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MONTHYEARML24164A2942024-06-17017 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 Project stage: Meeting 2024-06-17
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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: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
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Proposed Vogtle Electric Generating Plant Units 3 & 4 License Amendment Request Revise Technical Specification 3.3.8 Engineered Safety Feature Actuation System Instrumentation Function 17, Source Range Neutron Flux Doubling Remove MODE 2 APPLICABILITY June 17, 2024
Agenda Description Technical Evaluation Regulatory Evaluation Schedule Discussion / Feedback
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability DESCRIPTION
- Engineered Safety Feature Actuation System (ESFAS) Instrumentation
- Table 3.3.8-1, Function 17, required OPERABLE in MODES 2, 3, 4, 5
- Source Range Neutron Flux Doubling Function:
- Purpose is to block boron dilution event
- Terminates supply from dilution sources
- TS 3.3.8 allows Function to be blocked during startup
- Applicability Note provides exceptions - when the reactor is critical or when an intentional approach to criticality is in progress
- i.e., when in MODE 2 or when proceeding from MODE 3 into MODE 2 3
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability Proposed Changes to TS 3.3.8, Table 3.3.8-1, Function 17 4
2(i),3(i),4(j) 5(j)
- 17. Source Range Neutron Flux Doubling
(i) With unborated water source flow paths not isolated except when critical or except during intentional approach to criticality (j) With unborated water source flow paths not isolated
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability DESCRIPTION (continued)
- Final Safety Analysis Report (FSAR) Subsection 7.3.1.2.14 termination of a boron dilution event via actuations from the source range neutron flux doubling function
- Includes discussion of blocking the function when above the P-6 setpoint (~1E5 cps) and when above the P-8 setpoint (~551 F [TS 3.4.2, Minimum Temperature for Criticality])
- Startup Procedures block the source range neutron flux doubling function above the P-6 and P-8 setpoints while in MODE 3 (as allowed by TS 3.3.8 Applicability footnote) and in MODE 2
- Blocked while in MODE 3 when an intentional approach to criticality is in progress
- Continues to be blocked while in MODE 2 when an intentional approach to criticality is in progress
- Continues to be blocked while in MODE 2 when the reactor is critical 5
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability TECHNICAL EVALUATION
- FSAR Subsection 15.4.6.2.5 describes the boron dilution event analysis during startup
- Credits only the source range reactor trip function (TS 3.3.2)
- Does not credit the source range neutron flux doubling function (TS 3.3.8)
- Boron Dilution Protection System MODE 2 Applicability is [bracketed]
- Applicability Note allows blocking boron dilution flux doubling signal while in MODE 2 and 3 during reactor startup
- Per Bases, The accident analyses rely on automatic BDPS actuation to mitigate the consequences of inadvertent boron dilution events.
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Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability TECHNICAL EVALUATION (continued)
- Consistent with Vogtle Units 1 and 2 TS 3.3.8
- High Flux at Shutdown Alarm Applicability does not include MODE 2
- Applicability Note allows blocking the alarm in MODE 3 during reactor startup 7
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability REGULATORY EVALUATION
- Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions
- Source range neutron flux doubling function not required for anticipated operational occurrences or for accident conditions
- The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.
- Source range neutron flux doubling function not required for anticipated operational occurrences or for accident conditions 8
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability REGULATORY EVALUATION
- an LCO is required for a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
- Source range neutron flux doubling function is not part of the primary success path for a design basis accident or transient
- Significant Hazards Consideration
- No significant hazards identified
- Environmental Consideration
- Meets the eligibility criteria for categorical exclusion 9
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability Proposed Changes to TS 3.3.8, Table 3.3.8-1, Function 17 10 2(i),3(i),4(j) 5(j)
- 17. Source Range Neutron Flux Doubling
(i) With unborated water source flow paths not isolated except when critical or except during intentional approach to criticality (j) With unborated water source flow paths not isolated
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability Related Bases Changes to TS 3.3.8, Function 17 (for information)
- 17. Source Range Neutron Flux Doubling
The signal to block boron dilution on source range neutron flux increasing at an excessive rate (source range neutron flux doubling) must be OPERABLE in MODE 2 and MODE 3 if unborated water source flow paths are not isolated except. However, the signal to block boron dilution on source range flux doubling is not required in MODE 2 or MODE 3 when the reactor is critical or when an intentional approach to criticality is in progress. It must also be OPERABLE in MODES 4 and 5 if unborated water flow paths are not isolated. In MODE 6, a dilution event is precluded by the requirement in LCO 3.9.2 to close, lock and secure at least one valve in each unborated water source flow path.
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Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability Schedule
- Target submittal 3rd Qtr 2024
- Target approval 3rd Qtr 2025 12
Remove Technical Specification 3.3.8, Function 17, Mode 2 Applicability Discussion / Feedback 13