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Category:Meeting Briefing Package/Handouts
MONTHYEARML24022A1192024-01-24024 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 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 ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22332A5372022-11-28028 November 2022 Draft LAR 23-001 for 12-8-22 Public Meeting 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 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 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 ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process ML21193A0762021-07-0808 July 2021 ITAAC Related to Incore Instrument Thimble Assembly (Iita) 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 ML20007D6772020-01-0808 January 2020 AP1000 Public Presentation Entitled Reactor Oversight Process (ROP) for Inspecting Vogtle Site with AP1000 Design ML19303A0252019-11-0404 November 2019 Risk-Informed GSI-191 NRC Public Meeting ML19295D4672019-10-30030 October 2019 Public Meeting for ITAAC Hearing Process, October 30, 2019 ML19239A1932019-08-29029 August 2019 SNC Slides for Public Pre-Submittal Meeting on August 29, 2019 (Eptd L-2019-LRM-0054) ND-19-0962, AP1000 Structural Reconciliation - Westinghouse Electric Company & Southern Nuclear Company Technical Exchange Meeting: August 13, 20192019-08-0202 August 2019 AP1000 Structural Reconciliation - Westinghouse Electric Company & Southern Nuclear Company Technical Exchange Meeting: August 13, 2019 ML19123A3562019-05-0202 May 2019 Public Meeting Summary - Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 ND-19-0152, Enclosure 2, Presentation Material: Functional Arrangement (FA) ITAAC, FA System Package Examples -Closed Meeting (Non-Proprietary)2019-02-14014 February 2019 Enclosure 2, Presentation Material: Functional Arrangement (FA) ITAAC, FA System Package Examples -Closed Meeting (Non-Proprietary) ML19025A0242019-01-25025 January 2019 SNC License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation 2024-01-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24022A1192024-01-24024 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 ML22319A1242022-11-15015 November 2022 NRC 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 ML22319A0052022-11-15015 November 2022 NEI 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 ML22206A1712022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22206A1682022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22201A0442022-07-20020 July 2022 Voices Dashboard Report for Vogtle Unit 3 as of July 20, 2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22144A0502022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22144A0492022-05-24024 May 2022 Dashboard Report 5-24-2022 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 ML21197A0032021-08-0606 August 2021 Slides - SNC Slides - Pre-Submittal Meeting on August 13, 2021 - Vogtle TS 3.3.1 and 3.3.2 LAR ML21193A0762021-07-0808 July 2021 ITAAC Related to Incore Instrument Thimble Assembly (Iita) ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process ML21188A3612021-07-0606 July 2021 1Q 2021 Performance Summary U4 ML21188A3592021-07-0606 July 2021 1Q 2021 Performance Summary U3 ML21188A3622021-07-0606 July 2021 Archives ML21193A0772021-06-24024 June 2021 Exemption from Operator Written Examination and Operating Test for Unit 4 Licenses, 6-24-21 Pre-submittal Meeting ML21124A2522021-05-31031 May 2021 Request for Alternative to ASME Section XI and Section III Requirements for Repair of Reactor Vessel Head Penetrations - NRC Pre-submittal Meeting May 10, 2021 (EPID L-2021-LRM-0047) (Slides) ML21085A4902021-05-19019 May 2021 Risk-informed Resolution of Generic Letter 2004-02 ML21113A2272021-04-23023 April 2021 Readiness Group Public Meeting Presentation Slides - April 28, 2021 2024-01-08
[Table view] |
Text
VEGP Unit 4 Potential LAR for Prior To Initial Criticality
Purpose
- Proactively Implement Unit 3 Lessons Learned
- Unit 3 Post Fuel Load Technical Specifications Amendments
>> Amendment 189: Emergency LAR for ADS Stage-4 Supports
>> Amendment 190: Exigent LAR for IRWST Injection Valve Repair
- Anticipate Appropriate Unit 4 Flexibility
- Establish Safety Basis Applicable Prior to Initial Criticality
- Submit LAR to Allow Timely Review 2
Lessons Learned
- Unit 3 Emergency LAR for ADS Stage-4 Supports
- ADS Stage-4 Not Required for Safety Prior to Criticality
>> Exceptions Applicable to MODES 4, 5, & 6
>> Safety Based On:
Lessons Learned
- Unit 3 Exigent LAR for IRWST Injection Valve Repair
- IRWST & ADS Stage-4 Not Required for Safety
>> Exceptions Applicable to MODES 5 & 6
>> Safety Based On:
- No Fission Products (No Radiological Consequences)
- Core Remains Submerged with Borated Water -- Low Evaporative Losses (< 200°F)
- Inadvertent Boron Dilution Prevented 4
Unit 4 Potential LAR - Reason For Request
- Expand Flexibility Beyond IRWST and ADS Stage-4
- Minimizes the Potential for Subsequent Emergency & Exigent LARs
- Enhance Startup Testing Efficiency
- Establish Appropriate Safety Basis for Operation Prior to Criticality 5
Unit 4 Potential LAR - Safety Basis
- Establish Appropriate Safety Basis for Prior to Initial Criticality
- Technical Specification Requirements Considerations:
>> No Exclusions for Core Reactivity Protections
>> No Exclusions for Reactor Vessel Integrity Protections
>> No Exclusions for MODE 3 (Based on Steamline Break Potential for Criticality)
>> MODE 5 & 6 Exclusions Similar to Previous Amendments - Based On:
- No Core Fission Products (No Radiological Consequences)
- Core Remains Submerged with Borated Water
- Inadvertent Boron Dilution Prevented 6
Unit 4 Potential LAR - Approach
- Modify Current COL Condition for TS Effectiveness Timing
- Current Timing 52.103(g) Finding
- Proposed Timing in Two Groups
>> Portions Related to Reactivity & Vessel Integrity at 52.103(g) Finding
>> Portions Related other TS:
- While Operating in MODE 3
- Prior to Initial Criticality
- LCO 3.0.7 is Designed to Address TS Exceptions
- LCO 3.0.7 Avoids Potential Conflicting Requirements 7
Unit 4 Potential LAR - Approach
- Revising COL Condition Defining TS Effective Timing
- Currently Established Mechanism Defining When TS Are Effective
- Providing COL Staged Effectiveness vs TS Notes
>> Minimizes TS Presentation Impacts to Operators
>> Avoids Additional Complexity if Numerous Notes Added
- Consistent Application of Special Operational Requirement Exceptions
- Recognizes the Tie Between COL Condition and TS Effectiveness 8
Unit 4 Potential LAR - Approach
- Tentative COL Condition 2.D(9) Changes:
The technical specifications in Appendix A to this license listed below become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g). The remainder of the technical specifications in Appendix A to this license become effective while operating in plant operational Mode 3 (Hot Standby) and become fully effective at initial criticality of the reactor core.
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Unit 4 Potential LAR - Approach
- Tentative LCO 3.0.7 Changes:
Test Exception LCOs 3.1.8 and 3.1.10 allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.
For Unit 4 only, Combined License Condition 2.D(9) provides the milestone effectiveness for specified TS requirements. Compliance with TS requirements that become effective while operating in MODE 3 and become fully effective at initial criticality of the reactor core, in accordance with the COL Condition, is optional prior to operation in MODE 3.
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Summary
- Minimize Potential for Future Emergency / Exigent LAR
- Establish Safety Basis for Prior to Criticality
- Revise COL Condition Defining TS Effective Timing
- Revise LCO 3.0.7 Recognizes the COL Condition Tie 11}}