. For those non-LWR vendors who are utilizing risk-informed performance-based (RIPD) licensing approaches, such as the Licensing Modernization Project (LMP), there is an opportunity to include the non-core sources of radioactivity within the RIPB licensing framework for regulatory decision-making. This work explores the use of a RIPB approach for the licensing of regulated material under 10 CFR parts 30-35, 40, 70, and 72, including an assessment of regulatory criteria and available guidance compared with those utilized in the LMP approach. Synergies and potential challenges are identified as part of this crosswalk and recommendations, along with items for future development, are described.
KW - advanced reactors
KW - LMP
KW - non-core sources
KW - Risk-informed performance-based
UR - http://www.scopus.com/inward/record.url?scp=85184353851&partnerID=8YFLogxK
UR - https://www.mendeley.com/catalogue/f373be48-d68c-362a-a64e-cce90f660f4c/
U2 - 10.13182/PSA23-41165
DO - 10.13182/PSA23-41165
M3 - Conference contribution
AN - SCOPUS:85184353851
SN - 9780894487927
T3 - Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023
SP - 178
EP - 187
BT - Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023
PB - American Nuclear Society
T2 - 18th International Probabilistic Safety Assessment and Analysis, PSA 2023
Y2 - 15 July 2023 through 20 July 2023
ER -