M220721: Slides - Briefing on 10 CFR Part 53 Licensing and Regulation of Advanced Nuclear Reactors - Ucs SlidesML22196A043 |
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07/21/2022 |
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M220721 |
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Category:Commission Meeting Slides
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Johnson - Update on Research and Test Reactors Regulatory Program ML24046A0172024-02-22022 February 2024 M240222A: Slides - J. Dix - Update on Research and Test Reactors Regulatory Program ML24046A0182024-02-22022 February 2024 M240222A: Slides - Staff - Update on Research and Test Reactors Regulatory Program ML24047A0122024-02-22022 February 2024 M240222A: Slides - R. Towell - Update on Research and Test Reactors Regulatory Program ML24047A0132024-02-22022 February 2024 M240222A: Slides - A. Boulanger - Update on Research and Test Reactors Regulatory Program ML24019A1312024-01-19019 January 2024 M240125: Staff Slides - Joint Meeting of the Federal Energy Regulatory Commission (FERC) and the Nuclear Regulatory Commission (NRC) (Part 1) ML24017A1442024-01-17017 January 2024 M240123: Staff Slides - Briefing on International Activities ML24012A1552024-01-12012 January 2024 M240118: Slides - J. 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Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0632023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - E. Lyman - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0642023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - N. Mcmurray - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0652023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - S. Schilthelm - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0662023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - T. Chapman - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0972023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - Staff - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23103A1422023-04-20020 April 2023 M230420: Slides/Supporting Presentation - Strategic Programmatic Overview of the Fuel Facilities and the Spent Fuel Storage and Transportation Business Lines ML23083B3652023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - Z. Mohaghegh - Briefing on Nuclear Regulatory Research Program ML23083B3682023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - V. Rouyer - Briefing on Nuclear Regulatory Research Program ML23083B3642023-03-30030 March 2023 M230330: Agenda - Briefing on Nuclear Regulatory Research Program ML23083B3662023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - D. Pickett - Briefing on Nuclear Regulatory Research Program 2025-02-06
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UCS Perspectives on Part 53 Dr. Edwin Lyman Director of Nuclear Power Safety Climate and Energy Program Union of Concerned Scientists July 21, 2022
The current Part 53 approach remains problematic
- The staffs objective in developing Part 53 (per Commission policy) is to provide the same level of safety and security as currently operating plants
- But the current draft does not clearly provide for levels of safety and security equivalent to the operating fleet
- Rule text does not define the frequency cutoff between DBAs and non-DBA LBEsand even if it did, it is unclear how it would compare to operating LWRs
- RES project to apply the LMP to operating plants could help establish a basis for comparisonwhats its status?
- Incorporation of the QHOs as fundamental acceptance criteria will allow licensing of plants less safe than the current fleet
- Proposed Section 73.100 is completely divorced from current physical protection requirements 2
Margin to QHOs has increased
- Part 53 does need specific, quantitative acceptance criteria for limiting the risk of (non-DBA) LBEs, but the QHOs are not the right ones
- QHOs represent the (minimum) level of safety of the fleet as it was 30 years ago
- SRM-SECY-89-102 (Implementation of the Safety Goals) pointed out that operating plants circa 1990 already met the QHOs with margin
- Todays operating plant average core damage frequency is 10 times lower than in 1990
- Vogtle Level 3 PRA finds a hundred-fold margin to the latent cancer fatality QHO and a million-fold margin to the prompt fatality QHO 3
Decrease in Average Core Damage Frequency 4
D. True and J. Butler, The nexus between safety and operational performance, Nuclear News, May 2020
QHOs need to be revised
- Unless the rule includes a specific requirement to maintain a large margin to QHOs, Part 53 applicants could have much higher core damage frequencies than the current fleet and still meet the QHOs
- Absence of societal risk metric (land contamination)
- Use of average cancer fatality risk is inherently discriminatory
- Insensitive to the fact that Blacks and other disadvantaged populations have lower cancer survival rates than Whites
- Growing evidence of non-cancer endpoints for low-level radiation exposure (e.g. cardiovascular disease) 5
Revised QHOs (cont.)
- Be reduced by at least one order of magnitude
- Incorporate cancer incidence rather than cancer mortality, consider other disease endpoints as information becomes available
- Include land contamination (risk of long-term relocation) 6
PRA issues
- A Level 3 PRA, including all hazards, modes, and sources of potential radiological release will be necessary to support Framework A licensing
- The recent publication of the first part of the Vogtle Level 3 PRA illustrated the significant time and resources required for such an effort, even for a well-studied reactor design with significant operating experience
- Can applicants develop a high-quality and sufficiently complete Level 3 PRA for advanced reactors in the timeframe needed for licensing?
7
Framework B/AERI Approach
- Our preliminary assessment is that the AERI approach in Framework B looks generally reasonable (pending a more detailed review)
- However, the same caveats regarding the QHOs apply here as well
- It remains unclear what additional value is added by the entry criterion for use of Framework B.
Applicants could just as well do a direct comparison of the bounding event to the (hopefully revised) QHOs for screening 8
Proposed Section 73.100
- 73.100 is a completely arbitrary and irresponsible gutting of NRCs physical protection requirements but would be available for use by any Part 53 applicant
- Would place an undue burden on NRC inspectors and analysts
Policy decisions that the NRC should reconsider
- Safety goal for advanced reactors:
- Given the performance of the current generation of plants, I believe a safety goal for these plants is not good enough for the future to argue that the level of safety that is achieved by plant designs that are over 10 years old is good enough for the next generation is to have little faith in the ingenuity of engineers and in the potential for nuclear technology.
I would have required the next generation of plants to be substantially safer than the currently operating plants. - 1986 Safety Goal Policy Statement, Separate Views of Commissioner Asselstine 10
Policy issues (cont.)
- Use of safety goals in licensing:
- Safety goals are to be used in a more generic sense and not to make specific licensing decisions. - SRM-SECY-89-102, June 1990.
- Staffs proposed incorporation of QHOs into the Part 53 rule text would arguably be inconsistent with this position
- Important to establish an updated basis for this significant policy change 11
No need for speed
- The nuclear industry is trying to pressure the NRC to radically accelerate licensing reviews for new, untested, paper reactors (see NEI June 7, 2022 letter to NRR)
- The NRC must not compromise its fundamental safety and security obligations to the public based on a false sense of urgency
- UCS sees no evidence that the current Part 53 approach involves significant increases in regulatory burden, as NEI alleges 12
Conclusions
- The Commission should develop revisions to the relevant policy statements and positions to provide a clear basis for Part 53 moving forward
- The absence of a regulatory basis document for the rule is compromising the publics ability to understand its technical underpinnings and allows for the arbitrary addition of provisions without any clear technical justification such as Section 73.100
- Trying to include all this content in the Part 53 Statement of Considerations will be a heavy lift 13
14 Acronyms
- AERI: Alternative Evaluation for Risk Insights
- CDF: Core Damage Frequency
- DBA: Design-Basis Accident
- LBE: Licensing Basis Event
- LMP: Licensing Modernization Project
- QHOs: Quantitative Health Objectives