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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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Text
July 8, 2021 Vogtle 3&4 ITAAC Related to Incore Instrument Thimble Assembly (IITA)
2 Background
- 6/24/21SNC discussion regarding draft ICN for ITAAC 515
-Added manufacturer inspections to draft ICN in accordance with NEI 08-01, Section 9.5, because the DAS core exit temperature sensors (located within the IITA) cant be installed in final as-built location until core fuel load
-NRC requests additional discussion
- 7/8/21Follow-up discussion agenda:
-IITA Design & Installation
-Related ITAAC
3
- IITA cables are inserted into 8 Quickloc assemblies which penetrate the upper head of the reactor vessel
- IITA cables from 8 reactor vessel head penetrations are connected to the 42 IITAs which are supported by the Instrumentation Grid Assembly (IGA)
- 42 IITAs are inserted into the fuel assemblies during operation (38 PMS & 4 DAS)
IITA Design
4 Refueling Operations
- Prior to removal of the IHP and reactor vessel head for refueling the IITA cables are disconnected at the Quickloc nozzle
- The Quickloc device is removed and the IHP with the reactor vessel head are both removed and transported to the head storage stand
- The Upper Reactor Vessel Internals assembly is prepared for moving to the upper internals stand by lifting the Instrumentation Grid Assembly (IGA) plate and with it lifting the IITAs out of the fuel assemblies
- The Upper Reactor Vessel Internals assembly, including the IGA, is then placed on the Upper Reactor Vessel Internals assembly stand within the refueling cavity
5 Initial Fuel Load
- Following initial core fuel load the Upper Reactor Vessel Internals assembly is installed in the Reactor Vessel
- Upper Reactor Vessel Internals assembly houses the IGA containing the 42 IITAs
- IGA is then lowered into its seated position
- IHP with the reactor vessel head are both installed
- Quickloc device installed
- IITA cables are connected at the Quickloc nozzle
6 Incore Instrumentation System Precritical Verification
- Verifications performed after initial fuel load and IITAs installed
- Electrical continuity checks made at the incore instrumentation system panel to verify proper installation and connection of the incore sensor strings
- Incore thermocouple data compared with the measured reactor coolant system temperature to verify proper operation of the incore thermocouples and signal processing
- Confirms that the incore instrumentation thimbles have been installed correctly following initial fuel load
- Confirms proper operation of the incore thermocouples prior to plant heatup
7 IITA ITAAC Discussion
- Requires inspection of as-built Diverse Actual System (DAS) sensor inputs
>> Demonstrate DAS sensor inputs are separate from those used by Protection and Safety Monitoring System (PMS) and Plant Control System (PLS)
>> DAS Core Exit Temperature (CET) sensors are located in 4 of the 42 IITAs (other 38 IITAs are for PMS) and therefore cannot be installed until after fuel is loaded in core
- Utilized NEI 08-01 section 9.5 to credit inspection of IITAs and their DAS CET sensors performed at manufacturer prior to shipment to the plant site, since sensors will be not installed in their final as-built location until core fuel load.
- Utilized construction drawings and work packages to demonstrate remainder of DAS CET sensor installation outside of the IITAs
- Preparation of ITAAC Principal Closure Document led to review of other ITAACs associated with incore instrumentation
8 Other IITA Related ITAACs
- Deleted in License Amendment 85 based on the Function Arrangement being verified by other ITAAC
- Not impacted since the basis for deleting ITAAC 505 remains valid, i.e., ITAAC 506 preserves the Design Commitment, Inspection Tests, Analyses (ITA), and Acceptance criteria for ITAAC 505.
- ITAAC 564 (Incore Instrumentation System (IIS) Functional Arrangement)
- Deleted in License Amendment 170 based on the Function Arrangement being verified by other ITAAC
- Not impacted since the basis for deleting ITAAC 564 remains valid, i.e., ITAACs 565, 570 and 572 remain
9 Other IITA Related ITAACs
- ITAAC 556 (Data Display Processing System (DDS) Functional Arrangement)
- Unit 3 ICN documents review of the DDS Network and Workstation Cabinets.
- Not impacted since individual IITA sensor inputs were not within the scope of the ITA or AC.
- ITAAC 570 (IIS cable sheaths)
- Similar to the approach for ITAAC 515, U3 ICN for ITAAC 570 documents inspections performed both at manufacturer and on-site.
- ITAAC 572 (IIS Core Exit Temperature (CET) safety-related displays in MCR)
- Not impacted. As described in UIN this ITAAC injects a test signal for CET and visually confirms that when each of the safety-related displays for CET is summoned from a Main Control Room PMS Visual Display Unit (VDU), the summoned CET appears on the PMS VDU.
10 10 Other IITA Related ITAACs
- 2.i (CET displays in Remote Shutdown Workstation (RSW))
>> Not impacted. Testing forces the Data Display System CET input parameter from an engineering workstation and CET display data recorded from RSW.
- 2.ii (CET visual Alerts at RSW)
>> Not impacted. As described in UIN, a combination of factory acceptance and on-site testing is performed. Testing forces the applicable Data Display System CET input parameter from an engineering workstation and visually confirms that when each of the plant parameters is used to generate visual alerts that identify challenges to Critical Safety Functions, the summoned plant visual alert appears on a display monitor at the RSW.
- Not impacted. Test signal will be used to inspect and record CET display data.
11 11 Other IITA Related ITAACs
- Not impacted. Test signal will be used to inspect and record CET display data.
- Not impacted. Testing is performed by simulating an analog signal and then inspection is performed to check that appropriate indication is retrieved in the MCR.
- Not impacted. Test signal will be used to inspect and record CET display data.
12 12 Other IITA Related ITAACs
- Not impacted. Factory Acceptance Testing is used following the guidance of NEI 08-01 Section 9.4 for as-built tests performed at other than the final installed location.
>> Plant parameters are simulated and adjusted to create applicable alert conditions, PMS outputs monitored, and confirmed that visual alerts were generated that identify challenges to critical safety functions
- ITAAC 565 (IITA Seismic and Equipment Qualification)
- As-built installation Acceptance Criteria will likely utilize NEI 08-01 section 9.5 to document inspections performed by the manufacturer prior to shipment to the plant site, where necessary and justifiable, since IITAs can not be installed in their final as-built location until core fuel load
>> Draft ICN will be provided to NRC when its available
13 13 Conclusions
- This approach is consistent with ITAAC 570, which was already submitted and accepted for Unit 3.
- SNC will likely use a similar approach for ITAAC 565 also.