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Category:Legal-Affidavit
MONTHYEARML23361A0942023-12-21021 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 . ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22322A1822022-11-18018 November 2022 Proposed Emergency Plan Revision - Relocation of the Technical Support Center ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21264A5372021-09-20020 September 2021 Framatome, Inc. - Affidavit for Philip A. Opsal ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21264A5362021-09-10010 September 2021 Westinghouse Electric Company LLC - Affidavit for Camille T. Zozula ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21084A1822021-03-24024 March 2021 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information for the Safety Review - Set 1 ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20296A6232020-10-22022 October 2020 Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping ML20246G6972020-08-24024 August 2020 Application for Subsequent Renewed Operating Licenses ML20149K6942020-05-28028 May 2020 Response to Request for Additional Information, to Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident ML20149K6732020-05-28028 May 2020 PWR Owners Group, Affidavit of Zachary S. Harper ML20149K6742020-05-26026 May 2020 PWR Owners Group, Affidavit of Philip A. Opsal ML20087G3072020-03-19019 March 2020 ASME Section XI Inservice Inspection Program Proposed Inservice Inspection Alternative N1-I5-NDE-003 ML19343A0192019-12-0606 December 2019 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19267A0422019-09-16016 September 2019 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information Set 2 ML19253B3302019-09-0303 September 2019 Response to Requests for Additional Information - Sets 3 and 4 - Subsequent License Renewal Application ML19204A3572019-07-17017 July 2019 Subsequent License Renewal Application Response to Request for Additional Information - Set 2 ML19196A1092019-07-0909 July 2019 Stations, Units 1 and 2 - Proposed License Amendment Requests Re Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident (SBLOCA) Response to Request for Additional. ML19183A3862019-06-27027 June 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Set 1 ML19095A5972019-04-0202 April 2019 Submittal of Supplement to Subsequent License Renewal Application Change Notice 2 ML18291A8352018-10-15015 October 2018 Submittal of Application for Subsequent Renewed Operating Licenses ML18218A1702018-07-31031 July 2018 Proposed License Amendment Request Revision of Analytical Methodology Reference in Core Operating Limits Report for Small Break Loss of Coolant Accident ML18198A1182018-07-12012 July 2018 Transmittal of Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Small Break Loss of Coolant Accident (SBLOCA) ML18093B0762018-03-28028 March 2018 SME Section XI Inservice Inspection Program Request for Proposed Alternative N2-14-NDE-007 ML17251A8972017-08-24024 August 2017 Enclosure 3 to 17-296, Affidavit from Structural Group ML17251A8982017-08-16016 August 2017 Affidavit from Simpson Gumpertz & Heger, Inc ML17055C3602017-02-23023 February 2017 Submittal of Supplement to Proposed Alternative to ASME Section XI, Requirements for Repair/Replacement of Buried Circulating and Service Water Class 3 Piping with Carbon Fiber Reinforced Polymer ML17207A1742016-12-13013 December 2016 Enclosure 5: Affidavit of Westinghouse Electric Co, LLC ML17207A1732016-12-13013 December 2016 Enclosure 4: Affidavit of Electric Power Research Institute, Inc and Areva ML17207A1722016-11-18018 November 2016 Enclosure 3: Affidavit of Westinghouse Electric Co, LLC ML17207A1712016-10-31031 October 2016 Enclosure 2: Affidavit of Areva Np, Inc ML16175A6082016-06-15015 June 2016 Supplement to Proposed License Amendment Request on Realistic Large Break Loss of Coolant Accident Analysis ML15324A0442015-11-12012 November 2015 Request for Withholding Proprietary Information from Public Disclosure ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow ML13037A3012013-01-29029 January 2013 Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 1, Integrated Assessment Approach ML0814900872008-05-0808 May 2008 Proposal of License Amendment Request Interim Alternative Repair Criteria (Iarc) for Steam Generator (SG) Tube Repair ML0720002812007-07-13013 July 2007 License Amendment Request - Stretch Power Uprate - Supplemental Information ML0532900212005-10-19019 October 2005 Transmittal of Proprietary Information on Pressurizer Spray Nozzle Weld Overlay Design for Millstone Unit 3 ML0501100792005-01-0606 January 2005 Response to Request for Additional Information Re Reconciliation of Regulatory Requirements ML0501903172004-12-17017 December 2004 Virginia Electric and Power Company Surry Power Station Units 1 and 2 - Proposed Technical Specifications Change Request for Reactor Coolant System Pressure/Temperature Limits. Ltops Setpoint, and Ltops Enable Temperature with Exemption. ML0423302382004-08-0909 August 2004 Original Affidavit of Joseph J. Mangano, a Copy of Which Was Filed with the Connecticut Coalition Against Millstone Motion for Reconsideration and Request for Leave to Amend Petition ML0423300732004-08-0909 August 2004 Original Affidavit of Cynthia M. Besade, a Copy of Which Was Filed with the Connecticut Coalition Against Millstone'S Motion for Reconsideration and Request for Leave to Amend Petition ML0423302452004-08-0909 August 2004 Original Affidavit of Carol Ward, a Copy of Which Was Filed with the Connecticut Coalition Against Millstone Motion for Reconsideration and Request for Leave to Amend Petition ML0423302472004-08-0808 August 2004 Original Declaration of Ernest J. Sternglass, a Copy of Which Was Filed with the Connecticut Coalition Against Millstone Motion for Reconsideration and Request for Leave to Amend Petition ML0317700252003-06-20020 June 2003 Letter from David A. Repka to Administrative Judges Enclosing an Affidavit of William J. Eakin 2023-04-06
[Table view] 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:Response to Request for Additional Information (RAI)
MONTHYEARML23361A0942023-12-21021 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 . 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 ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23136A8832023-05-16016 May 2023 Responses to Request for Additional Information and Request for Confirmation of Information Regarding Environmental Review of Subsequent License Renewal Application L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23124A3642023-04-20020 April 2023 Response to Request for Additional Information for Spring 2022 Steam Generator Tube Inspection Report ML23103A2752023-04-13013 April 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request for Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer ML23096A1972023-04-0606 April 2023 License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure - Response to Request for Additional Information ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML23089A3542023-03-30030 March 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML23044A0392023-02-11011 February 2023 Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request for Additional Information ML23025A1252023-01-25025 January 2023 Response to Request for Additional Information License Amendment Request, NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML22343A0002022-12-0909 December 2022 Response to Request for RAI on ASME Operation & Maintenance Code Inservice Testing Program - Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date 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 ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information ML22115A1752022-04-25025 April 2022 ASME Section XI Inservice Inspection Program - Relief Request N2-14-LMT-004 - Fourth Interval Third Period Limited Examinations - Response to Request for Additional Information ML21350A4082021-12-16016 December 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Genera Tor Tube Inspections, Rev 1, Using the Consolidated Line-Item Improvement Process Response to RAI ML21341B4372021-12-0606 December 2021 (Naps), Units 1 and 2 - Subsequent License Renewal Application Responses to NRC Request for Additional Information Safety Review - Set 5 ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit ML21258A3542021-09-15015 September 2021 (Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Confirmation of Information Set 2 Safety Review ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21210A3962021-07-29029 July 2021 (Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 4 and Supplement 3 ML21209A7622021-07-26026 July 2021 Response to Request for Additional Information for Alternative Request V-01 - Proposed Request for Alternative Frequency to Supplemental Valve Positionn Verification Testing Requirements ML21153A4132021-06-0202 June 2021 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML21147A2932021-05-27027 May 2021 (Naps), Units 1 and 2 Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 3 and Administrative Change to SLRA Table A4.0-1, Item 25 ML21147A4772021-05-27027 May 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Final Supplemental Response ML21140A2992021-05-20020 May 2021 Response to Request for Additional Information for Proposed License Amendment Request to Add an Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21126A3152021-05-0606 May 2021 Proposed License Amendment Request to Battery Surveillance Requirements - Response to Request for Additional Information ML21119A2872021-04-29029 April 2021 (Naps), Unit 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 2 and Flow Accelerated Corrosion Program Enhancement Completion ML21105A4332021-04-15015 April 2021 Final Supplemental Response to NRC Genetic Letter 2004-02 on Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pressurized-Water Reactors ML21105A4822021-04-15015 April 2021 Response to Request for Additional Information for Proposed License Amendment Request to Revise the Millstone, Unit 2 Technical Specification for Steam Generator Inspection Frequency ML21098A2612021-04-0808 April 2021 Subsequent License Renewal Application, Response to Request for Additional Information Re Environmental Review ML21091A1872021-04-0101 April 2021 Response to NRC Request for Additional Information Regarding Safety Review - Set 1 & Clarification to Aging Management of Fire Protection System Lined Ductile Iron Valves ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21084A1822021-03-24024 March 2021 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information for the Safety Review - Set 1 ML21081A1362021-03-19019 March 2021 Response to Request for Additional Information for Alternative Request RR-05-06 - Inspection Interval Extension for Steam Generator Pressure-Retaining Welds and Full-Penetration Welded Nozzles ML21056A5572021-02-25025 February 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Final Supplemental Response ML21056A5412021-02-25025 February 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Final Supplemental Response ML21053A4332021-02-22022 February 2021 (Naps), Units 1 and 2 - Subssequent License Renewal Application (SLRA) Environmental Review - Response to NRC Request for Additional Information ML21042B9262021-02-11011 February 2021 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative Requests S1-I5-ISl-05 and S2-I5-ISl-06 - Response to Request for Additional Information ML21042B9042021-02-11011 February 2021 Subsequent License Renewal Application, Response to NRC Requests for Confirmation of Information for the Environmental Review ML22040A1012021-02-0909 February 2021 Response to Request for Additional Information 2021 Steam Generator Inservice Report 2023-08-07
[Table view] |
Text
PROPRIETARY INFORMATIONWITHHOLD UNDER10CFR2.390 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA23261 September 15,2021 U.S.Nuclear Regulatory Commission No. 21-042B Serial ATTN:Document Control Desk NRA/GDM RO Washington,D.C.20555 DocketNos. 50-336/423 50-338/339 50-280/281 Nos.DPR-65/NPF-49 License NPF-4/7 DPR-32/37 NORTHANNAANDSURRYPOWERSTATIONSUNITS 1AND2 MILLSTONE POWER STATIONUNITS2 AND3 REQUEST FORAPPROVAL OFAPPENDIX E OFFLEETREPORT DOM-NAF-2-A QUALIFICATION OFTHEFRAMATOME BWU-ICHFCORRELATION INTHE DOMINION ENERGY VIPRE-D COMPUTER CODE RESPONSE TOREQUEST FORADDITIONAL INFORMATION datedFebruary By letter 11,2021[Serial No.21-042 (ADAMS Accession No.
ML21042B321)), Dominion Energy Virginia andDENC(collectively,Dominion Energy)
Appendix"Qualification submitted E, oftheFramatome BWU-ICHFCorrelation in the Energy Dominion VIPRE-D Computer Code," Report toFleet DOM-NAF-2-A for NRCreview andapproval.Byletter dated August 13,2021, theNRCrequested additionalinformation tofacilitate theirreview. Dominion Energy's responsetotheNRCrequest isprovided in Attachment 1
Attachment 1 contains information proprietary toFramatome Inc.andissupported byan (Attachment affidavit 3) signed byFramatome, theowner oftheinformation.Theaffidavit forth sets the basis onwhich theinformation maybewithheld frompublic disclosure bythe Commissionandaddresses withspecificitytheconsiderations inparagraph listed (b)(4)of Section 2.390 oftheCommission's regulations. Accordingly,isrespectfully it requested theproprietaryinformation bewithheld frompublic inaccordance disclosure with 10CFR2.390. A redacted, non-proprietary responsetotheNRCrequest for additional isprovided information inAttachment 2.
Attachment1contains information thatisbeing withheldfrompublicdisclosure under 10CFR2.390. Uponseparation fromAttachment 1,thispageisdecontrolled.
Serial No.21-042B DocketNos.50-336/423/338/339/280/281/395 RAlResponse DOM-NAF-2, Appendix E Page2 of3 lf youhave questions orrequire information, additional please contactMr.Gary D.Miller at (804) 273-2771 Respectfully,
~-
p -
MarkD.Sartain Vice President -
Nuclear Engineeringand Fleet Support Commitments madeinthis letter:
None
Attachment:
Response toNRCRequest forAdditional Information 1 Response toNRCRequest forAdditional Information, Appendix E toFleet Report DOM-NAF-2, "QualificationoftheFramatome BWU-I CHFCorrelation inthe Dominion Energy VIPRE-D Computer Code." [PROPRIETARY) 2.Response toNRCRequest forAdditional Information, Appendix E to Fleet Report DOM-NAF-2, "QualificationoftheFramatome BWU-I CHFCorrelation in the Dominion Energy VIPRE-D Computer Code." [Non-Proprietary) 3.Framatome Affidavit Withholding for Proprietary Information from Public Disclosure
Serial No.21-0428 Nos.50-336/423/338/339/280/281/39 Docket RAlResponse Appendix DOM-NAF-2, E Page3 of3 cc:U.S. Nuclear Regulatory Commission -
RegionI 2100Renaissance Blvd, Suite100 Kingof Prussia, Pennsylvania 19406-2713 U.S.NuclearRegulatory Commission -
RegionII Marquis OneTower 245Peachtree Center Avenue, NE Suite 1200 Atlanta,Georgia 30303-1257 R.V.Guzman NRCSenior Project ManagerMillstone PowerStation U.S.Nuclear Regulatory Commission OneWhite Flint North, Mail Stop 08-C2 11555 Rockville Pike Rockville,Maryland 20852-2738 Mr.G.Edward Miller NRCSenior Project ManagerNorth AnnaPower Station U.S.Nuclear Regulatory Commission OneWhite Flint North, MailStop 09E-3 11555Rockville Pike Rockville,Maryland 20852-2738 Mr.J.J.Klos NRCProject ManagerSurry Power Station U.S.Nuclear Regulatory Commission OneWhite Flint Mail North, Stop 09E-3 11555 Rockville Pike Rockville, MD20852-2738 NRCSenior Resident Inspector MillstonePower Station NRCSenior Resident inspector NorthAnnaPower Station NRCSenior Resident Inspector SurryPower S tation
Serial No.21-042B DocketNos.50-336/423/338/339/280/281
[NonProprietary)
ATTACHMENT 2 M
Energy Dominion Nuclear (DENC)
Inc.
Connecticut, Millstone PowerStation 2and3 Units Virginia andPowerCompany Electric (DominionEnergyVirginia)
AnnaandSurry North PowerStations 1 and2 Units
SerialNo.21-042B Docket Nos.50-336/423/338/339/280/281 Attachment 2 Page1of12 RESPONSE TONRCREQ UESTFORADDITIONAL INFORMATION:
FRAMATOME BWU-I CHFCORRELATION INTHEDOMINION ENERGY VIPRE-D COMPUTER CODE" h
Byletter dated February11,2021 (Agencywide Documents Access andManagement System (ADAMS) Accession No. ML21042B321), as supplemented byletter dated May 13,2021(ADAMS AccessionNo ML21133A285), Dominion Energy requested ofAppendix approval E offleet report DOM-NAF-2, "QualificationoftheFramatome BWU-ICHF[Critical HeatFlux) Correlation in the Dominion Energy VIPRE-D Computer Code."Byletter datedAugust 13,2021, theNRC staff requested additional information tocompletetheir TheNRCrequest review. andDominion Energy's responses are provided below.
NRCRAl1 Please confirm thatDominion willusea process togenerate the predicted CHF[Critical Heat value Flux) thatisconsistent withthe process used w hendetermining thepredicted CHFvalue ofthe validationdata.
h:
Yes,Dominion Energyuses a process toqualify CHFcorrelations which isconsistent with theapproach usedby thevendor during thedevelopment ofthecorrelation as documented inSection4.9and4.10 ofReference 7.
NRCRAl- 2:
Please identifywhich fueltypes havebeenvalidated using theBWU-1 CHFmodel. For application topreviouslyunanalyzed fuel types, suchasAFAfuel, please demonstrate that thenumber ofdatapoints used forvalidation ofthat fueltypeissufficient for ensuring theaccuracy oftheDNBR[Departure from Nucleate BoilingRatio) limit.Specifically,
((
M 11
Serial No.21-042B Docket Nos.50-336/423/338/339/280/281 Attachment 2 Page2 of12 M:
Theresponse to this RAIisaddressed byseparating the requested informationinto three sections:
1 Please identify which fuel typeshave beenvalidated using the BWU-ICHFmodel.
Dominion Energy is not aware ofanyfuel designs that havebeenlicensed for reactor operations with the BWU-ICHF correlation; however, theBWUCritical HeatFluxCorrelations Topical Report (Reference 1, Section4.2) contains information on thefuelassemblies forwhich theBWU-ICHF correlation is applicable:
"Inthis report, then,theInconel mixingvanedesign correlation (BWU-I) isestablished asthe basic correlation for fuelassemblies with mixing vane grids.
Theenhanced mixing vane (BWU-correlation z) ispresently onlyvalid forthe Mark-BW17 design. Fuel assemblies with anyother type ofmixingvane spacer grid would require analysis with BWU-Iunless an enhancement could be demonstrated from CHFdata for that specific design."
Note that theterm "Inconel" isdescribed byFramatometo be a "convenient term foruseindescribing theoriginalmixing vaneconceptnot the material itself" (Reference 1,Section 4.2).
2.Forapplication topreviously unanalyzed fuel types, suchasAFA fuel, please demonstrate thatthe number ofdata points used for validation ofthatfuel type is sufficient for ensuring the accuracyofthe DNBR[Departure fromNucleate Boiling RatioJlimit.
Historically,thetesting anddevelopment ofolder CHFcorrelations hasconsisted ofa wide array ofgrid types, operating conditions, axialpower distributions,array sizes,andgrid spacings. Morerecently, CHFcorrelations tend tobedeveloped for specific fuel orgrid designs whichproduce moreaccurate DNBRs, leadingtolower DNBRlimits for thecorrelations which provide moremargin inDNBanalyses.
Forexample, theWestinghouse WRB-2CHFcorrelation wasdeveloped using testswith various heated lengths,axial power profiles, both unitandguide tube aswell cells, asdifferent mixing vanegrid designs (Reference 5,Section A.2.3).
Assuch, the WRB-2CHFcorrelation database contains a wide variety oftest data for17x17 nuclear fuel products.
Serial No.21-042B Docket Nos.50-336/423/338/339/280/281 Attachment 2 Page3 of12 Elaborating onthis example, theWRB-2MCHFcorrelation waslater introduced for fuel assemblies with theModified LowPressure Drop(LPD) mixing vanegrid andModified Intermediate FlowMixer (IFM) grid (Reference 6, Section 1).
Westinghouse conducted additional CHFtests withtheModified LPDandIFM grids. TheWRB-2M CHF correlation isa modification totheWRB-2 CHF correlation developed tooptimize the CHF predictionsto provide moreaccurate DNBpredictions, as it was determined during testing that WRB-2significantly underpredicted theCHF performance (Reference 6,Section 3.1). Thetests conducted forthedevelopment ofthe WRB-2M CHFcorrelation aredocumented inReference 6,Section 2.
Assuch, theWRB-2M CHFcorrelation is a morefine-tuned correlation than WRB-2 andisspecifically intended for more accurate DNBanalysis offuel assemblies with the Modified LPDandIFMgrid designs.
Westinghouse determined a minimum DNBR (95/95) limit of1.17 for theWRB-2 CHFcorrelation 5, Section (Reference A.2.3.4)and a limit of 1.14 for the WRB-2M CHF correlation (Reference 6,Section 3.4). The reduction inthelimit clearly demonstrates that theWRB-2MCHF correlation, which was correlated and optimized especially for those fuels with Modified LPD and IFMgrids, offers an improved predictive capabilityofthe thermal performancecompared totheWRB-2 CHFcorrelation. Reference 6,Section 1also statesthat the WRB-2 correlation DNBRlimit of1.17 maybeconservatively applied tofuels with the Modified LPD andIFMgrids; however, it wasdesired todevelop a correlation which willmore accurately predict DNBfor fuelswith Modified LPDandIFMgrids.
Similarly, Framatome hasestablished theBWU-ICHFcorrelation asthe basic correlation forfuel assemblies with mixing vanegrids (Reference 1,Section 4.2).
Thethermal-hydraulic testsupon which the BWU-I CHFcorrelation constants were developed (herein referred toas the BWU-I E xperimental Database), consider a widevariety oftest geometries suchas roddiameters, pinpitches, axial flux shapes, heated lengths, andmixing vanegrid spacings. As such,theBWU-I correlation isa generic correlation andtherefore applicable tothedifferent types offuel assemblies that arerepresented bytheconstituent test sections and approved bytheNRC(Reference 2).
Framatome hasdetermined a DNBRlimit of1.21 fortheBWU-ICHFcorrelation using LYNX2(Reference 1, Section 4.1). Dominion Energy's benchmark to LYNX2/BWU-I (Reference E.5.1) 3,Section using VIPRE-D/BWU-I (Experimental Database)ina DNBRlimit results of1.23.
Serial No.21-042B Docket Nos.50-336/423/338/339/280/281 Attachment 2 Page4 of12 Recall that Westinghouse stated that theWRB-2DNBRlimit (1.17) may be conservatively appliedtothose fuelassemblies with Modified LPDandIFMgrids.
Oncethe WRB-2M correlation wasoptimized forthese grid designs, the applicable DNBRlimitdecreased (1.14), thereby allowing moremargin for DNBanalyses. It isexpected that, should a CHFcorrelation bedeveloped solely upon the AFA-type mixing vaneandmid-span mixing grid data collected attheColumbia University Heat Transfer Research Facility (HTRF)1 (referred toasthe CUTests) theresulting 95/95 DNBRlimit would be lowerthanthat determined forVIPRE-D/BWU-I Combined Database inReference 3 (1.23). Inother words, applying theDNBR limit derived usingthegeneric VIPRE-D/BWU-I Combined Database is conservative.
TheBWU-ICHFcorrelation wasnotdeveloped using the CUTests. Asmentioned previously, theBWU-I CHFcorrelation is a generic correlation intended for fuel assemblies with mixing vanegrids. Therefore, a statistical analysis ofthetwodata sets (the BWU-ICHFcorrelation Experimental Database andtheCU Tests) is performed to determine ifthedataaresimilar enough to combine and conservatively apply one-sided tolerance theory for the determination ofa 95/95 DNBRlimit. Section E.5.2 ofReference 3documents this statistical analysis ofthe VIPRE-D/BWU-I Experimental Database andtheCUTests, which demonstrates that the twodata groups areofsimilar populations andtherefore may becombined forfurther analysis. This total database isreferred toasthe VIPRE-D/BWU-I Combined Database. TheDNBRlimits for both the VIPRE-D/BWU-I Experimental andCombined Databases weredetermined tobe1.23. Additionally, the CHF results ofthe twodatabases areindistinguishable inFigures E.5.2-1 through E.5.2-4 ofReference 3,demonstrating that theBWU-ICHFcorrelation accurately predicts CHFfor assemblies which employ AFA-type mixing vaneandmid-span mixing grids.
Insummary, thehistorical experience ofgeneric versus optimized correlations, the generic applicability oftheBWU-ICHF correlation toa widevariety offuel assembly configurations, theextensive history oftheColumbia HTRFwith the development of NRC-approved CHF correlations, and theresults of the aforementioned statisticalandvisual analysis provide confidence that theDNBR limits for theVIPRE-D/BWU-I code/correlation pair documented inReference 3 provide adequate protection at a 95/95 confidence level. Therefore, thelimit of 1 TheColumbia HTRFhasanextensive history withthetesting anddevelopment ofvarious NRC-approved CHFcorrelations, such astheFramatome BWU-zandthe Westinghouse WRB-2M CHFcorrelations.
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Page5 of12 1.23 as documented inReference forapplication 3 isconservative tofuel assemblies withAFA-typemixing vaneandmid-span mixing grids.
3.Specifically, ((
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Attachment Page6 of12 RAl2-1 Figure M
FIGURE REDACTED RAI2-2:
Figure M
FIGURE REDACTED
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Serial No.21-042B Docket Nos.50-336/423/338/339/280/281 Attachment 2 Page8of12 As noted intheRAl, MassVelocity Dominion Energy analyses using the thermal-hydraulic VIPRE-Dcodearenot conducted at Thermal-hydraulic analyses performed inVIPRE-D are conducted atconservative initial flow conditions.
Forexample,theminimum measured flowrate usedin VIPRE-D for PowerStation Surry forcurrent andintended future operation is 273,000 gpm,whichtranslates toapproximately 2.37MIbm/hr-ft2. Similarly, for North AnnaPower theminimum Station, measured flow rateis 295,000 gpm, which translates 2.51MIbm/hr-ft2.
toapproximately ForMillstone Unit 3,the minimum measuredflow is379,200 rate gpm,which translates toapproximately 2.55Mlbm/hr-ft2 Assuch, theflow usedinVIPRE-D rates analyses shallM AsDominion Energy thermal-hydraulic analyses donotutilize M theBWU-ICHFcorrelation M
Ibeanody.namic.Quality
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FromFigures RAI 2-3and2-4,it appearsthat by very conservativepoints inthetests These considered. conservativepoints have M
Points with (Figure RAI2-3) areM andappear tobe Assuch, Similarly, points M with M (FigureRAl2-4)are andappear tobe Thesepoints M Figures RAl2-5and2-6areidenticalto Figures RAl2-3and2-4,respectively,
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Serial No.21-042B DocketNos.50-336/423/338/339/280/281 ATTACHMENT 3 FramatomeAffidavit:
DominionEnergyNuclear Connecticut, (DENC)
Inc.
PowerStation Milistone Units2and3 Virginia andPowerCompany(Dominion Electric EnergyVirginia)
NorthAnnaandSurry PowerStations 1 and2 Units
Serial No.21-042B Docket Nos.50-336/423/338/339/280/28 Attachment 3
Page 3 1of A F FIDA V IT
- 1. Myname isGayle Elliott. IamDeputy Director, Licensing andRegulatory for Affairs,Framatome Inc.(Framatome) andassuch Iamauthorized toexecute this Affidavit.
- 2. Iamfamiliar with the criteria applied byFramatome todetermine whether certain Framatomeinformationisproprietary. Iamfamiliar withthepolicies established by Framatome theproper toensure application of these criteria.
- 3. Iamfamiliar with theFramatome information contained inAttachment 1, "Response toNRCRequest for Additional Information: Appendix E toFleet Report DOM-NAF-2-A,'Qualification oftheFramatome BWU-I CHFCorrelation intheDominion Energy VIPRE-DComputer Code'," ofa Letter fromMr.MarkSartain(Virginia ElectricandPower Company) toDocument Control Desk (NRC), Serial No.21-042B, Docket Nos. 50-336/423, 50-338/339, dated 50-280/281, September 13, 2021 andreferred herein as "Document."
Information contained inthisDocument hasbeen classified byFramatome asproprietary in with accordance thepolicies established byFramatome for thecontrolandprotection of andconfidential proprietary information.
- 4. ThisDocument contains information ofa proprietaryandconfidential nature andisofthetypecustomarily held inconfidence byFramatome andnotmadeavailable tothe public.
Based onmyexperience, Iamaware that other companies regard information ofthe kind containedinthis Document asproprietary andconfidential.
- 5. ThisDocument hasbeen madeavailable totheU.S. Nuclear Regulatory Commissioninconfidence with therequest that the information contained inthis Document be withheld from disclosure.
public Therequest for withholding ofproprietary information ismadein accordance with10CFR2.390. Theinformation for which withholdingfrom disclosure is
Serial No.21-042B Docket Nos.50-33614231338/339/280/28 Attachment 3 Page2 of3 requested qualifies under 10CFR2.390(a)(4) "Trade secrets andcommercial orfinancial information."
- 6. The following criteria arecustomarily applied byFramatome todetermine whether informationshould beclassifiedasproprietary:
(a)The information revealsdetails ofFramatome's research anddevelopment plans andprograms ortheir results.
(b) Useoftheinformation byacompetitor would permit thecompetitor to significantly reduce itsexpenditures, intime orresources, todesign, produce, ormarket a similarproduct or service.
(c)Theinformation includes test data or analytical techniques concerning a process, methodology, orcomponent,the application ofwhich results ina competitive advantage for Framatome.
(d) Theinformation reveals certain distinguishing aspects ofa process, methodology, orcomponent, the exclusive useofwhich provides a competitive advantage for Framatome inproduct optimization or marketability.
(e)Theinformation isvitaltoacompetitive advantage heldby Framatome, would behelpful tocompetitors toFramatome, andwould likely cause substantial harm tothe competitiveposition ofFramatome.
Theinformation inthisDocument isconsidered proprietary for the reasons set forth in paragraphs 6(d) and6(e) above.
- 7. Inaccordance with Framatome's policies governing theprotection andcontrol ofinformation, proprietary information contained inthis Document hasbeen madeavailable, on a limited basis, toothers outside Framatome only asrequired andunder suitable agreement providing for nondisclosure andlimited useofthe information.
- 8. Framatome policyrequiresthat proprietary information bekept ina secured fileorarea anddistributed ona need-to-know basis.
Serial No.21-042B Docket Nos.50-336/423/338/339/280/28 Attachment 3
Page3of3
- 9. Theforegoing aretrue statements andcorrect tothebestofmyknowledge, information, and belief.
Ideclare under penalty ofperjury the that foregoing istrue andcorrect.
Executed on:September 13,2021 signed Digitally byELUOTT ELLIOTTGayle cavieDate: -04'00' 11:29:11 2021.09.13 Gayle Elliott