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Category:Meeting Agenda
MONTHYEARPMNS20240086, Periodic Advanced Reactor Stakeholder Meeting2024-02-0909 February 2024 Periodic Advanced Reactor Stakeholder Meeting PMNS20240067, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Delete Surveillance Requirement 3.8.1.8 from the Technical Specifications2024-02-0606 February 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Delete Surveillance Requirement 3.8.1.8 from the Technical Specifications PMNS20240061, Virtual Palisades Pre-submittal Meeting with Holtec Decommissioning International, LLC on Proposed License Amendment for Changes to Technical Specifications Administrative Controls and Discussion on Quality Assurance Plans2024-02-0505 February 2024 Virtual Palisades Pre-submittal Meeting with Holtec Decommissioning International, LLC on Proposed License Amendment for Changes to Technical Specifications Administrative Controls and Discussion on Quality Assurance Plans PMNS20240113, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Revise the Fuel Handling Accident Analysis and Outage Related Fuel Decay Time2024-02-0202 February 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Revise the Fuel Handling Accident Analysis and Outage Related Fuel Decay Time PMNS20240146, NRC Hybrid Workshop (2 of 3) - Update to RG 1.183, Revision 1, Alternative Radiologicalsource Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors2024-02-0202 February 2024 NRC Hybrid Workshop (2 of 3) - Update to RG 1.183, Revision 1, Alternative Radiologicalsource Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ML24032A4692024-02-0101 February 2024 Forthcoming Quarterly Public Teleconference Between the U. S. Nuclear Regulatory Commission and the Technical Specifications Task Force PMNS20240143, Notice of Meeting with Southern Nuclear Operating Company2024-02-0101 February 2024 Notice of Meeting with Southern Nuclear Operating Company PMNS20240142, Notice of Meeting with Southern Nuclear Operating Company2024-02-0101 February 2024 Notice of Meeting with Southern Nuclear Operating Company PMNS20240140, Notice of Meeting with Southern Nuclear Operating Company2024-02-0101 February 2024 Notice of Meeting with Southern Nuclear Operating Company PMNS20240141, Notice of Meeting with Southern Nuclear Operating Company2024-02-0101 February 2024 Notice of Meeting with Southern Nuclear Operating Company PMNS20240075, Forthcoming Public Meeting with the Nat'L Org of Test, Research & Training Reactors on Training for NRC Form 396, Certification of Medical Examination by Facility Licensee, and NRC Form 398, Personal Qualification Statement -- Licensee2024-01-31031 January 2024 Forthcoming Public Meeting with the Nat'L Org of Test, Research & Training Reactors on Training for NRC Form 396, Certification of Medical Examination by Facility Licensee, and NRC Form 398, Personal Qualification Statement -- Licensee PMNS20240010, Public Meeting to Discuss SRP Chapter 19 Scope for Light-Water Reactor Construction Permit Applications Staff White Paper Guidance2024-01-30030 January 2024 Public Meeting to Discuss SRP Chapter 19 Scope for Light-Water Reactor Construction Permit Applications Staff White Paper Guidance PMNS20240126, Periodic Public Meeting to Discuss Possible Efficiencies for the Subsequent Licenserenewal Review2024-01-30030 January 2024 Periodic Public Meeting to Discuss Possible Efficiencies for the Subsequent Licenserenewal Review PMNS20240088, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant Technical Specifications2024-01-30030 January 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant Technical Specifications PMNS20240133, Public Meeting on Holtec SMR Conformance with RG 1.189 Rev. 5, Fire Protection Guidance2024-01-30030 January 2024 Public Meeting on Holtec SMR Conformance with RG 1.189 Rev. 5, Fire Protection Guidance PMNS20240012, 10 CFR Part 52 Construction Lessons-Learned Report2024-01-30030 January 2024 10 CFR Part 52 Construction Lessons-Learned Report PMNS20240125, Kickoff Public Meeting with Duke Energy on Belews Creek Early Site Permit Pre-Application2024-01-29029 January 2024 Kickoff Public Meeting with Duke Energy on Belews Creek Early Site Permit Pre-Application PMNS20240007, Pre-Application Meeting with Constellation Energy Generation, LLC, (Constellation) Regarding Potential Requests to Use Code Case N-9322024-01-29029 January 2024 Pre-Application Meeting with Constellation Energy Generation, LLC, (Constellation) Regarding Potential Requests to Use Code Case N-932 PMNS20240087, Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed License Amendment Request by Making Use of Risk-Informed Process for Evaluations at Palo Verde Nuclear Generating Station, Units 1, 2, and 32024-01-25025 January 2024 Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed License Amendment Request by Making Use of Risk-Informed Process for Evaluations at Palo Verde Nuclear Generating Station, Units 1, 2, and 3 PMNS20231417, Quarterly NRC-NuScale Management Meeting on NuScale US460 Standard Design Approval Application2024-01-25025 January 2024 Quarterly NRC-NuScale Management Meeting on NuScale US460 Standard Design Approval Application PMNS20240078, Meeting with Tennessee Valley Authority to Discuss a Future License Amendment Request to Revise the Final Safety Analysis Report Regarding the Hydrologic Analysis for the Browns Ferry Nuclear Plant2024-01-24024 January 2024 Meeting with Tennessee Valley Authority to Discuss a Future License Amendment Request to Revise the Final Safety Analysis Report Regarding the Hydrologic Analysis for the Browns Ferry Nuclear Plant PMNS20231097, Periodic Advanced Reactor Stakeholder Meeting2024-01-24024 January 2024 Periodic Advanced Reactor Stakeholder Meeting PMNS20240076, NRC Meeting with Industry Steam Generator Task Force2024-01-22022 January 2024 NRC Meeting with Industry Steam Generator Task Force PMNS20240054, Phenomenon Identification and Ranking Table (Pirt) Panel Follow-Up Discussion on High Burnup Fuel Dispersal and Its Consequences2024-01-17017 January 2024 Phenomenon Identification and Ranking Table (Pirt) Panel Follow-Up Discussion on High Burnup Fuel Dispersal and Its Consequences PMNS20240028, Meeting with Tennessee Valley Authority to Discuss Proposed Use of the Risk-Informed Process for Evaluations (RIPE) for an Upcoming License Amendment Request for the Browns Ferry Nuclear Plant2024-01-12012 January 2024 Meeting with Tennessee Valley Authority to Discuss Proposed Use of the Risk-Informed Process for Evaluations (RIPE) for an Upcoming License Amendment Request for the Browns Ferry Nuclear Plant PMNS20231406, Presubmittal Meeting with Entergy Operations, Inc. for a Proposed Online Monitoring License Amendment Request2024-01-11011 January 2024 Presubmittal Meeting with Entergy Operations, Inc. for a Proposed Online Monitoring License Amendment Request PMNS20231384, 2024 Nondestructive Examination (NDE) Technical Information Exchange - Hybrid2024-01-11011 January 2024 2024 Nondestructive Examination (NDE) Technical Information Exchange - Hybrid PMNS20231408, Notice of Meeting with Dominion Energy South Carolina (Desc) to Discuss Virgil C. Summer Nuclear Station'S Seismic Risk Analysis2024-01-10010 January 2024 Notice of Meeting with Dominion Energy South Carolina (Desc) to Discuss Virgil C. Summer Nuclear Station'S Seismic Risk Analysis ML24009A2622024-01-0909 January 2024 Forthcoming PRE-SUBMITTAL Teleconference with the Technical Specifications Task Force (TSTF) Regarding Draft Traveler TSTF-600, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency PMNS20231397, Periodic Public Meeting to Discuss Possible Efficiencies for the Subsequent License Renewal Review2024-01-0909 January 2024 Periodic Public Meeting to Discuss Possible Efficiencies for the Subsequent License Renewal Review PMNS20240027, NRC Public Meeting (Virtual) with the Nuclear Energy Institute (NEI) on the Emergency Response Organization (ERO) Remote Augmentation White Paper, Revision 02024-01-0909 January 2024 NRC Public Meeting (Virtual) with the Nuclear Energy Institute (NEI) on the Emergency Response Organization (ERO) Remote Augmentation White Paper, Revision 0 ML24009A2632024-01-0909 January 2024 Forthcoming PRE-SUBMITTAL Teleconference with the Technical Specifications Task Force (TSTF) Regarding Draft Traveler TSTF-599, Eliminate Periodic Surveillance Test of Simultaneous Start of Redundant Diesel Generators PMNS20231393, Notice of Meeting with Constellation Energy Generation, LLC (Constellation) Regarding a Future Amendment Request to Delete Byron and Braidwood Station Technical Specification 5.6.5.b.22024-01-0808 January 2024 Notice of Meeting with Constellation Energy Generation, LLC (Constellation) Regarding a Future Amendment Request to Delete Byron and Braidwood Station Technical Specification 5.6.5.b.2 PMNS20231392, NRC Hybrid Workshop (1 of 3) - Update to RG 1.183, Revision 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors2024-01-0808 January 2024 NRC Hybrid Workshop (1 of 3) - Update to RG 1.183, Revision 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors PMNS20240022, Reactor Oversight Process Public Meeting2024-01-0505 January 2024 Reactor Oversight Process Public Meeting PMNS20240017, Meeting to Discuss Sections of the National Organization of Test, Research and Trainingreactors, Inc. (Trtr) Proposed Guidance on the 50.59 Process for Digital Applications(Nei 23-03) with the U. S. Nuclear Regulatory Commission (NRC) S2024-01-0404 January 2024 Meeting to Discuss Sections of the National Organization of Test, Research and Trainingreactors, Inc. (Trtr) Proposed Guidance on the 50.59 Process for Digital Applications(Nei 23-03) with the U. S. Nuclear Regulatory Commission (NRC) Staff PMNS20231429, Meeting in Support of License Amendment Review Regarding Neutron Flux Channels2023-12-27027 December 2023 Meeting in Support of License Amendment Review Regarding Neutron Flux Channels PMNS20231422, Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application2023-12-22022 December 2023 Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application PMNS20231418, Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application2023-12-22022 December 2023 Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application PMNS20231419, Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application2023-12-22022 December 2023 Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application PMNS20231415, Notice of Meeting for the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application2023-12-22022 December 2023 Notice of Meeting for the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application PMNS20231420, Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application2023-12-22022 December 2023 Meeting with NuScale Power, LLC on NuScale Standard Design Approval Application PMNS20231395, Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2023-12-21021 December 2023 Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20231401, Meeting Between NRC Staff and Representatives of Nuclear Energy Institute to Discuss Draft Revision E to NEI 20-07, Guidance for Addressing Common Cause Failure in High Safety-Significant Safety-Related Digital I&C Systems2023-12-19019 December 2023 Meeting Between NRC Staff and Representatives of Nuclear Energy Institute to Discuss Draft Revision E to NEI 20-07, Guidance for Addressing Common Cause Failure in High Safety-Significant Safety-Related Digital I&C Systems PMNS20231396, Pre-Submittal Meeting with Southern Nuclear Operating Company (SNC) Regarding a Proposed Relief Request for Explosively Actuated Valves at Vogtle Electric Generating Plant (Vogtle), Units 3 and 42023-12-15015 December 2023 Pre-Submittal Meeting with Southern Nuclear Operating Company (SNC) Regarding a Proposed Relief Request for Explosively Actuated Valves at Vogtle Electric Generating Plant (Vogtle), Units 3 and 4 PMNS20231361, NRC Public Hybrid Meeting with NEI to Address Industry Comments on the Draft Safety Evaluation on NEI 16-03, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools2023-12-14014 December 2023 NRC Public Hybrid Meeting with NEI to Address Industry Comments on the Draft Safety Evaluation on NEI 16-03, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools PMNS20231383, Pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) Regarding the Proposed Transition of the Vogtle Electric Generating Plant, Units 3 and 4 Ndqam Into the SNC Fleet QATR2023-12-11011 December 2023 Pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) Regarding the Proposed Transition of the Vogtle Electric Generating Plant, Units 3 and 4 Ndqam Into the SNC Fleet QATR PMNS20231341, Discussion of Draft NEI 23-01, Operator Cold License Training Plan for Advanced Nuclear Reactors2023-12-11011 December 2023 Discussion of Draft NEI 23-01, Operator Cold License Training Plan for Advanced Nuclear Reactors PMNS20231377, Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed License Amendment by Making Use of Risk-Informed Process for Evaluations at Palo Verde Nuclear Generating Station, Units 1, 2, and 32023-12-0707 December 2023 Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed License Amendment by Making Use of Risk-Informed Process for Evaluations at Palo Verde Nuclear Generating Station, Units 1, 2, and 3 PMNS20230812, Periodic Advanced Reactor Stakeholder Meeting2023-12-0606 December 2023 Periodic Advanced Reactor Stakeholder Meeting 2024-02-09
[Table view]Some use of "" in your query was not closed by a matching "". Category:Meeting Briefing Package/Handouts
MONTHYEARML24030A0092024-02-14014 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 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 ML23045A2902023-03-14014 March 2023 RIC 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2912023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2922023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23017A1872023-03-14014 March 2023 RIC 2023: T2 New Fuels Licensing Readiness NRC RIC Presentations Donoghue 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 ML23045A2932023-03-14014 March 2023 RIC 2023 -3/14/2023 to 3/16/2023 Regulatory Information Conference (RIC) ML23017A1112023-01-11011 January 2023 ACRS Presentation CNSC - U.S. NRC Cooperation on Advanced Reactor Technologies and Small Modular Reactors ML22342B1632022-12-13013 December 2022 NRC Staff Presentation on the Regulatory Basis for Changes to Reporting Requirements for Nonemergency Events at Nuclear Power Plants ML22340A4732022-12-0505 December 2022 NRC Presentation, Expansion of Policy for Addressing Potential Common Cause Failures in U.S. Nuclear Power Plant Digital Instrumentation and Control Systems, IAEA Technical Meeting, December 6-8 2022 ML22333A7402022-12-0505 December 2022 NRC Presentation - ASME OM Code and Snubber Issues at Inservice Service Testing Owner Group (Istog) Final - Meeting December 5-6, 2022, in Clearwater, Fl ML22311A5532022-11-16016 November 2022 Kairos Hermes NRC Staff Presentation at Nov 16 Public Meeting on the Draft Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor ML22298A2162022-10-25025 October 2022 TSTF Meeting Handout TSTF-585 and the Maintenance Rule ML22255A2042022-10-12012 October 2022 NRC Irsrr Update (Trtr 2022): Redacted ML22284A1412022-10-11011 October 2022 Advanced Reactor Stakeholder Slides for 10-12-2022 Public Meeting ML22262A2522022-09-20020 September 2022 Presentation - 09/20/2022 Scale Melcor Sodium Fast Reactor (Sfr) Workshop ML22250A4272022-09-0808 September 2022 EPZ TR ACRS Subcommittee Slides - Open Session ML22245A0822022-09-0808 September 2022 September 8 2022 NRC Public Meeting with Steam Generator Task Force - NRC Presentation Final ML22243A0152022-08-31031 August 2022 GALL-SLR Public Meeting Slides - 1 of 2 ML22243A0162022-08-31031 August 2022 GALL-SLR Public Meeting Slides - 2 of 2 ML22234A2892022-08-22022 August 2022 Advanced Reactor Regulatory Priorities 6-30-22 Stakeholder Meeting ML22229A5622022-08-18018 August 2022 Advanced Reactors Stakeholder'S Meeting 08/18/2022 ML22230B8512022-08-18018 August 2022 Advanced Reactor Stakeholder Public Meeting 8/18/22 ML22214A0962022-08-0404 August 2022 NRC Staff Risk-informed Subsequent License Renewal - 2022-08-04 ML22201A0052022-07-19019 July 2022 License Renewal Application - Safety Pre-Application Meeting July 21, 2022 (NRC Slides) ML22180A0952022-06-30030 June 2022 Adv_Rx_Stakeholders_Meeting_Presentation_6-30-22 ML22180A2962022-06-30030 June 2022 Adv_Rx_Stakeholders_Meeting_Presentation_6-30-22 ML22048C2422022-03-31031 March 2022 Regulatory Information Conference (RIC) 2022 - Technical Session W16 Be Risksmart Presentation ML22074A1902022-03-15015 March 2022 March 16, 2022 Title Slides Advanced Reactor Stakeholder Public Meeting ML22053A3042022-03-0101 March 2022 NRC Presentation for INL OL SME Workshop - Jesse Seymour ML22056A2942022-02-24024 February 2022 2/24/2022 Meeting Handout - TSTF 2021 in Review ML22056A2932022-02-24024 February 2022 2/24/2022 Meeting Handout - Active Traveler Summary Report ML22053A3052022-02-22022 February 2022 Licensing of Personnel for Research Reactors John Nguyen Rtr 02152022 ML22038A9602022-02-0707 February 2022 Nuclear Regulatory Commission February 2022 EPRI Joint Utility Task Group Presentation ML21326A1452022-02-0202 February 2022 PRA Configuration Control Workshop ML22021B3082022-01-21021 January 2022 NRC Plant Modernization Oversight Activities - ROP Public Meeting 2024-02-14
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24030A0092024-02-14014 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 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 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 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 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 ML23184A1282023-06-0707 June 2023 Advanced Reactors 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 ML23017A1872023-03-14014 March 2023 RIC 2023: T2 New Fuels Licensing Readiness NRC RIC Presentations Donoghue ML23045A2932023-03-14014 March 2023 RIC 2023 -3/14/2023 to 3/16/2023 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 ML23045A2912023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2902023-03-14014 March 2023 RIC 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2922023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23053A2912023-02-22022 February 2023 Presentation - February 23, 2023 Licensing Review Framework for Advanced Reactors I&C Workshop 1 ML23017A1112023-01-11011 January 2023 ACRS Presentation CNSC - U.S. NRC Cooperation on Advanced Reactor Technologies and Small Modular Reactors ML22349A6482022-12-14014 December 2022 PWROG Risk Management Committee Meeting Dec 2022 ML22342B1632022-12-13013 December 2022 NRC Staff Presentation on the Regulatory Basis for Changes to Reporting Requirements for Nonemergency Events at Nuclear Power Plants ML22333A7282022-12-0606 December 2022 NRC Staff Presentation on Inservice Testing Activities by Thomas G. Scarbrough, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, at Inservice Testing Owners Group (Istog) Meeting in December 2022 ML22333A7402022-12-0505 December 2022 NRC Presentation - ASME OM Code and Snubber Issues at Inservice Service Testing Owner Group (Istog) Final - Meeting December 5-6, 2022, in Clearwater, Fl ML22340A4732022-12-0505 December 2022 NRC Presentation, Expansion of Policy for Addressing Potential Common Cause Failures in U.S. Nuclear Power Plant Digital Instrumentation and Control Systems, IAEA Technical Meeting, December 6-8 2022 ML22333A7192022-11-29029 November 2022 NEI-Presentation-Seismic Hazards Public Meeting - November 2022 - Final Presentation to NRC ML22311A5532022-11-16016 November 2022 Kairos Hermes NRC Staff Presentation at Nov 16 Public Meeting on the Draft Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor ML22318A2842022-11-0808 November 2022 Presentation Slides November 8 2022 Public Meeting on Trial Use Regulatory Guide 1.247 ML22298A2162022-10-25025 October 2022 TSTF Meeting Handout TSTF-585 and the Maintenance Rule ML22339A2282022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Beth Reed Presentation on SNM Options ML22339A2212022-10-12012 October 2022 Trtr 2022 Annual Conference Duane Hardesty Presentation on Performance Based Approach to Licensing ML22255A2042022-10-12012 October 2022 NRC Irsrr Update (Trtr 2022): Redacted ML22339A2162022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Adrian Muniz Presentation on Advanced Reactor Licensing ML22339A2192022-10-12012 October 2022 Trtr 2022 Annual Conference Duane Hardesty Presentation on Irsrr Red.Pdf ML22339A2302022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Beth Reed Breakout Session Presentation on Draft Security Measures ML22339A1862022-10-12012 October 2022 National Organization for Test, Research and Training Reactors Trtr 2022 Annual Conference Joshua Borromeo Presentation on Npuf Licensing ML22339A1912022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Travis Tate Presentation on Npuf Oversight ML22284A1412022-10-11011 October 2022 Advanced Reactor Stakeholder Slides for 10-12-2022 Public Meeting ML22262A2522022-09-20020 September 2022 Presentation - 09/20/2022 Scale Melcor Sodium Fast Reactor (Sfr) Workshop ML22255A2142022-09-12012 September 2022 Presentation - 9/13/22 Scale Melcor Molten Salt Reactor (MSR) Workshop ML22250A4272022-09-0808 September 2022 EPZ TR ACRS Subcommittee Slides - Open Session ML22245A0822022-09-0808 September 2022 September 8 2022 NRC Public Meeting with Steam Generator Task Force - NRC Presentation Final ML22243A0162022-08-31031 August 2022 GALL-SLR Public Meeting Slides - 2 of 2 ML22243A0152022-08-31031 August 2022 GALL-SLR Public Meeting Slides - 1 of 2 2024-02-14
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Text
Advanced Reactor Stakeholder Public Meeting August 18, 2022 Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 951 216 02#
1
Time Agenda Speaker 10:00 - 10:15 am Opening Remarks/ Adv. Rx Integrated Schedule NRC (Shelley Pitter - Logistics, Steve Lynch) 10:15 - 10:30 am Population-Related Siting Considerations for Advanced Reactors (next NRC Part 53 Rulemaking Process steps, including NRC path forward, role(s) for stakeholders)
(Steve Lynch) 10:30 - 11:00 am (Steve Lynch)
Part 53 Update: Status and Path Forward NRC (Steve Lynch) 11:00 am - 12:00 Part 53 - Stakeholder Perspectives Stakeholders pm (TBD) 12:00 - 1:00 pm Lunch Break All 1:00 - 1:45 pm IAEA Safeguards, the Additional Protocol, and its reporting NRC requirements (Eduardo Sastre Fuente) 1:45 - 2:30 pm Technology Inclusive Risk Informed Change Evaluation Southern (TIRICE) Guidance Company (Michael Tschiltz) 2:30 - 2:35 pm Future Meeting Planning and Concluding Remarks All 2
https://www.nrc.gov/reactors/new-reactors/advanced/integrated-review-schedule.html 3
Population-Related Siting Considerations for Advanced Reactors (next steps, including NRC path forward, role(s) for stakeholders)
(Steven Lynch) 4
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
Part 53 Update: Status and Path Forward (Steven Lynch) 8
Part 53 Rulemaking Status and Consideration of Feedback Steven Lynch, Chief Advanced Reactor Policy Branch
RULEMAKING STATUS Rule Language Stakeholder Engagement o 2021: definitions (A), safety criteria (B), design and o 21 public meetings, 2 Commission Meetings, and 18 analyses (C), siting (D), construction/manufacturing (E), ACRS meetings operations and programs (F), decommissioning (G), o Recent: 5/25 public meeting on Framework A, 6/11 public licensing processes (H), maintenance of the licensing meeting on Framework B, 6/30 stakeholder meeting on basis (I), reporting (J), security, access authorization, stakeholder feedback and Subpart F, 7/28 public meeting FFD, traditional alternatives. on Framework B and key technical topics o 2022: consolidated rule package (Feb.), 2nd iteration o Future: October ACRS Subcommittee Meeting on Framework A (May, June), 1st iteration Framework B integrated rulemaking, November ACRS Full Committee (June), updated consolidated rule package with Meeting statements of consideration (September)
Focus Areas Industry Input o Finalize rule language o Over 1500 public comments received o Develop rule package (SOCs, regulatory analysis, etc.)
o Develop guidance
CURRENT PART 53 TIMELINE Oct 2020-Aug 2022 Feb 2023 Jun 2023 Oct 2023 Public Outreach, ACRS Draft Proposed Rule to Publish Proposed Rule and Public Comment Period - 60 Interactions and Generation Commission Draft Key Guidance days of Proposed Rule Package Nov 2023-Nov 2024 Dec 2024 Apr 2025-Jun 2025 Jul 2025 Public Outreach and Draft Final Rule to Office of Management and Publish Final Rule and Key Generation of Final Rule Commission Budget and Office of the Guidance Package Federal Register Processing 11
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.
IAEA Safeguards, the Additional Protocol, and its reporting requirements (Eduardo Sastre Fuente) 13
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 NPT Signing, 1968 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 NPT RevCon, 2010 15
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
Applicable U.S. Laws and Regulations
- 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 17
U.S. Government Oversight Defined in Federal Register Subgroup on Subcommittee IAEA Sub-IPC IAEA on International Steering *Chaired by the Safeguards in Safeguards and Committee National Security the U.S. Monitoring (ISC) Council (NSC)
(SISUS) (SISM)
Nonproliferation Interagency Policy Committee (IPC)
- Chaired by the NSC Implementation Policy 18
Who Implements in the U.S.?
Who are the Players?
U.S. Nuclear Regulatory Commission
- chair Department Department of of Energy SISUS Commerce Committee Department Department of Defense of State 19
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)
U.S. VOA Comprehensive Safeguards Selection-based approach based on the Eligible Safeguards are applied on all nuclear material in the Facilities List territory (all facilities)
Completion of Design Information Questionnaire Completion of Design Information Questionnaire and Design Information Verification and Design Information Verification Monthly and annual material Monthly and annual material accountancy reports (e.g., Physical accountancy reports (e.g., Physical Inventory Listing (PIL), Inventory Inventory Listing (PIL), Inventory Change Report (ICR), etc.) Change Report (ICR), etc.)
Inspections at selected facilities under full scope Inspections at all facilities safeguards (one in the U.S.)
National Security Exclusion No Exclusions 22
Eligible Facilities List (EFL)
- Two portions of the U.S. EFL SISUS Committee Since 1981,
- DOE facilities (non-public) the IAEA has
- NRC facilities (public) selected 21
- 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 Selection direct national security significance 23
Implementation Contd.
Selection
- 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
Present
- K-Area Material Storage (KAMS) at Savannah River Site (SRS)
- Only facility currently under routine inspections by the IAEA Reporting AND
- Incorporates remote monitoring Inspections
- Allow for installation of IAEA equipment
- Westinghouse Fuel Fab. Facility (Columbia, SC)
- Framatome Fuel Fab. Facility (Richland, WA)
Reporting ONLY,
- Global Nuclear Fuel - Americas Fuel NO INSPECTIONS Fab. Facility (Wilmington, NC)
- URENCO USA Gas Centrifuge Enrichment Plant (Eunice, NM) 25
Flow of Information through NMMSS (Nuclear Materials Management & Safeguards System)
U.S. Nuclear Industry Facilities Regulatory NMMSS Commission U.S. U.S.
Department Department of of State Energy U.S.
Department of Commerce 26
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 www.AP.gov 27
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!
Additional Protocol 30
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
- 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 37
Questions?
38
Technology Inclusive Risk Informed Change Evaluation (TIRICE) Guidance (Michael Tschiltz) 39
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 August 18, 2022 Mike Tschiltz Consultant to Southern Company 40
Topics
-Project Overview
-Objectives
-Schedule
-Questions 41
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.
42
Project Overview, Objectives and Schedule 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 43
Project Overview, Objectives and Schedule
- 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 44
- Develop Table Top Guidelines and Objectives (Apr June 22) complete
Project Overview, Objectives and Schedule
- 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) 45
- ARRTF review of draft NEI guidance
Questions Thank you for your time and attention 46