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Category:Meeting Briefing Package/Handouts
MONTHYEARML24305A2162024-11-0505 November 2024 ACRS NuScale Sdaa FSAR Chapters 3, 8, 14 Subcommittee Meeting - Final ML24269A0772024-10-0202 October 2024 Presentation Slides for the July 17, 2024, Quarterly Observation Public Meeting on the Status of Nuscales US460 Standard Design Approval Application ML24229A1572024-08-22022 August 2024 ACRS NuScale Sdaa FSAR Chapters 7, 9, 12, 18 Subcommittee Meeting ML24194A0902024-07-17017 July 2024 Presentation Slides for the July 17, 2024, Quarterly Public Meeting on the Status of NuScales US460 Standard Design Approval Application ML24099A0322024-04-11011 April 2024 Presentation Slides for the April 11, 2024, Quarterly Observation Public Meeting on the Status of NuScale US460 Standard Design Approval Application ML24039A1492024-02-0606 February 2024 Staff ACRS Open Session Presentation Slides for Safety Evaluation for NuScale Topical Reports TR-108601-P Rev 4 and TR-0715-50350-P Rev 3 ML24024A1882024-01-30030 January 2024 Presentation Slides for the January 30, 2024, Quarterly Observation Public Meeting on the Status of NuScales US460 Standard Design Approval Application ML23206A0062023-07-27027 July 2023 NRC 2nd Public Meeting Presentation on Risk Insights and Severe Accident Vulnerability Information for LWR CP Applications ML23230A0072023-07-26026 July 2023 Presentation Slides for the July 26, 2023, Observation Public Meeting on the Status of NuScales US460 Standard Design Approval Application ML23116A0872023-04-25025 April 2023 Sdaa - NuScale-NRC Management Public Meeting Presentation ML22091A0412022-04-0707 April 2022 NRC Staff ACRS Fc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML22080A0062022-03-18018 March 2022 NRC Staff ACRS Sc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML22095A2062022-03-18018 March 2022 NRC Staff Public Presentation ACRS Subcommittee Meeting on BWRX-300 Containment Evaluation Method-Public ML21295A6222021-10-22022 October 2021 Slides for the October 27 2021 Public Meeting with NuScale ML21293A2332021-10-20020 October 2021 Us Update - 27th Wgrnr Meeting Updated ML21293A0412021-10-19019 October 2021 Slovenia Nuclear Innovation Seminar, Regulatory Frameworks for Nuclear Safety- MID-FINAL ML21274A0762021-09-29029 September 2021 Sept 29 2021 Adv Rx Stakeholder Meeting Slides ML21028A4432021-01-28028 January 2021 ACRS Fc NRC Staff Public LTR BWRx-300 Containment Performance Final Slides ML20204A7642020-07-22022 July 2020 Staff Backup Slides ACRS Fc 07/21/2020 ML20171A4092020-06-19019 June 2020 NRC Risk Tool ML20113E8392020-04-28028 April 2020 Approach for a New Regulatory Guidance Infrastructure for Digital Instrumentation and Control (I&C) ML20107F7582020-04-15015 April 2020 Slides for April 15, 2020 NuScale Boron Redistribution Audit Status Public ML20021A2212020-01-22022 January 2020 Workshop on Spent Fuel Performance Margins ML19304A0392019-11-20020 November 2019 Preliminary Recommendations for Modernization of the Nrc'S Digital I&C Regulatory Infrastructure 2024-08-22
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24305A2162024-11-0505 November 2024 ACRS NuScale Sdaa FSAR Chapters 3, 8, 14 Subcommittee Meeting - Final ML24269A0772024-10-0202 October 2024 Presentation Slides for the July 17, 2024, Quarterly Observation Public Meeting on the Status of Nuscales US460 Standard Design Approval Application ML24229A1572024-08-22022 August 2024 ACRS NuScale Sdaa FSAR Chapters 7, 9, 12, 18 Subcommittee Meeting ML24194A0902024-07-17017 July 2024 Presentation Slides for the July 17, 2024, Quarterly Public Meeting on the Status of NuScales US460 Standard Design Approval Application ML24099A0322024-04-11011 April 2024 Presentation Slides for the April 11, 2024, Quarterly Observation Public Meeting on the Status of NuScale US460 Standard Design Approval Application ML24039A1492024-02-0606 February 2024 Staff ACRS Open Session Presentation Slides for Safety Evaluation for NuScale Topical Reports TR-108601-P Rev 4 and TR-0715-50350-P Rev 3 ML24024A1882024-01-30030 January 2024 Presentation Slides for the January 30, 2024, Quarterly Observation Public Meeting on the Status of NuScales US460 Standard Design Approval Application ML23206A0062023-07-27027 July 2023 NRC 2nd Public Meeting Presentation on Risk Insights and Severe Accident Vulnerability Information for LWR CP Applications ML23230A0072023-07-26026 July 2023 Presentation Slides for the July 26, 2023, Observation Public Meeting on the Status of NuScales US460 Standard Design Approval Application ML23116A0872023-04-25025 April 2023 Sdaa - NuScale-NRC Management Public Meeting Presentation ML23087A2102023-03-28028 March 2023 NRC Public Meeting Presentation on Risk Insights and Severe Accident Vulnerability Information for LWR CP Applications ML22091A0412022-04-0707 April 2022 NRC Staff ACRS Fc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML22080A0062022-03-18018 March 2022 NRC Staff ACRS Sc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML22095A2062022-03-18018 March 2022 NRC Staff Public Presentation ACRS Subcommittee Meeting on BWRX-300 Containment Evaluation Method-Public ML22013A3872022-01-13013 January 2022 01-2022 Staff Presentation to ACRS on New and Advanced Reactor Licensing Processes ML22048A5192021-12-31031 December 2021 PNNL Perspectives Report on Enhancing Environmental Justice Activities at the NRC ML21295A6222021-10-22022 October 2021 Slides for the October 27 2021 Public Meeting with NuScale ML21293A2332021-10-20020 October 2021 Us Update - 27th Wgrnr Meeting Updated ML21293A0412021-10-19019 October 2021 Slovenia Nuclear Innovation Seminar, Regulatory Frameworks for Nuclear Safety- MID-FINAL ML21274A0762021-09-29029 September 2021 Sept 29 2021 Adv Rx Stakeholder Meeting Slides ML21195A0322021-07-14014 July 2021 EPZ Slides for the July 14 2021 Public Meeting with NuScale ML21028A4432021-01-28028 January 2021 ACRS Fc NRC Staff Public LTR BWRx-300 Containment Performance Final Slides ML20204A7642020-07-22022 July 2020 Staff Backup Slides ACRS Fc 07/21/2020 ML20171A4092020-06-19019 June 2020 NRC Risk Tool ML20113E8392020-04-28028 April 2020 Approach for a New Regulatory Guidance Infrastructure for Digital Instrumentation and Control (I&C) ML20107F7582020-04-15015 April 2020 Slides for April 15, 2020 NuScale Boron Redistribution Audit Status Public ML20021A2212020-01-22022 January 2020 Workshop on Spent Fuel Performance Margins ML19304A0392019-11-20020 November 2019 Preliminary Recommendations for Modernization of the Nrc'S Digital I&C Regulatory Infrastructure 2024-08-22
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NRC Licensing of Small Modular Reactors (SMRs)
Purpose
- The purpose of this section is to provide an understanding of the differences that the NRC is encountering with licensing SMRs (small light-water reactor technology)
Modular designs Nuclear safety review areas Environmental review areas SMR review challenges SMR lessons-learned
2 Differences in Licensing SMRs
- In general, the same regulatory framework applies to SMRs as to large LWRs; however, gaps may exist
- Gaps in regulatory and guidance documents are a continually evolving challenge
- Gaps change according to changes in technologies and approaches
- Addressing gaps in a completely technology-neutral, meaningful way is difficult
3 Differences in Licensing SMRs
- Not all gaps warrant the same amount of NRC focus or resources Safety or security significance Likelihood of guidance in that area actually being needed Timing of the need
- The NRC is always scanning the horizon for future gaps and prioritizing them
4 Part 50 vs. Part 52 Licensing
2 -step licensing - Part 50Alternative licensing - Part 52
Preliminary Safety Analysis Report Early Site Permit Design Certification
Construction Permit Site/design information
Construction and further design Final Safety Analysis Report
Final Safety Construction Combined License Analysis Report complete Operating License Construction
Operation* Verification (ITAAC)
- Includes Pre-operational testing Operation*
5 Nuclear Safety Review Areas
- Site Characteristics and Site Parameters
- Systems, Structures, Components, and Equipment Design
- Engineered Safety Features
- Digital Instrumentation and Controls/Electrical Power
- Steam and Power Conversion Systems
- Radioactive Waste Management and Radiation Protection
- Initial Test Program and ITAAC
- Quality Assurance Program
- Human Factors Engineering
6 Environmental Review Areas
- Demography (population distribution)
- Radiological Effluent Releases
- Radiological Dose Consequences
- Security Plan Feasibility
7 SMR Review Challenges
- New first-of-a-kind designs Modular construction Completeness of the design Applicability of existing regulations Verification and validation of computer codes Applicability of prior operating experience
- Smaller applicant organizations in some cases Important that they have experience with nuclear licensing requirements Important that they are adequately staffed to address regulator questions in a timely manner during reviews
8 Modular Designs - AP1000 Modules
CA01 Steam Generator / Refueling Channel CA02 In-Containment Refueling W ater Storage Tank (IRW ST) Interior W all CA03 IRW ST Perimeter W all CA04 Reactor Vessel Cavity CA05 Access Tunnel / Passive Core Cooling and Volume Control System Equipment Room W all CA20 Aux Building
9 SMR Lessons-Learned
- A rigorous safety basis and understanding is still essential for new designs
- If an organization is mostly familiar only with large light water reactors (LWRs), a mindset change may need to occur
- Sustained focus on the most safety-significant aspects of the design is important
- Complete understanding of the design as a whole assists the applicant and the regulator
- Successful completion of first-of-a-kind reviews will result in streamlined Nth-of-a-kind reviews
- Early and frequent communication with applicants is crucial, both prior to and during the regulator s review
10 NRC Licensing of Advanced Reactors Purpose
- The purpose of this section is to provide an understanding of the differences that the NRC is encountering with licensing Advanced Reactors (small non-light water reactor technology)
Advanced Reactor design landscape Ensuring readiness for licensing Advanced Reactor designs
12 New Non-Light Water Licensing
Companies in active pre-application engagement:
X-Energy TerraPower & GE-Hitachi Oklo Aurora - first Ka i ro s Powe r advanced reactor Terrestrial Energy USA licensing application General Atomics Energy submitted March 2020. Microreactor - Westinghouse Electric Company 1.5 MWe
13 Broad Landscape of Advanced Reactor DesignsAdvanced Reactor Landscape
Liquid Metal Cooled Fast High-Temperature Gas -Cooled Molten Salt Reactors Micro Reactors Reactors (MSR) Reactors (LMFR) (HTGR)
TerraPower/GEH Kairos
(Natrium)* X-energy
- GEH PRISM (VTR) Framatome Kairos (HermeslRTR) BWX Technologies
Advanced Reactor Liquid Salt Cooled X-energy Concepts StarCore Sodium-Cooled MIT Radiant l RTR Terrestrial
Westinghouse TRISO Fuel TerraPower Ultra Safe Columbia Basin Southern (TP MCFR) lRTR University of Illinois RTR
Hydromine General Atomics (EM2)* ACU lRTR
Lead-Cooled General Atomics Elysium Stationary ThorCon LEGEND ARDP Awardees Muons Demo Reactors In Licensing Review Flibe
Risk Reduction
- Preapplication Alpha Tech ARC-20 RTR Research/Test Reactor Liquid Salt Fueled
14 Ensuring Readiness for Licensing
15 Ensuring Readiness for Licensing
- Risk-Informed Performance-Based Licensing Approaches Draft Regulatory Guide (DG) 1353
16 Questions?