Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Results
Other: ML21161A299, ML21203A314, ML21211A082, ML21214A178, ML21260A161, ML22013A339, ML22019A279, ML22061A056, ML22109A175, ML22164A861, ML22167A170, ML23188A020, ML23193A938, ML23200A183, ML23243A910
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MONTHYEARML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 Project stage: Meeting ML17310B2062017-11-20020 November 2017 Summary of September 20, 2017, Meeting with Florida Power & Light Company and NextEra Energy Regarding Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 Project stage: Meeting ML18136A9052018-05-31031 May 2018 Summary of April 25, 2017, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of Exemption Requests to Support Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 Project stage: Meeting L-20-162, Supplemental Response to NRC Generic Letter 2004-022020-11-30030 November 2020 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request 0CAN122001, Final Response to NRC Generic Letter 2004-022020-12-10010 December 2020 Final Response to NRC Generic Letter 2004-02 Project stage: Request ML21062A0642021-03-0202 March 2021 NRR E-mail Capture - Request for Additional Information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000) Project stage: RAI NL-21-0020, Final Supplemental Response to NRC Generic Letter 2004-022021-03-23023 March 2021 Final Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request DCL-21-034, Response to Request for Additional Information on Final Supplemental Response to Generic Letter 20042021-04-15015 April 2021 Response to Request for Additional Information on Final Supplemental Response to Generic Letter 2004 Project stage: Supplement ML21118A0072021-04-28028 April 2021 Final Response and Close-out to Generic Letter 2004-02 Project stage: Request PMNS20210610, Public Meeting Regarding Path Forward for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 22021-05-17017 May 2021 Public Meeting Regarding Path Forward for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 2 Project stage: Request ML21134A0232021-05-18018 May 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC (NextEra) Project stage: Request ML21147A1462021-05-27027 May 2021 Response to Request for Additional Information Regarding Generic Letter 2004-02 Project stage: Response to RAI ML21168A2612021-06-17017 June 2021 (Vcsns), Unit 1 - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors - Final Supplemental Response Project stage: Request ML21161A2992021-06-17017 June 2021 Summary of May 18, 2021 Public Webinar with Nextera Energy Point Beach, LLC Regarding Path Forward for Generic Letter 2004-02 Closure Project stage: Other ML21197A0372021-07-16016 July 2021 NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02 Project stage: RAI ML21203A3142021-07-29029 July 2021 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML21232A0402021-08-20020 August 2021 Notice of Teleconference with Entergy Operations, Inc. Concerning Final Response to Generic Letter 2004-02 at Arkansas Nuclear One, Units 1 and 2 Project stage: Meeting ML21252A3212021-08-20020 August 2021, 30 August 2021, 14 September 2021 ANO Meeting Summary for September 1, 2020 Public Meeting/Teleconference Project stage: Request ML21242A2792021-08-30030 August 2021 ANO Slides Presentation for 9-1-21 Public Meeting Project stage: Meeting ML21252A2662021-09-14014 September 2021 Summary of September 1, 2021, Teleconference Meeting with Entergy Operations, Inc. Concerning the Final Response to Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2 Project stage: Meeting ML21211A0822021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML21260A1612021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other RA-21-0230, Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2021-09-30030 September 2021 Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request 0CAN102101, Final Request for Additional Information Concerning Generic Letter 2004-022021-10-0404 October 2021 Final Request for Additional Information Concerning Generic Letter 2004-02 Project stage: Request ML21214A1782021-10-0808 October 2021 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other PMNS20211455, Pre-Submittal Public Meeting Regarding License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 22021-12-0303 December 2021 Pre-Submittal Public Meeting Regarding License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 2 Project stage: Meeting ML21336A7972021-12-0909 December 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC - December 9, 2021 (Slides) Project stage: Request ML22019A2792022-01-20020 January 2022 Summary of Public Webinar with NextEra Energy Point Beach, LLC Regarding Future License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Project stage: Other ML22019A2652022-01-27027 January 2022 Us NRC Staff Review of Documentation Provided by Firstenergy Nuclear Operating Co. for Beaver Valley, Units 1&2 Concerning Resolution of Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design B Project stage: Approval ML22013A3722022-01-27027 January 2022, 31 January 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML22013A3392022-01-31031 January 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22053A2402022-02-22022 February 2022 Final Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request ML22061A0562022-03-29029 March 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 Project stage: RAI ML22109A1752022-04-27027 April 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 Project stage: Supplement ML22164A8612022-06-24024 June 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) Project stage: Draft RAI ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 Project stage: RAI ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI Project stage: Request ML22335A4142022-12-21021 December 2022 Request for Withholding Information from Public Disclosure for Dominion Fleet Response to Request for Additional Information Regarding NRC Generic Letter 2004-02 Project stage: RAI ML23193A9382023-07-18018 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23200A1832023-08-0303 August 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML24012A0492024-01-11011 January 2024 Request for Additional Information Regarding Final Response to Generic Letter 2004-02 Project stage: RAI 2021-09-14
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Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 ML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML24032A4662024-01-16016 January 2024 Response to Comments on Draft Vpdes Permit No. VA0052451 ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24017A0802024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000338/2024301 and 05000339/2024301 ML24003A8502024-01-0909 January 2024 Letter to Wenonah Haire, Thpo, Catawba Indian Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8492024-01-0909 January 2024 Letter to W. Frank Adams, Chief, Upper Mattaponi Tribe Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML23332A7272024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8352024-01-0909 January 2024 Letter to Acee Watt, Thpo, United Keetoowah Band of Cherokee Indians in Oklahoma Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8362024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8372024-01-0909 January 2024 Letter to Elizabeth Toombs, Thpo, Cherokee Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8382024-01-0909 January 2024 Letter to G. Anne Richardson, Chief, Rappahannock Tribe, Inc., Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8392024-01-0909 January 2024 Letter to Gerald Stewart, Chief, Chickahominy Indian Tribe, Eastern Division Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8402024-01-0909 January 2024 Letter to Katelyn Lucas, Thpo, Delaware Nation, Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8412024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8422024-01-0909 January 2024 Letter to Paul Barton, Thpo, Eastern Shawnee Tribe of Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8482024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8432024-01-0909 January 2024 Letter to Robert Gray, Chief, Pamunkey Indian Tribe, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8442024-01-0909 January 2024 Letter to Russell Townsend, Thpo, Eastern Band of Cherokee Indians ML24003A8452024-01-0909 January 2024 Letter to Stephen Adkins, Chief, Chickahominy Indian Tribe, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8462024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8472024-01-0909 January 2024 Letter to Tom Jonathan, Chief, Tuscarora Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23332A0872024-01-0404 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23332A1852024-01-0404 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23360A6352024-01-0404 January 2024 Letter to Dominion Availability for North Anna Units 1 and 2 Draft Site Specific Environmental Impact Statement ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23332A1472023-12-21021 December 2023 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23346A0972023-12-11011 December 2023 License Amendment Request to Revise the Emergency Plan Relocation of the Technical Support Center - Response to NRC Request for Additional Information ML23346A1022023-12-11011 December 2023 2024 North Anna Power Station Brq Inspection Notification Letter 2024-02-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23318A1172023-11-13013 November 2023 NRR E-mail Capture - Formal Issuance of RAIs for North Anna Technical Support Center (TSC) License Amendment Request (LAR) (L-2023-LLA-0006) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23219A1602023-08-0707 August 2023 003 Radiation Safety Baseline Inspection Information Request ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23187A1122023-07-0606 July 2023 TSC Relocation LAR RAIs ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23081A5282023-04-26026 April 2023 Request for Additional Information - North Anna Subsequent License Renewal Application Environmental Review ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report ML23075A0232023-03-15015 March 2023 NRR E-mail Capture - RAI - License Amend Req (LAR) to Revise Tech Spec (Ts) 3.6.8 Limiting Condition for Operation to Remove Refueling Water Chemical Addition Tank and Replace the Containment Sump Buffer North Anna, 1 and 2 (L-2022-LLA-0162 ML23073A1802023-03-14014 March 2023 Notification of Commercial Grade Dedication Inspection (05000336/2023010 and 05000423/2023010) and Request for Information ML23068A0242023-03-0808 March 2023 RAI Issuance Fuel Handling Trolley LAR ML23060A0932023-03-0101 March 2023 NRR E-mail Capture - Formal Issuance of RAIs for Surry/North Anna Emergency Plans LAR ML23059A2282023-02-28028 February 2023 NRR E-mail Capture - Draft RAIs for Containment Buffer Change to Natb (L-2022-LLA-0162) ML23054A2412023-02-23023 February 2023 NRR E-mail Capture - Formal Issuance of RAIs for Surry Turbine Building Tornado Reclassification ML23046A1172023-02-0202 February 2023 002 Radiation Safety Baseline Inspection Information Request ML23018A1642023-01-17017 January 2023 Formal Issuance of RAIs for Surry ISI Alternative for SG Welds, 30 Day Calendar Response Period (Email) ML22349A2102022-12-15015 December 2022 Formal 43-day Request for Additional Information Issuance for Surry Turbine Building License Amendment Request ML22339A1582022-11-30030 November 2022 Requalification Inspection Notification Letter ML22258A2202022-09-13013 September 2022 FFD RFI ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML22223A1192022-08-14014 August 2022 RP Inspection Document Request Letter Final ML22110A2052022-04-19019 April 2022 Formal Issuance of RAIs for Post LOCA Buffer Change LAR ML22083A2102022-03-24024 March 2022 NRR E-mail Capture - Draft RAI - Relief Request N2-14-LMT-003 Fourth Ten Year Inservice Inspection Interval ML22067A1622022-03-0909 March 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22012A0572022-01-11011 January 2022 Issuance of RAIs for Surry Unit 1, Spring 2021 Steam Generator Tube Inspection ML21327A3652021-11-23023 November 2021 NRR E-mail Capture - Draft RAI for TSTF-577 LAR ML21322A0962021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21322A0992021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21256A0672021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21256A0692021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Request for Confirmation of Information ML21238A0942021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21238A0982021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21225A5022021-08-13013 August 2021 Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version ML21196A1012021-07-15015 July 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000280/2021011 and 05000281/2021011) and Request for Information (RFI) ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21188A1632021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21188A1652021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21182A2902021-07-0101 July 2021 7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements ML21174A1952021-06-23023 June 2021 Safety RAIs - Set Y - Draft - Enclosure ML21166A3512021-06-15015 June 2021 Safety RAIs - Set 4 - Draft ML21123A2972021-05-0303 May 2021 Final Request for Additional Information Set 3 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - E-mail ML21123A2982021-05-0303 May 2021 Final Request for Additional Information Set 3 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21112A3082021-04-22022 April 2021 Request for Additional Information (E-mail Dated 4/22/2021) License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML21105A1152021-04-15015 April 2021 Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA ML21102A3122021-04-12012 April 2021 NRR E-mail Capture - Surry, Units 1 & 2 - Final RAI for the LOCA AST LAR ML21091A0032021-04-0101 April 2021 Final Request for Additional Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure 1 - RAIs ML21091A0042021-04-0101 April 2021 SLRA Safety Review - Withdrawn Requests for Information (EPID No. L-2020-SLR-0000) - Enclosure 2 2023-09-14
[Table view] |
Text
September 9, 2022 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3, NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, AND SURRY POWER STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO RESPONSE TO GENERIC LETTER 2004-04 (EPID L-2017-LRC-0000)
Dear Mr. Stoddard:
By letters dated May 27, 2021 (Millstone 2), April 15, 2021 (Millstone 3), and February 25, 2021 (North Anna and Surry) (Agencywide Documents Access and Management System Accession Nos. ML21147A477 (Millstone 2), ML21105A433 (Millstone 3), ML21056A557 (North Anna),
and ML21056A541 (Surry)) Dominion Energy Nuclear Connecticut, Inc. and Virginia Electric and Power Company, the licensees, submitted supplemental responses Generic Letter(GL) 2004-02 to provide information regarding their evaluations of the effects of debris on long-term core cooling with respect to in-vessel effects.
The U. S. Nuclear Regulatory Commission (NRC) staff have reviewed the responses to GL 2004-02 and determined that additional information is required to complete the review. The additional information needed is enclosed with this letter. Following a discussion with your staff, a response is requested within 60 days.
D. Stoddard If you have any questions on this matter, I can be contacted at (301) 415-2481 or ed.miller@nrc.gov.
Sincerely,
/RA/
G. Edward Miller, Project Manager Plant Licensing Branch 2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336, 50-423, 50-338, 50-339, 50-280, and 50-281
Enclosure:
Request for Additional Information cc: Listserv
REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION MILLSTONE POWER STATION, UNITS 2 AND 3 NORTH ANNA POWER STATION, UNITS 1 AND 2 SURRY POWER STATION, UNITS 1 AND 2 DOMINION ENERGY CONNECTICUT, INC VIRGINIA ELECTRIC AND POWER COMPANY RESPONSE TO GENERIC LETTER 2004-02 DOCKET NOS. 50-336, 50-423, 50-338, 50-339, 50-280, AND 50-281 RAIs for Generic Letter 2004-02 Title 10 of the Code of Federal Regulations Part 50, Section 50.46 requires that plants maintain the ability to provide long-term core cooling following any initial loss-of-coolant accident (LOCA) response. To ensure that this cooling is available, licensees demonstrate that in-vessel fiber accumulation will not adversely affect the required function.
Millstone Power Station, Unit 2 (Millstone 2)
In its most recent supplemental response for U. S. Nuclear Regulatory Commission (NRC)
Generic Letter 2004-02, dated May 27, 2021 (ADAMS Accession No. ML21147A477), Dominion Energy Nuclear Connecticut, Inc. (Dominion Energy) provided information regarding the debris amounts used in the fiber penetration calculation for Millstone 2 and explained the methodology used to determine the amount of fiber that could penetrate the emergency core cooling system (ECCS) strainer. Regarding the basis for some of the assumptions used in the calculations, discuss the following aspects of the calculation, so that the NRC staff can understand how the in-vessel debris amounts were calculated:
- 1) The method for implementing the bed thickness correction was unclear. It seems that the Point Beach values would be directly applicable to Millstone 2 up to the tested thickness. Beyond the tested thickness, the model would have to be extrapolated to a higher debris load. With respect to extrapolation to higher debris loads, address the items below.
- a. Was the correction for bed thickness applied to the thickness that will occur at the Initial Sump Fiber Load amount or was it applied to the design basis load?
- b. Provide the characteristics of the fiber in the test compared to the characteristics of the fiber used to calculate the plant bed thickness for the penetration correction. Explain why any differences would not have to be accounted for in the correction factor, if applicable.
- c. Provide plots of penetrated debris vs. accumulated debris for the plant strainer.
On the plot, or separately, provide points (timing/bed thickness) at which the Enclosure
operating state of the ECCS and containment spray system (CSS) pumps change including swapover to recirculation, flow changes, and the end of injection from the refueling water storage tank (RWST).
- d. Confirm that the bed thickness is assumed to be zero at the time that ECCS pump suctions are realigned to the sump.
- e. Provide the assumptions used for flow rates, timing of flow rate changes, and other factors that could impact the calculation. Provide these for the various scenarios for which in-vessel fiber loads were calculated.
- f. What is the basis for the total fiber load of 5429 pounds (lb)? Was this value used to develop the bed thickness correction? If yes, what is the basis for using this value considering that lower amounts of fiber may transport for many scenarios, a more realistic erosion rate, and the debris generation and transport assumptions in the analysis? The fiber bed thickness is too small if only low-density fiberglass (LDFG) is considered. Did the thickness account for fiber densities other than LDFG? If so, justify this considering the test used only LDFG.
- i. This could result in a thinner bed and higher penetration at the time that ECCS is realigned to the sump.
- g. What does the initial sump fiber load of 660.15 lb. represent? How was it calculated? What is its relevance and how is it used in the in-vessel debris loading calculation? How were the debris generation and transport analyses for this value performed?
- h. How are the bed thickness correction values calculated for each time step?
- i. If only a single thickness correction is used, provide a justification considering that bed thickness changes as debris arrives at the strainer.
- 2) Verify that the list of references in the submittal is correct and ensure that the citations in the text are correct. For example, there is a reference to South Texas Project (STP) testing in the text, but no STP references in the list.
- 3) Confirm that the CSS operates for all scenarios throughout the period during which transport to the reactor is calculated. Are there scenarios where the spray flow would be zero, or less than the flow rate analyzed? If so, justify the flow rate used.
- 4) In the listed conservatisms it is stated that the designated sacrificial area was included to minimize the thickness. Confirm that this means that no sacrificial area was subtracted from the total strainer area for the penetration calculations.
- 5) The Millstone 2 evaluation described the acceptability of a minimum ECCS flow rate below the analyzed values. The condition was accepted based on the maximum flow case resulting in higher fiber loading. If the fiber mass for the high flow case remains significantly below the total in-vessel limit a more refined evaluation would not be required. However, if the fiber value approaches the limit a more refined analysis could be required. Provide the calculated fiber load for the high flow case.
- 6) Table 5 appears to contain an error for tblock. The value is listed as 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but the value for combustion engineering (CE) plants is 333 minutes or about 5.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Please confirm the correct value.
- 7) Provide the basis for the maximum ECCS flow rate of 4100 gpm [gallons per minute] in the last row in Table 5. Explain how this value was used to calculate the maximum in-vessel fiber load. Does the full 4100 gpm inject to the reactor vessel as implied by the 18.9 gpm per fuel assembly flow rate or is some of this CSS flow?
Millstone Power Station, Unit 3 (Millstone 3)
In its most recent supplemental response for NRC Generic Letter 2004-02, dated April 15, 2021 (ML21105A433), Dominion Energy provided information regarding the debris amounts used in the fiber penetration calculation for Millstone 3 and explained the methodology used to determine the amount of fiber that could penetrate the emergency core cooling system strainer.
Regarding the basis for some of the assumptions used in the calculations, discuss the following aspects of the calculation so that the NRC staff can understand how the in-vessel debris amounts were calculated:
- 1) The method for implementing the bed thickness correction was unclear. It seems that the Point Beach values corrected by Vogtle velocity data would be directly applicable to Millstone 3 up to the tested thickness. From that point on, the model would have to be extrapolated to a higher debris load. The items below should be considered.
- a. Was the correction for bed thickness applied to the thickness that will occur at the ECCS strainer (or the initial sump fiber load) amount or was it applied to the design basis load?
- b. Provide the characteristics of the fiber in the test compared to the characteristics of the fiber used to calculate the plant bed thickness for the penetration correction. Explain why any differences would not have to be accounted for in the correction factor, if applicable.
- c. Provide plots of penetrated debris vs. accumulated debris for the plant strainer.
On the plot or separately provide points (timing/bed thickness) at which the operating state of the recirculation spray system (RSS) changes including RSS swapover to recirculation, swapping ECCS pump suctions from the RWST to the RSS, RSS flow changes, and the end of injection from the RWST.
- d. Provide the bed thickness calculated at the time that ECCS pump suctions are realigned to the RSS.
- e. Provide the assumptions used for flow rates, timing of flow rate changes, and other factors that could impact the calculation. Provide these for each scenario for which in-vessel debris loads were calculated.
- f. What is the basis for the total fiber load of 2053 lb? Was this value used to develop the bed thickness correction? If yes, what is the basis for using this value considering that lower amounts of fiber may transport for many scenarios, a more realistic erosion rate, and the debris generation and transport assumptions in the analysis?
- i. This could result in a thinner bed and higher penetration at the time that ECCS is realigned to the sump/RSS.
- g. What is the basis for the ECCS fiber amount (initial sump fiber load) of 380.32 lb? How was it calculated? What is its relevance and how is it used in the in-vessel debris loading calculation? How were the debris generation and transport analyses for this value performed?
- h. How are the bed thickness correction values calculated for each time step?
- i. If only a single thickness correction is used, provide a justification considering that bed thickness changes as debris arrives at the strainer.
- 2) Verify that the list of references in the submittal is correct and ensure that the citations in the text are correct. In the text, near the bottom of page 16 of 30, reference 4.14 is to STP testing. For example, in the list of references, 4.14 is to WCAP-17788. References
4.4 through 4.10 are referred to as Point Beach and Vogtle testing near the top of page 17 of 30. This appears to be an error.
- 3) Confirm that containment RSS operates for all scenarios throughout the period during which debris transport to the reactor is calculated. Are there scenarios where the spray flow would be zero, or less than the 4071 gpm analyzed?
- 4) The Millstone 3 evaluation described the acceptability of a minimum ECCS flow rate below the analyzed values. The condition was accepted based on the maximum flow case resulting in higher fiber loading. If the fiber mass for the high flow case remains significantly below the total in-vessel limit a more refined evaluation would not be required. However, if the fiber value approaches the limit a more refined analysis could be required. Provide the fiber value calculated for the high flow case.
North Anna Power Station (North Anna), Units 1 and 2 In its most recent supplemental response for NRC Generic Letter 2004-02, dated February 25, 2021 (ML21056A557), Virginia Electric and Power Company provided information regarding the debris amounts used in the fiber penetration calculation for North Anna, Units 1 and 2 and explained the methodology used to determine the amount of fiber that could penetrate the emergency core cooling system (ECCS) strainer. Regarding the basis for some of the assumptions used in the calculations, discuss the following aspects of the calculation so that the NRC staff can understand how the in-vessel debris amounts were calculated:
- 1) The method for implementing the bed thickness correction is unclear. It seems that the Point Beach values corrected by Vogtle velocity data would be directly applicable to North Anna up to the tested thickness. From that point on, the model would have to be extrapolated to a higher debris load. However, it appears to the staff that the in-vessel loading was simply calculated by multiplying the fine fiber amount by the corrected penetration fraction and dividing by the number of fuel assemblies. This may be appropriate if the correction factor was calculated correctly. To clarify the appropriateness of using a correction factor in lieu of extrapolation:
- a. Was the correction for bed thickness applied to the thickness that will occur at the low head safety injection (LHSI) strainer or was it applied to the design basis load? Was it developed for the same load to which it was applied?
- b. Provide the characteristics of the fiber in the Point Beach test compared to the characteristics of the fiber used to calculate the plant bed thickness for the penetration correction. Explain why any differences would not have to be accounted for in the correction factor, if applicable.
- c. Provide the assumptions used for flow rates in the fiber load calculation.
- d. Provide the basis for the total fiber load of 909 lb loading. On which strainer(s) was this value used to develop the bed thickness correction? What is the basis for using this value considering that lower amounts or different sizes of fiber may transport for many scenarios?
- e. How is the initial sump fiber load of 219 lb used in the in-vessel debris loading calculation?
- f. How are the bed thickness correction values calculated for each time step?
- g. If only a single thickness correction is used, provide a justification considering that bed thickness changes as debris arrives at the strainer.
- 2) Verify that the list of references in the submittal is correct and ensure that the citations in the text are correct. In the text, near the bottom of page 16 of 30, reference 4.13 is to
STP testing. For example, in the list of references, 4.13 is to WCAP-17788. References 4.4 through 4.10 are referred to as Point Beach and Vogtle testing near the top of page 17 of 30. This appears to be an error.
- 3) Confirm that RSS spray operates for all scenarios throughout the period during which transport to the reactor is calculated. Are there scenarios where the spray flow would be zero as assumed in the analysis for conservatism? If spray is not in service more than 50 percent of the fiber could transport to the LHSI strainer.
Surry Power Station (Surry), Units 1 and 2 In its most recent supplemental response for NRC Generic Letter 2004-02, dated February 25, 2021 (ML21056A541), Virginia Electric and Power Company provided information regarding the debris amounts used in the fiber penetration calculation for Surry, Units 1 and 2 and explained the methodology used to determine the amount of fiber that could penetrate the ECCS strainer.
Regarding the assumptions used in the calculations, discuss the following aspects of the calculation so that the NRC staff can understand how the in-vessel debris amounts were calculated:
- 1) The method for implementing the bed thickness correction is unclear. It seems that the Point Beach values corrected by Vogtle velocity data would be directly applicable to Surry up to the tested thickness. From that point on, the model would have to be extrapolated to a higher debris load. However, it appears to the staff that the in-vessel loading was simply calculated by multiplying the fine fiber amount by the corrected penetration fraction and dividing by the number of fuel assemblies. This may be appropriate if the correction factor was calculated correctly. The items below should be considered as appropriate.
- a. Was the correction for bed thickness applied to the thickness that will occur at the LHSI strainer or was it applied to the design basis load? Was it developed for the load to which it is applied?
- b. Provide the characteristics of the fiber in the Point Beach test compared to the characteristics of the fiber used to calculate the plant bed thickness for the penetration correction. Explain why any differences would not have to be accounted for in the correction factor, if applicable.
- c. Provide the assumptions used for flow rates in the fiber load calculation.
- d. What does the total fiber load of 526.08 lb represent? Loading on which strainer(s)? Was this value used to develop the bed thickness correction? If yes, what is the basis for using this value considering that lower amounts or different sizes of fiber may transport for many scenarios, debris characteristics, and the debris generation and transport assumptions in the analysis?
- e. How is the initial sump fiber load of 56.98 lb. used in the in-vessel debris loading calculation?
- f. How are the bed thickness correction values calculated for each time step?
- g. If only a single thickness correction is used, provide a justification considering that bed thickness changes as debris arrives at the strainer.
- 2) Verify that the list of references in the submittal is correct and ensure that the citations in the text are correct. In the text, near the bottom of page 18 of 37, reference 4.15 is to STP testing. However, in the list of references, 4.15 appears to be a Surry calculation.
References 4.4 through 4.10 are referred to as Point Beach and Vogtle testing near the top of page 19 of 37. This appears to be an error.
- 3) Confirm that RSS spray operates for all scenarios throughout the period during which transport to the reactor is calculated. Are there scenarios where the spray flow would be zero as assumed in the analysis for conservatism? If spray is not in service more than 40 percent of the fiber could transport to the LHSI strainer.
The NRC staff also identified that it requires additional information regarding the assumption for the debris limit assumed for the fuel assemblies. Please respond to the following:
- 4) In the submittal dated February 25, 2021, the licensee states that Framatome expects the fiber limit for the AGORA-5A-I fuel product with the coarse mesh TRAPPER debris filter to lie between the debris limits for HTP [High Thermal Performance] fuel with FUELGUARD debris filter and the GAIA fuel with the GRIP debris filter as noted in Reference 4.11, Table 7-2. Explain why this limit would be expected to lie between the limits for the other two fuel debris filter designs or provide the relevant excerpt from Reference 4.11 that provides this information.
ML22251A129 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NRR/DORL/LPL2-1/BC MMarkley NAME GEMiller KGoldstein VCusumano (SDevlin-Gill for)
DATE 09/07/2022 09/09/2022 8/19/2022 09/09/2022