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Category:Meeting Briefing Package/Handouts
MONTHYEARML24289A2352024-10-15015 October 2024 Supplemental Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 PRHR LAR ML24283A2022024-10-0909 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 16, 2024 - Proposed Vogtle 3 and 4 Flexibility Modes LAR ML24282A9822024-10-0808 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 Passive Residual Heat Removal Actuation Logic Changes License Amendment Request ML24164A2942024-06-17017 June 2024 Licensee Slides for Pre-submittal Meeting for VEGP Units 3 and 4 for a Proposed License Amendment Request Regarding TS 3.3.8 ML24158A3832024-06-0606 June 2024 SNC Slides - Vogtle 3 and 4 - TS 3-8-2 - Pre-Submittal Meeting - 06-27-2024 ML24120A2202024-04-30030 April 2024 Annual Assessment Meeting Presentation Slides - April 30, 2024 ML24089A1492024-04-0404 April 2024 Slides - SNC Presentation - Pre-Submittal Meeting on April 4, 2024 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML24060A2732024-03-0707 March 2024 SNC Slides - Pre-Submittal Meeting on March 7, 2024 - Vogtle 3 & 4 TSTF-577 LAR ML24022A1192024-01-24024 January 2024 Slides - SNC Slides - Pre-Submittal Meeting on January 24, 2024 - Vogtle 3 & 4 Explosively Actuated Valves Relief Request ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML24004A1852024-01-0404 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR Revised ML23257A2322023-09-28028 September 2023 SNC Presentation - Pre-Submittal Meeting on September 28, 2023 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML23137A1162023-06-0202 June 2023 Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23094A1402023-04-0404 April 2023 4 -- 2022 Aam Slides ML23055A0402023-02-24024 February 2023 VEGP, Unit 4, Potential License Amendment Request for Prior to Initial Criticality Overview Presentation ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 ML22329A0192022-12-0101 December 2022 Southern Nuclear Company Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request 1 ML22332A5372022-11-28028 November 2022 Draft LAR 23-001 for 12-8-22 Public Meeting ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22319A1242022-11-15015 November 2022 NRC Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22319A0052022-11-15015 November 2022 NEI Slides for November 15 2022 Public Meeting on Part 52 Lessons Learned ML22319A1232022-11-15015 November 2022 Kozak Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22251A0002022-09-30030 September 2022 Pre-Submittal Meeting on September 13, 2022 - Vogtle Online Monitoring LAR ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation for Public Meeting on 9/27/2022 ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22137A2812022-05-23023 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 23, 2022 - Vogtle TS 3.8.1 and TSTF-163 LAR ML22126A0102022-05-11011 May 2022 Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemption Requests - Licensing Questions ML22123A3332022-05-10010 May 2022 Pre-Submittal Meeting 2: TSTF-51, TSTF-471, TSTF-490, and Alternative Source Term License Amendment Request - May 10, 2022 (EPID L-2022-LRM-0033)(slides) ML22110A1702022-04-20020 April 2022 4 2022 Annual Assessment Meeting.Final ML22021B6472022-01-27027 January 2022 Pre-Submittal for Westinghouse Increased Enrichment Accident Tolerant Fuel Lead Test Assemblies (EPID L-2022-LRM-0003) (Slides) ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21333A2172021-11-29029 November 2021 Readiness Group Presentation During 12-2-21 Public Meeting ML21230A2842021-08-18018 August 2021 SNC Slides - Vogtle MSIV Elimination LAR - Pre-submittal Meeting Part 2 - 08-25-2021 ML21193A0762021-07-0808 July 2021 ITAAC Related to Incore Instrument Thimble Assembly (Iita) ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process ML21172A1312021-07-0101 July 2021 Pre-Submittal Meeting Alternate Source Term and TSTF-490 ML21193A0772021-06-24024 June 2021 Exemption from Operator Written Examination and Operating Test for Unit 4 Licenses, 6-24-21 Pre-submittal Meeting ML21085A4902021-05-19019 May 2021 Risk-informed Resolution of Generic Letter 2004-02 ML21064A3652021-03-0101 March 2021 Dashboard Report 3-1-2021 ML21027A2062021-02-28028 February 2021 Fixed 8-Hour Emergency Light Deviation Pre-Submittal Meeting, February 2021 (Slides) ML21057A0182021-02-26026 February 2021 Pre-Submittal Meeting Revise Technical Specification 3.2.1 Heat Flux Hot Channel Factor (Fq(Z)) (EPID L-2021-LRM-0023) (Slides) ML21036A1172021-02-0505 February 2021 SNC Slides - Pre-Submittal Meeting on February 16, 2021 - Beacon LAR ML20343A0742020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20314A0962020-11-0202 November 2020 Dashboard Report 11/02/2020 ML20217L4312020-08-13013 August 2020 Edwin I Hatch, Units 1 and 2; and Vogtle Electric Plant, Units 1, 2, 3, and 4 - Meeting Slides a License Amendment Request for the Emergency Plan (EPID Nos L-2020-LLA-0150 and L-2020-LLA-051 ML20136A2832020-05-15015 May 2020 4 EOC Slides ML20114E3032020-04-23023 April 2020 Risk-Informed GL 2004--02 Pre-Submittal NRC Meeting - May 2020 2024-06-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) NL-24-0170, Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report2024-04-25025 April 2024 Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0045, Supplement to Response to Requests for Additional Information for Proposed Alternative ALT-VR-022024-02-0808 February 2024 Supplement to Response to Requests for Additional Information for Proposed Alternative ALT-VR-02 NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters – Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters – Operating, Completion Time Extension (LAR-22-002S2) NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-22-0609, Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2022-09-13013 September 2022 Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-22-0549, Responses to NRC Request for Additional Information for Refueling Outage 1R23 Steam Generator Tube Inspection Report2022-07-19019 July 2022 Responses to NRC Request for Additional Information for Refueling Outage 1R23 Steam Generator Tube Inspection Report ND-22-0328, Enclosuvogtle Electric Generating Plant, Units 3 & 4 - Fukushima Response NEI 12-01 On-Shift Staffing Analysis Phase 2 Report, Revision 3.0, Standard Emergency Plan Annex, Revision 6.02022-06-29029 June 2022 Enclosuvogtle Electric Generating Plant, Units 3 & 4 - Fukushima Response NEI 12-01 On-Shift Staffing Analysis Phase 2 Report, Revision 3.0, Standard Emergency Plan Annex, Revision 6.0 NL-22-0055, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2022-02-28028 February 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System NL-21-1015, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2022-01-13013 January 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System ND-21-0618, Response to Request for Additional Information Regarding Request for Alternative: Alternative Requirements for ASME Section Ill Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16)2021-07-0202 July 2021 Response to Request for Additional Information Regarding Request for Alternative: Alternative Requirements for ASME Section Ill Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16) NL-21-0208, Response to Request for Additional Information Related to Refueling Outage 1R22 Steam Generator Tube Inspection Report2021-03-0202 March 2021 Response to Request for Additional Information Related to Refueling Outage 1R22 Steam Generator Tube Inspection Report NL-20-1417, Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-1912020-12-17017 December 2020 Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-191 NL-20-1312, Response to Request for Additional Information Related to Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.02020-11-23023 November 2020 Response to Request for Additional Information Related to Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.0 NL-20-1273, Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for2020-11-20020 November 2020 Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for ND-20-1005, Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1)2020-09-18018 September 2020 Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1) NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request ND-19-1097, Response to Request for Additional Information - LAR-19-013R12019-11-0101 November 2019 Response to Request for Additional Information - LAR-19-013R1 NL-19-1183, Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown2019-10-17017 October 2019 Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown ND-19-1023, Enclosure 7 - Response to Draft Request for Additional Information (LAR-19-005R1)2019-10-10010 October 2019 Enclosure 7 - Response to Draft Request for Additional Information (LAR-19-005R1) ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification ...2019-10-0707 October 2019 Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification ... ND-19-1177, Supplement to Request for License Amendment and Exemption: Addition of In-Containment Refueling Water Storage Tank to Radiation Analyses (LAR-19-003S1)2019-10-0303 October 2019 Supplement to Request for License Amendment and Exemption: Addition of In-Containment Refueling Water Storage Tank to Radiation Analyses (LAR-19-003S1) NL-19-0709, Core Operating Limits Report, Cycle 21, Version 1, SNC Response to NRC Request for Additional Information2019-06-17017 June 2019 Core Operating Limits Report, Cycle 21, Version 1, SNC Response to NRC Request for Additional Information NL-19-0498, License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable SNC Response to NRC Request for ...2019-04-30030 April 2019 License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable SNC Response to NRC Request for ... ND-19-0289, Enclosure 1 - Revised Response to Request for Additional Information Question 1b Related to Request for Exemption from Operator Written Examination and Operating Test2019-04-16016 April 2019 Enclosure 1 - Revised Response to Request for Additional Information Question 1b Related to Request for Exemption from Operator Written Examination and Operating Test ND-19-0178, Supplement to Request for Exemption: 10 CFR Part 26 Visitor Access Requirements (Supplement 1)2019-03-0808 March 2019 Supplement to Request for Exemption: 10 CFR Part 26 Visitor Access Requirements (Supplement 1) ND-19-0216, Response to Request for Additional Information Related to Request for Exemption from Operator Written Examination and Operating Test2019-03-0404 March 2019 Response to Request for Additional Information Related to Request for Exemption from Operator Written Examination and Operating Test NL-18-1514, Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift.2019-01-31031 January 2019 Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift. ND-19-0007, Supplement to Request for Alternative: Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI/ISI-ALT-06S1)2019-01-28028 January 2019 Supplement to Request for Alternative: Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI/ISI-ALT-06S1) ND-18-1439, Revised Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017R1)2018-12-0303 December 2018 Revised Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017R1) NL-18-1181, Relief Requests VEGP-ISI-RR-05 and VEGP-ISI-RR-06, SNC Response to NRC Request for Additional Information2018-10-17017 October 2018 Relief Requests VEGP-ISI-RR-05 and VEGP-ISI-RR-06, SNC Response to NRC Request for Additional Information ND-18-1058, Supplement to Request for License Amendment and Exemption: Containment Pressure Analysis (LAR-17-043S1)2018-09-28028 September 2018 Supplement to Request for License Amendment and Exemption: Containment Pressure Analysis (LAR-17-043S1) NL-18-1130, Units 1 and 2 - Relief Request VEGP-ISI-RR-03: SNC Response to NRC Request for Additional Information2018-09-26026 September 2018 Units 1 and 2 - Relief Request VEGP-ISI-RR-03: SNC Response to NRC Request for Additional Information NL-18-1179, Response to NRC Request for Additional Information Tornado Missile Risk Evaluator SNC Supplemental2018-09-14014 September 2018 Response to NRC Request for Additional Information Tornado Missile Risk Evaluator SNC Supplemental 2024-08-14
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24317A2232024-11-12012 November 2024 Slides - SNC Presentation - Pre-Submittal Meeting on November 19, 2024 - Proposed Vogtle 3 and 4 Modes 5 and 6 LAR ML24317A0032024-11-12012 November 2024 Slides - SNC Presentation - Pre-Submittal Meeting on November 18, 2024 - Proposed Vogtle 3 and 4 SR TS 3.3.15 and TS 3.3.16 Licensing Amendment Request ML24289A2352024-10-15015 October 2024 Supplemental Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 PRHR LAR ML24283A2022024-10-0909 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 16, 2024 - Proposed Vogtle 3 and 4 Flexibility Modes LAR ML24282A9822024-10-0808 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 Passive Residual Heat Removal Actuation Logic Changes License Amendment Request ML24164A2942024-06-17017 June 2024 Licensee Slides for Pre-submittal Meeting for VEGP Units 3 and 4 for a Proposed License Amendment Request Regarding TS 3.3.8 ML24158A3832024-06-0606 June 2024 SNC Slides - Vogtle 3 and 4 - TS 3-8-2 - Pre-Submittal Meeting - 06-27-2024 ML24120A2202024-04-30030 April 2024 Annual Assessment Meeting Presentation Slides - April 30, 2024 ML24089A1492024-04-0404 April 2024 Slides - SNC Presentation - Pre-Submittal Meeting on April 4, 2024 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML24060A2732024-03-0707 March 2024 SNC Slides - Pre-Submittal Meeting on March 7, 2024 - Vogtle 3 & 4 TSTF-577 LAR ML24022A1192024-01-24024 January 2024 Slides - SNC Slides - Pre-Submittal Meeting on January 24, 2024 - Vogtle 3 & 4 Explosively Actuated Valves Relief Request ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML24004A1852024-01-0404 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR Revised ML23304A2682023-11-0707 November 2023 License Amendment Request to Revise the Ultimate Heat Sink Mission Time Pre Submittal Meeting on November 7, 2023 ML23311A2452023-11-0707 November 2023 Pre-Submittal Meeting on November 7, 2023 - License Amendment Request to Revise the Ultimate Heat Sink Mission Time (Slides) ML23293A0052023-10-20020 October 2023 Lessons Learned from the ITAAC Hearing Process for Vogtle 3 and 4 ML23257A2322023-09-28028 September 2023 SNC Presentation - Pre-Submittal Meeting on September 28, 2023 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML23137A1162023-06-0202 June 2023 Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23094A1402023-04-0404 April 2023 4 -- 2022 Aam Slides ML23072A1802023-03-13013 March 2023 2023 RIC Powerpoint Slide Presentation, Vogtle 3: Journey from Construction to Operations ML23055A0402023-02-24024 February 2023 VEGP, Unit 4, Potential License Amendment Request for Prior to Initial Criticality Overview Presentation ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22335A5542022-12-0101 December 2022 Slides - SNC Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request - ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 ML22329A0192022-12-0101 December 2022 Southern Nuclear Company Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request 1 ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22319A1232022-11-15015 November 2022 Kozak Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22319A0052022-11-15015 November 2022 NEI Slides for November 15 2022 Public Meeting on Part 52 Lessons Learned ML22319A1242022-11-15015 November 2022 NRC Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22251A0002022-09-30030 September 2022 Pre-Submittal Meeting on September 13, 2022 - Vogtle Online Monitoring LAR ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation for Public Meeting on 9/27/2022 ML22206A1682022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22206A1712022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22201A0442022-07-20020 July 2022 Voices Dashboard Report for Vogtle Unit 3 as of July 20, 2022 ML22144A0502022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22144A0492022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22137A2812022-05-23023 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 23, 2022 - Vogtle TS 3.8.1 and TSTF-163 LAR ML22126A0102022-05-11011 May 2022 Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemption Requests - Licensing Questions ML22123A3332022-05-10010 May 2022 Pre-Submittal Meeting 2: TSTF-51, TSTF-471, TSTF-490, and Alternative Source Term License Amendment Request - May 10, 2022 (EPID L-2022-LRM-0033)(slides) ML22126A0012022-05-0606 May 2022 SNC Slides - Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemptions ML22110A1702022-04-20020 April 2022 4 2022 Annual Assessment Meeting.Final ML22060A0062022-02-28028 February 2022 4Q 2021 Performance Summary U3 ML22021B6472022-01-27027 January 2022 Pre-Submittal for Westinghouse Increased Enrichment Accident Tolerant Fuel Lead Test Assemblies (EPID L-2022-LRM-0003) (Slides) ML22026A0582022-01-26026 January 2022 Dashboard Report 1-26-2022 ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21333A2172021-11-29029 November 2021 Readiness Group Presentation During 12-2-21 Public Meeting ML21230A2842021-08-18018 August 2021 SNC Slides - Vogtle MSIV Elimination LAR - Pre-submittal Meeting Part 2 - 08-25-2021 2024-06-06
[Table view] |
Text
NRC Public Meeting on VEGP Draft RAIs 12/8/15 - Rockville, MD
Draft RAI 1.a Confirm that SSCs credited in a PRA Functionality determination are the same SSCs relied upon to perform the specified safety function.
VEGP Proposed Response:
- VEGP may credit alternative SSCs to establish PRA Functionality if modeled in the PRA. This is not prohibited by NEI 06-09.
Draft RAI 1.b.i Confirm that all human actions required to achieve PRA functionality upon loss of specified safety function are modeled in the PRA (i.e., are proceduralized and trained on or so simple to be skill of the craft).
VEGP Proposed Response: Human actions required to achieve PRA Functionality upon loss of specified safety function are modeled in the PRA, and are proceduralized and trained.
Draft RAI 1.b.ii (part 1)
Confirm that actions to open doors during loss of room cooling are explicitly proceduralized and trained on and summarize the evaluation concluding the HEPs are extremely small.
VEGP Proposed Response Plan:
- Actions to open doors when required are proceduralized and trained on.
- HEPs for failure to open doors are very low (simple actions, low stress, with long available time).
Draft RAI 1.b.ii (part 2)
Clarify why these actions [opening doors] have a negligible impact on CDF and LERF and the associated CT that will be used when room cooling is unavailable.
VEGP Proposed Response Plan:
- Change in CDP and LERP is negligible to zero when critical room doors can be propped open during loss of room cooling and the time available for this action is long.
- Actual RICT is based on plant configuration.
- A maximum of 30 day RICT is possible.
Draft RAI 1.b.iii If any other human actions are directly or indirectly credited in the CT length calculations, please provide the same information requested in 1.b.ii about each action.
VEGP Proposed Response Plan:
Human actions not evaluated in the PRA will not be credited in CT length calculations.
Draft RAI 1.c Confirm that PRA Functionality does not include any scenarios that allow any design basis accident to proceed directly to core damage or containment failure.
VEGP Proposed Response Plan:
NRC SE on NEI 06-09 has no requirements to identify scenarios that proceed directly to core damage or containment failure when a PRA Functionality evaluation is performed.
Draft RAI 2.a Confirm that the acceptable PRA Function modeled in the PRA is also available and sufficient for the remaining design basis accident scenarios that are not modeled in the PRA.
VEGP Proposed Response Plan:
For design basis accident scenarios that are not modeled in the PRA because they do not affect CDF or LERF, the PRA Functionality evaluation will ensure SSCs not supporting CDF/LERF will remain available.
Draft RAI 2.b Confirm there are no safety functions required to reach a safe and stable state but not included in the PRA because they are only required after the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mission time generally used in the PRA.
VEGP Proposed Response Plan:
- VEGP PRA was developed and peer reviewed against the NRC endorsed standards and meets mission time and initiator selection requirements.
- The VEGP PRA quality has been reviewed by the NRC and considered acceptable for NRC approved risk-informed applications, such as 50.69 and 5B.
Draft RAI 2.c For LOF cases, please elaborate on how adequate safety margins are maintained and provide some clarifying examples of adequate safety margins for where the PRA success criteria (e.g., flow rates, temperature limits) differ from the design criteria.
VEGP Proposed Response Plan:
- NRC SE on NEI 06-09 clearly states that, The design, operation, testing methods, and acceptance criteria for SSCs, specified in applicable codes and standards (or alternatives approved for use by the NRC) will continue to be met as described in the plant licensing basis (including the final safety analysis report and bases to TSs),
since these are not affected by risk-informed changes to the CTs. Similarly, there is no impact to safety analysis acceptance criteria as described in the plant licensing basis.
Thus, safety margins are maintained by the proposed methodology, and the third key safety principle of RG 1.177 is satisfied.
- VEGP LAR and responses to NRC RAIs demonstrate that the above statements are fully applicable to VEGP without exceptions.
- VEGP intends to enter a RICT during emergent plant conditions if TS inoperable SSCs are demonstrated to be PRA Functional such that a loss of safety function is no longer possible.
Draft RAI EDG CTs Provide technical justification for the addition of a RICT for the Required Actions associated with LCO 3.8.1 Condition C.
VEGP Proposed Response Plan:
- A RICT can be applied to the 14 day AOT with the CTG available (Condition B) OR if the CTG is unavailable (Condition C).
- Plants that rely on a non-TS AAC source can apply a RICT to a TS DG when the non-TS AAC source is non-functional. The RICT would account for either situation.
- NRC SE on NEI 06-09 has no special requirements for treating DGs different than other SSCs.
NRC Public Meeting on VEGP Draft RAIs 12/8/15 - Rockville, MD
Draft RAI 1.a Confirm that SSCs credited in a PRA Functionality determination are the same SSCs relied upon to perform the specified safety function.
VEGP Proposed Response:
- VEGP may credit alternative SSCs to establish PRA Functionality if modeled in the PRA. This is not prohibited by NEI 06-09.
Draft RAI 1.b.i Confirm that all human actions required to achieve PRA functionality upon loss of specified safety function are modeled in the PRA (i.e., are proceduralized and trained on or so simple to be skill of the craft).
VEGP Proposed Response: Human actions required to achieve PRA Functionality upon loss of specified safety function are modeled in the PRA, and are proceduralized and trained.
Draft RAI 1.b.ii (part 1)
Confirm that actions to open doors during loss of room cooling are explicitly proceduralized and trained on and summarize the evaluation concluding the HEPs are extremely small.
VEGP Proposed Response Plan:
- Actions to open doors when required are proceduralized and trained on.
- HEPs for failure to open doors are very low (simple actions, low stress, with long available time).
Draft RAI 1.b.ii (part 2)
Clarify why these actions [opening doors] have a negligible impact on CDF and LERF and the associated CT that will be used when room cooling is unavailable.
VEGP Proposed Response Plan:
- Change in CDP and LERP is negligible to zero when critical room doors can be propped open during loss of room cooling and the time available for this action is long.
- Actual RICT is based on plant configuration.
- A maximum of 30 day RICT is possible.
Draft RAI 1.b.iii If any other human actions are directly or indirectly credited in the CT length calculations, please provide the same information requested in 1.b.ii about each action.
VEGP Proposed Response Plan:
Human actions not evaluated in the PRA will not be credited in CT length calculations.
Draft RAI 1.c Confirm that PRA Functionality does not include any scenarios that allow any design basis accident to proceed directly to core damage or containment failure.
VEGP Proposed Response Plan:
NRC SE on NEI 06-09 has no requirements to identify scenarios that proceed directly to core damage or containment failure when a PRA Functionality evaluation is performed.
Draft RAI 2.a Confirm that the acceptable PRA Function modeled in the PRA is also available and sufficient for the remaining design basis accident scenarios that are not modeled in the PRA.
VEGP Proposed Response Plan:
For design basis accident scenarios that are not modeled in the PRA because they do not affect CDF or LERF, the PRA Functionality evaluation will ensure SSCs not supporting CDF/LERF will remain available.
Draft RAI 2.b Confirm there are no safety functions required to reach a safe and stable state but not included in the PRA because they are only required after the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mission time generally used in the PRA.
VEGP Proposed Response Plan:
- VEGP PRA was developed and peer reviewed against the NRC endorsed standards and meets mission time and initiator selection requirements.
- The VEGP PRA quality has been reviewed by the NRC and considered acceptable for NRC approved risk-informed applications, such as 50.69 and 5B.
Draft RAI 2.c For LOF cases, please elaborate on how adequate safety margins are maintained and provide some clarifying examples of adequate safety margins for where the PRA success criteria (e.g., flow rates, temperature limits) differ from the design criteria.
VEGP Proposed Response Plan:
- NRC SE on NEI 06-09 clearly states that, The design, operation, testing methods, and acceptance criteria for SSCs, specified in applicable codes and standards (or alternatives approved for use by the NRC) will continue to be met as described in the plant licensing basis (including the final safety analysis report and bases to TSs),
since these are not affected by risk-informed changes to the CTs. Similarly, there is no impact to safety analysis acceptance criteria as described in the plant licensing basis.
Thus, safety margins are maintained by the proposed methodology, and the third key safety principle of RG 1.177 is satisfied.
- VEGP LAR and responses to NRC RAIs demonstrate that the above statements are fully applicable to VEGP without exceptions.
- VEGP intends to enter a RICT during emergent plant conditions if TS inoperable SSCs are demonstrated to be PRA Functional such that a loss of safety function is no longer possible.
Draft RAI EDG CTs Provide technical justification for the addition of a RICT for the Required Actions associated with LCO 3.8.1 Condition C.
VEGP Proposed Response Plan:
- A RICT can be applied to the 14 day AOT with the CTG available (Condition B) OR if the CTG is unavailable (Condition C).
- Plants that rely on a non-TS AAC source can apply a RICT to a TS DG when the non-TS AAC source is non-functional. The RICT would account for either situation.
- NRC SE on NEI 06-09 has no special requirements for treating DGs different than other SSCs.