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Category:Meeting Agenda
MONTHYEARPMNS20241422, Meeting with Constellation Energy Generation, LLC to Discuss a Planned License Amendment Request for a Digital Instrumentation and Controls Upgrade at Peach Bottom Atomic Power Station, Units 2 and 32024-11-21021 November 2024 Meeting with Constellation Energy Generation, LLC to Discuss a Planned License Amendment Request for a Digital Instrumentation and Controls Upgrade at Peach Bottom Atomic Power Station, Units 2 and 3 PMNS20241374, Public Meeting with Industry Operator Licensing Representatives2024-11-21021 November 2024 Public Meeting with Industry Operator Licensing Representatives PMNS20241453, Meeting to Discuss Sections of the National Organization of Test, Research and Training Reactors, Inc. (Trtr) Proposed Guidance on the 50.59 Process for Digital Applications (NEI 23-03) with the U. S. Nuclear Regulatory Commission (NRC)2024-11-21021 November 2024 Meeting to Discuss Sections of the National Organization of Test, Research and Training Reactors, Inc. (Trtr) Proposed Guidance on the 50.59 Process for Digital Applications (NEI 23-03) with the U. S. Nuclear Regulatory Commission (NRC) Sta PMNS20241443, Advance Act Section 507: Operating Reactor Oversight and Inspection Proposed ROP Revisions2024-11-20020 November 2024 Advance Act Section 507: Operating Reactor Oversight and Inspection Proposed ROP Revisions PMNS20241440, Advanced Reactor Construction Oversight Process (Arcop) Workshop 5, Safety Culture Assessment2024-11-19019 November 2024 Advanced Reactor Construction Oversight Process (Arcop) Workshop 5, Safety Culture Assessment PMNS20241350, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Unit 2, Fitness for Duty Exemption2024-11-19019 November 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Unit 2, Fitness for Duty Exemption PMNS20241417, Public Pre-submittal Meeting with the Nuclear Regulatory Commission Staff and NextEra Energy Seabrook LLC (NextEra) Regarding a Proposed License Amendment Request (LAR) Related to Seabrooks Off-site Power Sources2024-11-19019 November 2024 Public Pre-submittal Meeting with the Nuclear Regulatory Commission Staff and NextEra Energy Seabrook LLC (NextEra) Regarding a Proposed License Amendment Request (LAR) Related to Seabrooks Off-site Power Sources PMNS20241432, Periodic Public Meeting to Discuss Possible Efficiencies for the Subsequent License Renewal Review2024-11-18018 November 2024 Periodic Public Meeting to Discuss Possible Efficiencies for the Subsequent License Renewal Review PMNS20241353, Reactor Oversight Process Public Meeting2024-11-18018 November 2024 Reactor Oversight Process Public Meeting PMNS20241401, U.S. Nuclear Regulatory Commission Hybrid Public Outreach Meeting on the Potential Palisades Nuclear Plant Restart2024-11-18018 November 2024 U.S. Nuclear Regulatory Commission Hybrid Public Outreach Meeting on the Potential Palisades Nuclear Plant Restart PMNS20240976, Public Meeting to Discuss Potential Enhancements to Power Uprate Applications and Reviews2024-11-14014 November 2024 Public Meeting to Discuss Potential Enhancements to Power Uprate Applications and Reviews PMNS20241423, Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application2024-11-14014 November 2024 Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application PMNS20241424, Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application2024-11-14014 November 2024 Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application ML24318C4632024-11-13013 November 2024 Presubmittal Teleconference with Wolf Creek Nuclear Operating Corporation Regarding a Planned License Amendment Request for Wolf Creek Generating Station, Unit 1 PMNS20241393, Us Nuclear Regulatory Commission (NRC) Public Meeting with Industry on Implementation of 12-YEAR Inservice Inspection Interval Via Code Case N-9212024-11-13013 November 2024 Us Nuclear Regulatory Commission (NRC) Public Meeting with Industry on Implementation of 12-YEAR Inservice Inspection Interval Via Code Case N-921 PMNS20241337, Pre-Application Public Meeting for Subsequent License Renewal Application - Edwin I. Hatch Nuclear Plant, Units 1 and 22024-11-12012 November 2024 Pre-Application Public Meeting for Subsequent License Renewal Application - Edwin I. Hatch Nuclear Plant, Units 1 and 2 PMNS20241387, Pre-submittal Meeting for a Proposed License Amendment Request (LAR) to Move Surveillance Requirements from Engineered Safety Feature Actuation System (ESFAS) Actuation Logic for Vogtle, Units 3 and 42024-11-10010 November 2024 Pre-submittal Meeting for a Proposed License Amendment Request (LAR) to Move Surveillance Requirements from Engineered Safety Feature Actuation System (ESFAS) Actuation Logic for Vogtle, Units 3 and 4 PMNS20241355, Annual Industry / U.S. Nuclear Regulatory Commission Nondestructive Examination (NDE) Technical Information Exchange Public Meeting2024-11-0808 November 2024 Annual Industry / U.S. Nuclear Regulatory Commission Nondestructive Examination (NDE) Technical Information Exchange Public Meeting PMNS20241361, Meeting with Constellation Energy Generation, LLC Regarding Digital Modernization License Amendment Request for Limerick Generating Station, Units 1 and 22024-11-0707 November 2024 Meeting with Constellation Energy Generation, LLC Regarding Digital Modernization License Amendment Request for Limerick Generating Station, Units 1 and 2 PMNS20241383, Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 22024-11-0707 November 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 2 PMNS20241412, Meeting to Discuss Sections of the National Organization of Test, Research and Training Reactors, Inc. (Trtr) Proposed Guidance on the 50.59 Process for Digital Applications (NEI 23-03) with the U. S. Nuclear Regulatory Commission (NRC)2024-11-0707 November 2024 Meeting to Discuss Sections of the National Organization of Test, Research and Training Reactors, Inc. (Trtr) Proposed Guidance on the 50.59 Process for Digital Applications (NEI 23-03) with the U. S. Nuclear Regulatory Commission (NRC) Sta PMNS20241409, Notice of Meeting with Northern States Power Company2024-11-0707 November 2024 Notice of Meeting with Northern States Power Company PMNS20241406, Pre-Submittal Meeting Regarding a Proposed License Amendment Request to Revise Various Technical Specification Shutdown Actions Mode Change Restrictions2024-11-0707 November 2024 Pre-Submittal Meeting Regarding a Proposed License Amendment Request to Revise Various Technical Specification Shutdown Actions Mode Change Restrictions PMNS20241276, Pre-Application Meeting with Constellation Energy Generation, LLC, (Constellation) Regarding Potential Alternative for Reactor Pressure Vessel Stud Examinations2024-11-0606 November 2024 Pre-Application Meeting with Constellation Energy Generation, LLC, (Constellation) Regarding Potential Alternative for Reactor Pressure Vessel Stud Examinations PMNS20241312, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specification 3.4.14 Related to Reactor Coolant System Pressure Isolation Valve Leakage2024-11-0606 November 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specification 3.4.14 Related to Reactor Coolant System Pressure Isolation Valve Leakage PMNS20241405, Public Meeting to Discuss the Part 53 Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors Rulemaking - Proposed Rule2024-11-0606 November 2024 Public Meeting to Discuss the Part 53 Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors Rulemaking - Proposed Rule PMNS20241410, Discussion on Alternative Risk-informed, Technology-inclusive Approaches to Advanced Reactor Regulation2024-11-0606 November 2024 Discussion on Alternative Risk-informed, Technology-inclusive Approaches to Advanced Reactor Regulation PMNS20241280, Proposed Rule Generic Environmental Impact Statement for Licensing of New Nuclear Reactors2024-11-0505 November 2024 Proposed Rule Generic Environmental Impact Statement for Licensing of New Nuclear Reactors PMNS20241344, Information Meeting on the U.S. Nuclear Regulatory Commission (NRC) Staff Draft White Paper on Nth-of-a-Kind Micro-Reactor Licensing and Deployment Considerations2024-11-0505 November 2024 Information Meeting on the U.S. Nuclear Regulatory Commission (NRC) Staff Draft White Paper on Nth-of-a-Kind Micro-Reactor Licensing and Deployment Considerations PMNS20241279, Proposed Rule Generic Environmental Impact Statement for Licensing of New Nuclear Reactors2024-11-0505 November 2024 Proposed Rule Generic Environmental Impact Statement for Licensing of New Nuclear Reactors PMNS20241398, Pre-submittal Meeting on the Kairos Power LLC Operator Training and Testing Program Topical Report and Proposed Exemption2024-11-0404 November 2024 Pre-submittal Meeting on the Kairos Power LLC Operator Training and Testing Program Topical Report and Proposed Exemption PMNS20241402, Notice of Public Observation Meeting with the Nuclear Energy Institute Regulatory Issues Task Force2024-11-0404 November 2024 Notice of Public Observation Meeting with the Nuclear Energy Institute Regulatory Issues Task Force PMNS20241266, Advanced Reactor Stakeholder Meeting2024-11-0202 November 2024 Advanced Reactor Stakeholder Meeting ML24303A1712024-10-29029 October 2024 Forthcoming Quarterly Public Meeting Between the U. S. Nuclear Regulatory Commission and the Technical Specifications Task Force ML24303A2372024-10-29029 October 2024 Forthcoming Public Meeting Between the U. S. Nuclear Regulatory Commission and the Technical Specifications Task Force (TSTF) PMNS20241289, Pre-Application Meeting Regarding Potential License Amendment Request Related to Revising the Emergency Plan for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 22024-10-29029 October 2024 Pre-Application Meeting Regarding Potential License Amendment Request Related to Revising the Emergency Plan for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 PMNS20241304, Notice of Meeting with Constellation Energy Generation, LLC2024-10-24024 October 2024 Notice of Meeting with Constellation Energy Generation, LLC 2024-11-08
[Table view]Some use of "" in your query was not closed by a matching "". Category:Meeting Briefing Package/Handouts
MONTHYEARML24319A1602024-11-14014 November 2024 Meeting Handouts - Overview of the Rulemaking Process - PRM Emphasis ML24309A2742024-11-0404 November 2024 Slides for the November 6, 2024, Public Information Meeting on the Draft White Paper on Nth-of-a-Kind Microreactor Licensing and Deployment Considerations ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24267A2452024-09-23023 September 2024 Session 3- Stakeholder Engagement - Advance Act of 2024, Section 401 ML24261B9742024-09-17017 September 2024 Master Slide Deck - Advanced Reactor Stakeholder Meeting - 2024-09-18 ML24248A2152024-09-0404 September 2024 Adapting Successful Hazard Analysis Approaches to New Hazards at the Nuclear Regulatory Commission ML24241A2342024-08-28028 August 2024 Bdh LIP Aug 29 2024 (002) - Final ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0202024-07-23023 July 2024 5 - RG 1.59 - Appendix K - Consideration for Applying Guidance to Advanced Reactor and Small Modular Reactors - Stakeholders Meeting 07/24/2024 ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24205A0192024-07-23023 July 2024 6-Licensing and Deployment Considerations for Noak Micro-Reactors - AR Stakeholders Meeting July 24 2024 ML24192A1272024-07-10010 July 2024 Scale and Melcor non-LWR Fuel Cycle Demonstration Project - MSR ML24193A0772024-07-0909 July 2024 Nice ASME NQA-1 International Working Group (Iwg) - Emea (Europe, Middle East, & Africa) Iwg Trip Report Part 21 Presentation ML24190A1462024-07-0808 July 2024 Arcop Ws 4 Ppt - Public ML24172A3062024-06-27027 June 2024 Risk-Informing Materials Issues Risk Insights for Materials Issues NRC Perspective ML24172A3052024-06-27027 June 2024 NRC- Perspective on ASME Code Efforts ML24173A1532024-06-27027 June 2024 20 - EPRI-NRC Cooperative Research Project: PWSCC Crack Initiation Characterization of Alloys 600/182 and Alloys 690/52/152-2024 Overview and Status ML24163A0412024-06-11011 June 2024 Arcop Ws 3 Exercise NRC Facilitator Handout ML24163A0422024-06-11011 June 2024 Arcop Ws 3 Exercise Participant Handout ML24017A2992024-05-29029 May 2024 Public Meeting with the Nuclear Energy Institue (NEI) Regulatory Issue Task Force Presentation Slides, May 29, 2024 ML24144A1832024-05-23023 May 2024 Advanced Reactor Stakeholder Meeting 2024-05-23 ML24143A0802024-05-22022 May 2024 Arcap ISG Documents and Ticap Guidance Final Documents ML24123A2172024-05-15015 May 2024 Research Test Rx Construction Workshop Date 5.15.25 - Public ML24131A0142024-05-14014 May 2024 NRC Slides Micro-Reactor Licensing 5_14_24 Public Meeting ML24129A0752024-05-0808 May 2024 Arcop Work Shop 3 May 7 Version ML24122C6322024-05-0101 May 2024 ROP Bi-Monthly Meeting Slides on IP93100 Revision Update ML24030A6732024-03-13013 March 2024 RIC 2024 Krepel Presentation Adapting to a Changing Landscape ML24067A2572024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Rtaylor Chair Opening Remarks ML24067A2582024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Ncoovert and Jgreives Future of Construction Oversight ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24030A0092024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2/14/2024 ML24043A1812024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2-14-24 Rev1 ML24044A1402024-02-0808 February 2024 TSTF Handout for 02/08/2024 Quarterly Meeting ML24038A3492024-02-0707 February 2024 NRC Comments for Pre-submittal Meeting TSTF-600, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency ML23338A2792023-11-30030 November 2023 Technology-Inclusive, Risk-Informed, and Performance-Based Licensing Approaches ML23306A1262023-11-0707 November 2023 Terrapower Public Outreach Meeting Wyoming Final (1) ML23298A1342023-10-27027 October 2023 DG-4034 (RG 4-7 Rev 4) Presentation on Population-Related Siting Oct 27 2023 ML23270B9282023-09-28028 September 2023 50.72 Aug 9 2023 Public Meeting Slides ML23256A0012023-09-20020 September 2023 Generic Issues Program Presentation - ROP Public Meeting ML23250A1292023-09-11011 September 2023 NRC Staff Presentation on the NRC Draft White Paper on Licensing and Deployment Considerations for Factory-Fabricated Micro-Reactors ML23243B0092023-08-30030 August 2023 Public Meeting Presentation - University of California Davis - Mcclellan Nuclear Research Center Reactor Meeting August 30, 2023 ML23219A1382023-08-0707 August 2023 50.72 Rulemaking Update ML23200A3392023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Travis Tate on Non-power Production and Utilization Facilities Oversight ML23122A1372023-05-0202 May 2023 NDE of AMT NRC Presentation ML23101A1232023-04-18018 April 2023 Staff Presentation on PRA Used to Implement Lmp in Support of Non-LWR Construction Permit Applications Under 10 CFR Part 50 ML23192A0392023-04-13013 April 2023 Abilene Christian University, NRC Slides from April 13, 2023, Closed Meeting to Discuss Security Topics ML23094A0562023-04-0404 April 2023 Presentation - April 4, 2023 Licensing Review Framework for Advanced Reactors I&C Workshop 2 ML23079A0482023-03-16016 March 2023 RIC 2023 Slides - Intro TH19 ML23045A2922023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2862023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric). Advances in RIDM: Past, Present, Future Technical Session T5 2024-09-04
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24319A1602024-11-14014 November 2024 Meeting Handouts - Overview of the Rulemaking Process - PRM Emphasis ML24309A2742024-11-0404 November 2024 Slides for the November 6, 2024, Public Information Meeting on the Draft White Paper on Nth-of-a-Kind Microreactor Licensing and Deployment Considerations ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24267A2452024-09-23023 September 2024 Session 3- Stakeholder Engagement - Advance Act of 2024, Section 401 ML24261B9742024-09-17017 September 2024 Master Slide Deck - Advanced Reactor Stakeholder Meeting - 2024-09-18 ML24248A2152024-09-0404 September 2024 Adapting Successful Hazard Analysis Approaches to New Hazards at the Nuclear Regulatory Commission ML24241A2342024-08-28028 August 2024 Bdh LIP Aug 29 2024 (002) - Final ML24218A1922024-07-30030 July 2024 NRC Presentation for 7-30-24 Public Meeting RG 1.247 Finalization Plan ML24205A0202024-07-23023 July 2024 5 - RG 1.59 - Appendix K - Consideration for Applying Guidance to Advanced Reactor and Small Modular Reactors - Stakeholders Meeting 07/24/2024 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24205A0192024-07-23023 July 2024 6-Licensing and Deployment Considerations for Noak Micro-Reactors - AR Stakeholders Meeting July 24 2024 ML24192A1272024-07-10010 July 2024 Scale and Melcor non-LWR Fuel Cycle Demonstration Project - MSR ML24193A0772024-07-0909 July 2024 Nice ASME NQA-1 International Working Group (Iwg) - Emea (Europe, Middle East, & Africa) Iwg Trip Report Part 21 Presentation ML24190A1462024-07-0808 July 2024 Arcop Ws 4 Ppt - Public ML24173A1532024-06-27027 June 2024 20 - EPRI-NRC Cooperative Research Project: PWSCC Crack Initiation Characterization of Alloys 600/182 and Alloys 690/52/152-2024 Overview and Status ML24172A3052024-06-27027 June 2024 NRC- Perspective on ASME Code Efforts ML24172A3062024-06-27027 June 2024 Risk-Informing Materials Issues Risk Insights for Materials Issues NRC Perspective ML24163A0422024-06-11011 June 2024 Arcop Ws 3 Exercise Participant Handout ML24163A0412024-06-11011 June 2024 Arcop Ws 3 Exercise NRC Facilitator Handout ML24017A2992024-05-29029 May 2024 Public Meeting with the Nuclear Energy Institue (NEI) Regulatory Issue Task Force Presentation Slides, May 29, 2024 ML24144A1832024-05-23023 May 2024 Advanced Reactor Stakeholder Meeting 2024-05-23 ML24143A0802024-05-22022 May 2024 Arcap ISG Documents and Ticap Guidance Final Documents ML24142A5492024-05-21021 May 2024 Adv Rx Stakeholders - Risk Metrics Workshop - Rev 2 ML24142A5512024-05-21021 May 2024 Path Forward - Arsm Slides for 5-23-24 ML24141A1552024-05-20020 May 2024 NRC Slides Micro-Reactor Licensing May 23 2024 Advanced Reactor Stakeholder Meeting ML24123A2172024-05-15015 May 2024 Research Test Rx Construction Workshop Date 5.15.25 - Public ML24131A0142024-05-14014 May 2024 NRC Slides Micro-Reactor Licensing 5_14_24 Public Meeting ML24129A0752024-05-0808 May 2024 Arcop Work Shop 3 May 7 Version ML24122C6322024-05-0101 May 2024 ROP Bi-Monthly Meeting Slides on IP93100 Revision Update ML24052A2232024-03-14014 March 2024 Regulatory Information Conference (RIC) 2024 - Digital Exhibit - the NRC Is Advanced Reactor Ready! ML24030A6732024-03-13013 March 2024 RIC 2024 Krepel Presentation Adapting to a Changing Landscape ML24067A2572024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Rtaylor Chair Opening Remarks ML24067A2582024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Ncoovert and Jgreives Future of Construction Oversight ML24040A1832024-03-12012 March 2024 RIC 2024 T4 Slides - Vhuckabay Spent Fuel Reprocessing: Past, Present, and Future ML24149A1492024-03-12012 March 2024 Enclosure 1 - 36th Annual RIC Presentation - Opening Remarks & Fulfilling the Mission Today and Tomorrow - Miranda Ross ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24043A1812024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2-14-24 Rev1 ML24030A0092024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2/14/2024 ML23338A2792023-11-30030 November 2023 Technology-Inclusive, Risk-Informed, and Performance-Based Licensing Approaches ML23306A1262023-11-0707 November 2023 Terrapower Public Outreach Meeting Wyoming Final (1) ML23298A1342023-10-27027 October 2023 DG-4034 (RG 4-7 Rev 4) Presentation on Population-Related Siting Oct 27 2023 ML23270B9282023-09-28028 September 2023 50.72 Aug 9 2023 Public Meeting Slides ML23256A0012023-09-20020 September 2023 Generic Issues Program Presentation - ROP Public Meeting ML23250A1292023-09-11011 September 2023 NRC Staff Presentation on the NRC Draft White Paper on Licensing and Deployment Considerations for Factory-Fabricated Micro-Reactors ML23219A1382023-08-0707 August 2023 50.72 Rulemaking Update ML23200A3392023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Travis Tate on Non-power Production and Utilization Facilities Oversight ML23200A3372023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Josh Borromeo on Non-power Production and Utilization Facilities and Advanced Reactors Licensing ML23200A3432023-06-19019 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Beth Reed on Physical Security Event Notification and Suspicious Activity Reporting Rule ML23200A3422023-06-19019 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Beth Reed on Secy Option Paper for Enhanced Security of Special Nuclear Material 2024-09-04
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
1 Advanced ReactorStakeholderPublic Meeting August 18, 2022 Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 951 216 02#
2 Part 53 Rulemaking Process (Steve Lynch)
Time Agenda Speaker 10:00 - 10:15 am Opening Remarks/ Adv. Rx Integrated Schedule (Shelley Pitter - Logistics, Steve Lynch)
NRC 10:15 - 10:30 am Population-Related Siting Considerations for Advanced Reactors (next steps, including NRC path forward, role(s) for stakeholders)
(Steve Lynch)
NRC 10:30 - 11:00 am Part 53 Update: Status and Path Forward (Steve Lynch)
NRC 11:00 am - 12:00 pm Part 53 - Stakeholder Perspectives (TBD)
Stakeholders 12:00 - 1:00 pm Lunch Break All 1:00 - 1:45 pm IAEA Safeguards, the Additional Protocol, and its reporting requirements (Eduardo Sastre Fuente)
NRC 1:45 - 2:30 pm Technology Inclusive Risk Informed Change Evaluation (TIRICE) Guidance (Michael Tschiltz)
Southern Company 2:30 - 2:35 pm Future Meeting Planning and Concluding Remarks All
3 https://www.nrc.gov/reactors/new-reactors/advanced/integrated-review-schedule.html
4 Population-Related Siting Considerations for Advanced Reactors (next steps, including NRC path forward, role(s) for stakeholders)
(Steven Lynch)
Population-Related Siting Considerations Steven Lynch, Chief Advanced Reactor Policy Branch
Commission Direction
- In Staff Requirements Memorandum (SRM)-SECY-20-0045, the Commission approved the staffs recommendation to revise the guidance in Regulatory Guide (RG) 4.7, General Site Suitability Criteria for Nuclear Power Stations related to implementation of Title 10 of the Code of Federal Regulations Part 100, Section 100.21(h).
o The SRM also states: With respect to the traditional dose assessment approach, the staff should provide appropriate guidance on assessing defense-in-depth adequacy and establishing hypothetical major accidents to evaluate.
6
Proposed Path Forward
- The NRC staff are working on both a focused update to RG 4.7 and Volume 2 of the Advanced Reactor Content of Application Project
- Development of guidance will consider design approaches using the Licensing Modernization Project approach, as well as others following more traditional analysis approaches
- These guidance documents would include details for assessing population density out to a distance equal to twice the distance at which a hypothetical individual could receive a calculated dose of 1 rem over a period of 1 month from the release of radionuclides following postulated accidents.
- The NRC staff currently estimate that guidance updates will be complete by 2024 7
8 Part 53 Update: Status and Path Forward (Steven Lynch)
Part 53 Rulemaking Status and Consideration of Feedback Steven Lynch, Chief Advanced Reactor Policy Branch
RULEMAKING STATUS Stakeholder Engagement o 21 public meetings, 2 Commission Meetings, and 18 ACRS meetings o Recent: 5/25 public meeting on Framework A, 6/11 public meeting on Framework B, 6/30 stakeholder meeting on stakeholder feedback and Subpart F, 7/28 public meeting on Framework B and key technical topics o Future: October ACRS Subcommittee Meeting on integrated rulemaking, November ACRS Full Committee Meeting Focus Areas o Finalize rule language o Develop rule package (SOCs, regulatory analysis, etc.)
o Develop guidance Industry Input o Over 1500 public comments received Rule Language o 2021: definitions (A), safety criteria (B), design and analyses (C), siting (D), construction/manufacturing (E),
operations and programs (F), decommissioning (G),
licensing processes (H), maintenance of the licensing basis (I), reporting (J), security, access authorization, FFD, traditional alternatives.
o 2022: consolidated rule package (Feb.), 2nd iteration Framework A (May, June), 1st iteration Framework B (June), updated consolidated rule package with statements of consideration (September)
11 Feb 2023 Draft Proposed Rule to Commission Jun 2023 Publish Proposed Rule and Draft Key Guidance Oct 2023 Public Comment Period - 60 days Dec 2024 Draft Final Rule to Commission Apr 2025-Jun 2025 Office of Management and Budget and Office of the Federal Register Processing Jul 2025 Publish Final Rule and Key Guidance Nov 2023-Nov 2024 Public Outreach and Generation of Final Rule Package CURRENT PART 53 TIMELINE Oct 2020-Aug 2022 Public Outreach, ACRS Interactions and Generation of Proposed Rule Package
Continued Consideration of Stakeholder Feedback on Part 53 Framework B Safety functions from Framework A should be employed in Framework B.
Framework B should have its own set of siting requirements and should not rely on Part 100 Framework B should incorporate a RIPB alternative for seismic design requirements.
The draft requirements for fire protection in Framework B need to be more performance-based.
Referencing 10 CFR 50.155 (mitigation of beyond design-basis events (BDBE)) could be a challenge in Framework B because these requirements are not technology-inclusive.
Use of Generally Licensed Reactor Operators (GLROs) should be permitted in Framework B.
Linked probabilistic risk assessment requirements in 10 CFR 50.44 (combustible gas control) could be a challenge for an Alternative Evaluation of Risk Insights (AERI).
The proposed requirements in 10 CFR 53.4730(a)(12) [from the Three Mile Island requirements in 10 CFR 50.34(f)] are not technology-inclusive.
13 IAEA Safeguards, the Additional Protocol, and its reporting requirements (Eduardo Sastre Fuente)
Implementation of IAEA Safeguards within the United States Material Control and Accounting Branch U.S. Nuclear Regulatory Commission (NRC) 14
History
- The Treaty on the Non-Proliferation of Nuclear Weapons (NPT) requires non-nuclear weapon states to accept IAEA safeguards on all source and special nuclear material in all peaceful nuclear activities
- The United States, as one of five nuclear-weapon states, or P5, was not obligated to conclude a safeguards agreement with the IAEA
- Since the early 1960s the U.S. has permitted the application of IAEA safeguards on a variety of nuclear facilities 15 NPT Signing, 1968 NPT RevCon, 2010
Overview of U.S.-IAEA Agreements U.S. - IAEA Safeguards Agreement (INFCIRC/288)
- The U.S. Voluntary Offer Agreement
- Entry Into Force 1980 Protocol to the U.S. - IAEA Safeguards Agreement (INFCIRC/288)
- The Reporting Protocol
- Entry Into Force 1980 Protocol Additional to the U.S. - IAEA Safeguards Agreement (INFCIRC/288 Add.1)
- The Additional Protocol
- Entry Into Force 2009 U.S.-IAEA Caribbean Territories Safeguards Agreement (INFCIRC/366)
- Includes a Small Quantities Protocol
- Entry Into Force 1989
- Modified Small Quantities Protocol - Entry Into Force 2018 16
17
- Atomic Energy Act of 1954, as amended
-Primary U. S. law on nuclear energy to... promote world peace, improve the general welfare, increase the standard of living and strengthen free competition in private enterprise.
- Energy Reorganization Act of 1974
-Established the United States Nuclear Regulatory Commission and Energy Research and Development Administration (eventually the Department of Energy)
- Nuclear Nonproliferation Action of 1978
-Establish a more effective framework for international cooperation on peaceful nuclear activities
-Codifies support to the IAEA
- Title 10 of the Code of Federal Regulations Part 75
-Requires NRC licensees to comply with U.S. obligations to the IAEA Applicable U.S. Laws and Regulations
U.S. Government Oversight 18 Subgroup on IAEA Safeguards in the U.S.
(SISUS)
Subcommittee on International Safeguards and Monitoring (SISM)
Subcommittee on International Safeguards and Monitoring (SISM)
IAEA Steering Committee (ISC)
IAEA Steering Committee (ISC)
Sub-IPC
- Chaired by the National Security Council (NSC)
Sub-IPC
- Chaired by the National Security Council (NSC)
Nonproliferation Interagency Policy Committee (IPC)
- Chaired by the NSC Nonproliferation Interagency Policy Committee (IPC)
- Chaired by the NSC Defined in Federal Register Implementation Implementation Policy Policy
Who Implements in the U.S.?
Who are the Players?
19 U.S. Nuclear Regulatory Commission
- chair Department of Commerce Department of State Department of Defense Department of Energy SISUS Committee
U.S. Voluntary Offer Agreement
- Based on INFCIRC/153
- Selection-based approach to safeguards
- Eligible Facilities List (EFL)
- National Security Exclusion
- Includes all typical safeguards activities including inspections, completion of Design Information Questionnaire (DIQ) and Design Information Verification (DIV), sampling, technical visits, etc
- Allows for the application of safeguards in a manner similar to that of non-nuclear weapon states (NNWS) 20
U.S. Voluntary Offer Agreement (VOA) -
Reporting Protocol
- Allows for limited safeguards activities to be performed at facilities with minimal cost to the IAEA
- Unique to the United States
- Includes activities such as completion of DIQs and DIVs
- Monthly and annual material accountancy reports (e.g.,
Physical Inventory Listing (PIL), Inventory Change Report (ICR), etc)
- 4 sites (all NRC licensees) currently selected under this Protocol
- NO INSPECTIONS 21
U.S. VOA or Comprehensive Safeguards Agreement (CSA) 22 U.S. VOA Comprehensive Safeguards Selection-based approach based on the Eligible Facilities List Safeguards are applied on all nuclear material in the territory (all facilities)
Completion of Design Information Questionnaire and Design Information Verification Completion of Design Information Questionnaire and Design Information Verification Monthly and annual material accountancy reports (e.g., Physical Inventory Listing (PIL), Inventory Change Report (ICR), etc.)
Monthly and annual material accountancy reports (e.g., Physical Inventory Listing (PIL), Inventory Change Report (ICR), etc.)
Inspections at selected facilities under full scope safeguards (one in the U.S.)
Inspections at all facilities National Security Exclusion No Exclusions
Eligible Facilities List (EFL)
- Two portions of the U.S. EFL
- DOE facilities (non-public)
- NRC facilities (public)
- Facility is formally defined by the IAEA
- Facilities removed when decommissioned (per IAEAs definition)
- Locations Outside Facilities (LOFs) not included on EFL
- Updates are vetted through the U.S.
Government
- Security evaluation to remove anything of direct national security significance 23 SISUS Committee Selection Since 1981, the IAEA has selected 21 facilities from the EFL
Implementation Contd.
- After the facility has been notified of selection, the following documents are completed:
- Design Information Questionnaire (DIQ)
- Facility Attachment
- U.S. and IAEA negotiate terms of implementation 24 Selection
Present
- K-Area Material Storage (KAMS) at Savannah River Site (SRS)
- Only facility currently under routine inspections by the IAEA
- Incorporates remote monitoring
- Allow for installation of IAEA equipment
- Westinghouse Fuel Fab. Facility (Columbia, SC)
- Framatome Fuel Fab. Facility (Richland, WA)
- Global Nuclear Fuel - Americas Fuel Fab. Facility (Wilmington, NC)
- URENCO USA Gas Centrifuge Enrichment Plant (Eunice, NM) 25 Reporting ONLY, NO INSPECTIONS Reporting AND Inspections
Flow of Information through NMMSS (Nuclear Materials Management & Safeguards System) 26 U.S.
Department of State U.S. Nuclear Regulatory Commission U.S.
Department of Energy U.S.
Department of Commerce Facilities NMMSS Industry
U.S. Additional Protocol (AP) 2009 - Present
- Signed in 1998, entry into force 2009
- Provides the IAEA with additional information and access rights on nuclear fuel cycle related activities
- Contains a national security exclusion
- Locations and Sites must submit:
- The U.S. AP applies to everyone within the U.S.
- Excluding anything of national security significance
- No selection is required 27 www.AP.gov
Reporting Requirements
- (2.a.i) Nuclear fuel cycle research and development (15 CFR 781)
- Approximately 75% of the total number of U.S. declarations are 2.a.i. declarations
- (2.a.iii) Site declaration including description of activities
- Only relevant for facilities that are currently or have previously been selected for IAEA safeguards
- Not applicable to a vast majority of the industry
- (2.a.iv) Nuclear fuel cycle related manufacturing and assembly (15 CFR 781)
- Annex I items from the U.S. Additional Protocol
- (2.a.v) Uranium and thorium mines, mills, and concentration plants
- (2.a.vi) Possession of large quantities of impure source material (15 CFR 781)
- Source material that is not yet suitable for fuel fabrication or enrichment
- (2.a.x) Ten year plan
- Input is not requested from the industry
- Quarterly reporting requirements [10 CFR 110.54(a)(1)]
- (2.a.ix) Exports of Annex II items
Nuclear Fuel Cycle Research and Development
- The R&D activities captured by AP are those are funded either by the U.S. Government or privately. (15 CFR 783.1(a)(1))
Reportable privately funded R&D activities:
- Enrichment,
- Reprocessing of nuclear fuel or
- Processing of intermediate or high-level waste containing plutonium, high enriched uranium or uranium-233
- Reportable U.S. Government funded R&D specifically related to:
- Conversion of nuclear material
- Enrichment of nuclear material
- Nuclear fuel fabrication
- Reactors
- Critical facilities
- Reprocessing of nuclear fuel
- Processing of intermediate or high level waste containing plutonium and/or high enriched uranium.
Snapshot of Licensees Who Report Under the U.S. APand many more!
30 Additional Protocol
Quarterly Export Reports Explained (2.a.ix)
- For licensees using NRC general or specific license authorizations for exports of specified equipment and non-nuclear material as listed in Annex II of the Additional Protocol
Most NRC licensees should report as a location using AP-13 found on www.AP.gov, to report directly to Department of Commerce, Bureau of Industry and Security (BIS) every quarter (forms are joint DOC/NRC forms).
Quarterly deadlines to BIS are: January 15, April 15, July 15, and October 15 of each year Exporters shall follow 10 CFR 110.54(c) for reporting items exported under Part 110.26 (General License)
Additional Protocol Reporting Process
- Information is sent to DOC by Jan 31st
- Can be sent via facsimile, mail, or email
- NRC receives licensees forms from DOC and performs a review
- NRC compiles data and submits a report to DOC for inclusion in the overall U.S.
Government declaration
- U.S. declaration must sit before Congress for a 60 day review period (for annual report only) 32
Additional Protocol Webpage
- The Department of Commerce manages a webpage that contains the handbooks and forms for the U.S. Additional Protocol
- Handbooks and forms are joint use for both DOC and NRC
- The majority of companies use the Report Handbook for Locations.
- Assistance in determining your obligations (15 CFR 782.4)
- apdr@bis.doc.gov
- Santiago.Aguilar@nrc.gov http://www.AP.gov 33
Additional Protocol Webpage 34
Additional Protocol Webpage 35
Complementary Access (CA)
- Complementary access is an essential aspect of the IAEAs expanded authorities
- Complementary access allows the IAEA to:
- Verify the absence of undeclared nuclear materials and activities
- Resolve a question or inconsistency
- Access for IAEA with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> advance notice
- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if IAEA is already onsite
- Only 2 CAs have been conducted in the U.S. (2010)
- AREVA Inc., Fuel Fabrication Facility (Lynchburg, VA)
- Global Advanced Metals (Boyertown, PA) 36
NRC Points of Contact 37
- Please ask questions early and often!
- NRC - Office of Nuclear Material Safety and Safeguards (NMSS); Material Control and Accounting Branch (MCAB)
- Eduardo Sastre Eduardo.Sastre@nrc.gov
- Oleg Bukharin Oleg.Bukharin@nrc.gov
- Department of Commerce, Treaty Compliance Division, Bureau of Industry and Security, U.S. Department of Commerce
- Hung Ly Hung.Ly@bis.doc.gov
- http://www.nrc.gov/about-nrc/ip/intl-safeguards.html
38 Questions?
39 Technology Inclusive Risk Informed Change Evaluation (TIRICE) Guidance (Michael Tschiltz)
40 August 18, 2022 Mike Tschiltz Consultant to Southern Company Technology-Inclusive Risk-Informed Change Evaluation (TIRICE) for Facilities Utilizing NEI 18-04 (Methodology) and NEI 21-07 (Content of Application) guidance NRC Advanced Reactor Stakeholder Meeting
41
-Project Overview
-Objectives
-Schedule
-Questions Topics
42 Project Overview, Objectives and Schedule The TIRICE project builds upon the work accomplished by LMP(NEI 18-04) and TICAP (NEI 21-07) to create guidance for evaluating changes to the facility as described in the UFSAR for those licensees that have used these guidance documents.
Advanced non-LWRs may elect to follow NEI 18-04 for selection of licensing basis events; safety classification of structures, systems, and components and associated special treatments; and determination of Defense-in-Depth (DID) adequacy.
The resulting LMP-based affirmative safety case is substantially different from the traditional deterministic, compliance-based safety cases in place for LWRs licensed by the NRC.
During development of TICAP guidance it became clear that there is a need to develop technology-inclusive, risk-informed, performance-based guidance for evaluating changes to a facility as described in the Updated Final Safety Analysis Report (UFSAR) (10 CFR 50.59).
The attributes of the LMP-based affirmative safety case require additional guidance for efficient application of an alternative change evaluation process.
The proposed change evaluation process would be invoked through a license condition in combination with an exemption to 10 CFR 50.59.
43 The project will develop guidance for a change evaluation process for reactors that are licensed under 10 CFR Part 50 or 52 that utilize NEI 18-04 to develop safety case and NEI 21-07 guidance to determine application content.
The objectives of the guidance are to:
Establish a process and criteria for evaluating changes to the facility as described in the final safety analysis report and determine which changes can be implemented without prior NRC approval Ensure that the changes that require NRC prior approval are properly identified Minimize the unnecessary burden to the regulator and operators Project Overview, Objectives and Schedule
44
- Develop Draft Guidance document to be provided for the NRC for review in August 22
- NRC review and endorsement FY23
- Develop Project Plan and establish Project Team (Dec 21-Jan 22) complete
- Develop Scope and Process papers (Feb-Mar 22) complete Utilized as inputs to white paper
- Develop White Paper (Apr-July 22) complete
- Identify specific steps to be performed during the change evaluation process
- Summarize efforts to date and obtain ARRTF feedback
- Provide draft white paper to NRC for review
- Meeting with NRC to obtain staff feedback
- Revise white paper in support of Table Top exercises
- Utilize white paper in performing Table Top exercises
- Develop Table Top Guidelines and Objectives (Apr June 22) complete Project Overview, Objectives and Schedule
45
- Develop Annotated Outline for Guidance (Apr - Jul) complete
- Conduct Tabletop Exercises (Jun - Jul) complete
- Conduct Table Tops with 2 Advanced Reactor Developers
- Obtain NRC observations from Table Tops
- Develop Lessons Learned and incorporate into Draft Guidance document
- Develop Southern Co. Draft Guidance document (Jul - Aug) ongoing
- ARRTF review of Draft Guidance
- Address ARRTF comments provide revised Draft Guidance to ARRTF
- NRC review of Draft Guidance
- Revise Draft Guidance to address NRC comments and provide to ARRTF and NRC
- Convert to NEI document and submit for NRC review/endorsement (Sep 22-FY23)
- ARRTF review of draft NEI guidance Project Overview, Objectives and Schedule
46 Questions Thank you for your time and attention