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MONTHYEARLR-N13-0205, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity...2013-09-10010 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity... Project stage: Response to RAI 0CAN091301, Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi..2013-09-12012 September 2013 Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi.. Project stage: Response to RAI LR-N14-0051, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. Project stage: Response to RAI 0CAN031404, ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima2014-03-28028 March 2014 ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima Da Project stage: Response to RAI ML14092A4172014-03-31031 March 2014 Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1 Project stage: Request RS-14-065, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The..2014-03-31031 March 2014 Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The.. Project stage: Response to RAI LIC-14-0047, Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi2014-03-31031 March 2014 Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Project stage: Request ML14204A6202014-07-21021 July 2014 Response to Request for Additional Information Regarding Seismic Hazard and Screening Report for Seismic Recommendation 2.1 Project stage: Response to RAI ML14204A6192014-07-21021 July 2014 Response to March 12, 2012 Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 Project stage: Request NL-14-099, Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights.2014-08-18018 August 2014 Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights. Project stage: Request 0CAN081401, Response to Request for Additional Information (RAI) Associated with Near-Term Task Force (NTTF) Recommendation 2.1, Seismic Hazard and Screening Report2014-08-21021 August 2014 Response to Request for Additional Information (RAI) Associated with Near-Term Task Force (NTTF) Recommendation 2.1, Seismic Hazard and Screening Report Project stage: Response to RAI RS-14-206, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other PLA-7224, Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-72242014-08-28028 August 2014 Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-7224 Project stage: Request RS-14-230, Supplemental Information Related to the Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2, 1 of the Near-Term Task Force Review Of...2014-08-29029 August 2014 Supplemental Information Related to the Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2, 1 of the Near-Term Task Force Review Of... Project stage: Supplement LIC-14-0124, Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...2014-10-22022 October 2014 Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The... Project stage: Supplement LR-N14-0227, Seismic Hazard and Screening Report - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-10-30030 October 2014 Seismic Hazard and Screening Report - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Supplement 0CAN111401, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-11-0404 November 2014 Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Other NL-14-139, Additional Information Regarding the Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-11-0505 November 2014 Additional Information Regarding the Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request ML14310A0222014-11-13013 November 2014 Report Regarding Individual Plant Examination of External Events Supporting Information for Seismic Screening Project stage: Other ML14246A4282014-11-21021 November 2014 Screening and Prioritization Results Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident Based on Individual Plant Examination of External Events Project stage: Approval ML14310A0332014-12-15015 December 2014 NRC Response to Licensees Notification of Revised Regulatory Commitments Associated with Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Revie Project stage: RAI ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review Project stage: Other ML17123A3782016-04-27027 April 2016 Reevaluated Seismic Hazard Mitigating Strategies Assessment Report Project stage: Other ML16365A0322016-12-21021 December 2016 Response to March 12, 2012 Information Request, Spent Fuel Pool Seismic Evaluation for Recommendation 2.1 Project stage: Other 2014-03-28
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Category:Letter
MONTHYEARML24030A7522024-01-30030 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) 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) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 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 ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) 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. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 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 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 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[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 . 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. 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 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 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 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 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 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 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 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 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 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 ML20274A3462020-09-30030 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Battery Survillance Requirements ML20261H5982020-09-17017 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20252A1912020-09-0404 September 2020 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Deferral of the Millstone Unit 3 Steam Generator Inspections ML20209A5362020-07-27027 July 2020 Response to Request for Additional Information Regarding Relief Request IR-3-33 for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval ML20079K4242020-03-19019 March 2020 Response to Request for Additional Information for License and Request to Revise TS 3.8.1.1, A.C Sources - Operating, to Support Maintenance and Replacement of the Millstone Unit 3 'A' Reserve Station Service Transformer and 345 Kv South Bu ML20076C8332020-03-16016 March 2020 Response to Request for Additional Information (E-mail Dated 3/16/2020) Alternative Request IR-4-03 for Use of Alternative Non-Code Methodology ML20048A0192020-02-11011 February 2020 Response to Request for Additional Information for License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of a Reserve Station Service Transformer and 345 Kv South Bus. ML20042D9962020-02-10010 February 2020 Response to March 12, Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19284A3972019-10-0303 October 2019 Response to NRC Request for Additional Information on License Amendment Request to Adopt 10 CFR 50.69 ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19092A3322019-03-27027 March 2019 Response to Request for Additional Information for Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage ML19011A1112018-12-18018 December 2018 Supplement to the Flooding Hazard Reevaluation Report in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding ML18340A0282018-11-29029 November 2018 Response to Request for Additional Information for Proposed Technical Specifications Changes for Spent Fuel Pool Storage and New Fuel Storage ML18302A1202018-10-22022 October 2018 Response to Request for Additional Information for License Amendment Request to Revise the Technical Specification for Control Building Ventilation Inlet Instrumentation ML18235A3212018-08-17017 August 2018 Response to Request for Additional Information for Proposed Alternative Request P-06 for 'C' Charging Pump ML18225A0662018-08-0606 August 2018 Response to Request for Additional Information for Alternative Requests Associated with the In-Service Testing Program for Pumps, Valves, and Snubbers Fifth and Fourth 10-Year Interval Updates ML18205A1762018-07-19019 July 2018 Response to Request for Additional Information for Alternative Requests Associated with the In-Service Testing Program for Pumps, Valves, and Snubbers Fifth and Fourth 10-Year Interval Updates for Units 2 and 3 ML18170A0932018-06-14014 June 2018 Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML18151A4672018-05-24024 May 2018 Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test (Typed a) and Type C Test Intervals ML17338A0572017-11-22022 November 2017 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML17300A2202017-10-24024 October 2017 Response to Information Need Request Regarding Mitigating Strategies Assessment (MSA) Report for Flooding ML17053A1062017-02-16016 February 2017 Response to Request for Additional Information Regarding Proposed Alternative Requests RR-04-24 and IR-3-30 for Elimination of the Reactor Pressure Vessel Threads in Flange Examination ML17038A0052017-01-31031 January 2017 Response to RAI Regarding End of Cycle 23 and End of Cycle 17 Steam Generator Tube Inspection Reports, CAC MF8507 & MF8506 ML16365A0362016-12-22022 December 2016 Response to March 12, 2012 Information Request High Frequency Sensitive Equipment Functional Confirmation for Recommendation 2.1 ML16365A0322016-12-21021 December 2016 Response to March 12, 2012 Information Request, Spent Fuel Pool Seismic Evaluation for Recommendation 2.1 ML16321A4542016-11-10010 November 2016 Connecticut and Virginia Electric & Power Company Response to Request for Additional Information Revision 22 of Quality Assurance Program Description Topical Report ML16312A0642016-11-0101 November 2016 Units 1 & 2, Surry, Units 1 & 2, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML16294A2702016-10-18018 October 2016 Response to Request for Additional Information for License Amendment Request Regarding Realistic Large Break Loss of Coolant Accident Analysis - RAI Questions 1 Through 3 ML16291A5082016-10-12012 October 2016 Response to Follow Up Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML16202A0402016-07-14014 July 2016 Response to Request for Additional Information Regarding Spent Fuel Pool Heat Load Analysis License Amendment Request ML16188A1962016-06-30030 June 2016 NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations ML16182A0372016-06-27027 June 2016 Response to Request for Additional Information for License Amendment Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML16159A2382016-06-0101 June 2016 Isfsis, Response to NRC Request for Information Security Plan, Training and Qualification Plan, Safeguards Contingency Plan and ISFSIs Security Program, Rev. 21 ML16148A7012016-05-20020 May 2016 Response to Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval 2023-08-30
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Dominion Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com December 21, 2016 U.S. Nuclear Regulatory Commission Serial No.16-427 Attention: Document Control Desk NRA/DEA RO Washington, DC 20555 Docket Nos. 50-336/423 License Nos. DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 2 AND 3 RESPONSE TO MARCH 12, 2012 INFORMATION REQUEST SPENT FUEL POOL SEISMIC EVALUATION FOR RECOMMENDATION 2.1
References:
- 1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012 [ADAMS Accession Nos. ML12056A046 and ML12053A340].
- 2. NRC Letter, "Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated October 27, 2015 [ADAMS Accession No. ML15194A015].
- 3. EPRI Report 3002007148, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation, February 2016.
- 4. Dominion Nuclear Connecticut, Inc. Letter, "Millstone Power Station Units 2 and 3, Response to March 12, 2012 Information Request - Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1," dated March 31, 2014
[ADAMS Accession No. ML14092A417].
- 5. NRC Letter, "Millstone Power Station, Units 2 and 3 - Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF3968 and MF3969)," dated December 15, 2015 [ADAMS Accession No. ML15328A268].
- 6. EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, February 2013 [ADAMS Accession No. ML12333A170].
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1, Item (9), of Reference 1 requested each addressee to provide spent fuel pool (SFP) seismic evaluations. By letter dated October 27, 2015 (Reference
- 4 pl D
- Jt-f.-
Serial No.16-427 Docket Nos. 50-336/423 Page 2 of 3 2), the NRC transmitted final seismic information request tables, which identified that Millstone Units 2 and 3 were to conduct a limited scope seismic evaluation that included a SFP evaluation.
Electric Power Research Institute (EPRI) Report 3002007148, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation (Reference 3), provides criteria for evaluating the seismic adequacy of a SFP to the reevaluated ground motion response spectrum (GMRS) hazard levels. This report supplements the guidance provided in the Seismic Evaluation Guidance Screening, Prioritization and Implementation Details (SPID) (Reference 6) for plants where the GMRS peak spectral acceleration is less than or equal to 0.8g. Section 3.3 of EPRI Report 3002007148 lists the parameters to be verified to confirm the results of the report are applicable to Millstone Units 2 and 3 in order to conclude that the SFPs are seismically adequate in accordance with Near-Term Task Force (NTTF) Recommendation 2.1: Seismic evaluation criteria.
Attachments 1 and 2 provide data for Millstone Power Station Units 2 and 3, respectively, which confirm the applicability of the EPRI Report 3002007148 criteria and confirm that each unit's SFP is seismically adequate. The attachments also provide the information requested in response to Enclosure 1, Item (9) of Reference 1 for Millstone Units 2 and 3.
If you have any questions regarding this information, please contact Diane E. Aitken at (804) 273-2694.
Sincerely,
.\::>wW David A. Heacock President Dominion Nuclear COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by David A. Heacock, who is President Dominion Nuclear of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this ~I st day of J>u~r , 2016.
My Commission Expires: --'-12.=+\:3~1/c..::a-:.....0 CRAIG D SLY Notary Public Commonwealth of Virginia Reg.# 7518653 My Commission Expires December 31, 2~
Serial No.16-427 Docket Nos. 50-336/423 Page 3 of 3 Commitments made in this letter: No new regulatory commitments.
Attachments:
- 1. Spent Fuel Pool Data for Millstone Unit 2
- 2. Spent Fuel Pool Data for Millstone Unit 3 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Richard V. Guzman Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C 2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station 50.54f_Seismic.Resource@nrc.gov
Serial No.16-427 Docket No. 50-336 ATTACHMENT 1 SPENT FUEL POOL DATA FOR MILLSTONE UNIT 2 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No.16-427 Docket No. 50-336 Attachment 1 Page 2 of 4 Spent Fuel Pool Data for Millstone Unit 2 NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012 (Reference 1), Enclosure 1, Item (9), requested each addressee, for which the ground motion response spectrum (GMRS) exceeds the safe shutdown earthquake (SSE) in the 1 to 10 Hz frequency range, to provide a spent fuel pool (SFP) seismic evaluation in response to NTTF Recommendation 2.1: Seismic. Specifically, plants were requested to consider "all seismically induced failures that can lead to draining of the SFP."
EPRI Report 3002007148 (Reference 2) provides guidance for the limited scope SFP seismic evaluation. The Millstone Unit 2 SFP has been evaluated consistent with the guidance provided in Reference 2. The table below lists the criteria from Section 3.3 of Reference 2 along with data for Millstone Unit 2 that confirms applicability of the EPRI Report 3002007148 criteria. The table confirms that the SFP is seismically adequate and can retain adequate water inventory for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with NTTF 2.1 Seismic evaluation criteria.
References:
- 1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated March 12, 2012
- 2. EPRI Report 3002007148, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation, February 2016
- 3. Dominion Nuclear Connecticut, Inc. Letter, "Millstone Power Station Units 2 and 3, Response to March 12, 2012 Information Request - Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1," dated March 31, 2014
- 4. NRC Letter, "Millstone Power Station, Units 2 and 3 - Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF3968 and MF3969)," dated December 15, 2015
Serial No.16-427 Docket No. 50-336 Attachment 1 Page 3 of 4
- 1. The site-specific GMRS peak The GMRS peak spectral acceleration in the Seismic spectral acceleration at any Hazard and Screening Report (Reference 3), as frequency should be less than or accepted by the NRC in the Staff Assessment equal to 0.8g. (Reference 4), is 0.4217g, which is s 0.8g. Therefore, this criterion is met.
- 2. The structure housing the SFP The SFP is housed in the Auxiliary Building, which is should be designed using an SSE a seismic Category I structure designed to the SSE.
with a peak ground acceleration Reference 3, Table 3.1.1-1 gives a tabular version of (PGA) of at least 0.1 g. the design spectra. The Millstone Power Station Unit 2 SSE PGA is 0.17g, which is greater than 0.1g.
Therefore, this criterion is met.
- 3. The structural load path to the SFP The structural load path from the foundation to the should consist of some SFP consists of reinforced concrete in moment combination of reinforced concrete resistant frames and shear walls. The walls are shear wall elements, reinforced nominally 72 inches thick with #11 rebar spaced at 9 concrete frame elements, post- inches on center. The pool is 42 feet long by 25 feet tensioned concrete elements wide by 41 feet deep with a nominal level of 38 feet and/or structural steel frame of water. The bottom slab is 5 feet thick and elements. reinforcing is #14 rebar at 9 inches on center.
Therefore, the structural load path to the SFP consists of reinforced concrete elements and this criterion is met for Millstone Power Station Unit 2.
- 4. The SFP structure should be The Auxiliary Building, which contains the SFP, is included in the Civil Inspection included in the Condition Monitoring of Structures Program performed in accordance Program (Civil Inspection Program) performed in with Maintenance Rule.
accordance with 10 CFR 50.65, Maintenance Rule.
Inspections of the structure are intended to ensure long term functionality. Therefore, this criterion is met.
Serial No.16-427 Docket No. 50-336 Attachment 1 Page 4 of 4
- 5. To confirm applicability of the Piping attached to the SFP, which is part of the SFP piping evaluation in Section 3.2 of cooling system, is seismic Category I up to the first EPRI 3002007148, piping valve and is evaluated to the SSE. Therefore, this attached to the SFP up to the first criterion is met.
valve should have been evaluated for the SSE.
- 6. Anti-siphoning devices should be Passive anti-siphoning devices are installed on SFP installed on any piping that could piping that could lead to siphoning of the pool lead to siphoning water from the inventory.
SFP. In. addition, for any cases where active anti-siphoning Additionally, there are no anti-siphoning devices with devices are attached to 2-inch or extremely large extended operators attached to 2-smaller piping and have extremely inch or smaller piping.
large extended operators, the valves should be walked down to Therefore, this criterion is met.
confirm adequate lateral support.
- 7. To confirm applicability of the The SFP has a length of 42 feet, a width of 25 feet sloshing evaluation in Section 3.2 and a depth of 41 feet with a nominal water level of of EPRI 3002007148, the 38 feet. Therefore, this criterion is met.
maximum SFP horizontal dimension (length or width) should The Millstone Power Station GMRS maximum be less than 125ft, the SFP depth spectral acceleration in the frequency range equal to should be greater than 36ft, and or less than 0.3Hz is 0.02g (Reference 3, Table 2.4-the GMRS peak Sa should be < 1), which is less than 0.1 g. Therefore, this criterion is 0.1g at frequencies equal to or met.
less than 0.3Hz.
- 8. To confirm applicability of the The surface area of the SFP is 1050 ft2 , which is evaporation loss evaluation in greater than 500 ft2 . The licensed reactor core Section 3.2 of EPRI 3002007148, thermal power for Millstone Power Station Unit 2 is the SFP surface area should be 2700MWt, which is less than 4000MWt per unit.
greater than 500ft2 and the Therefore, these criteria are met.
licensed reactor core thermal power should be less than 4000MWt per unit.
Serial No.16-427 Docket No. 50-423 ATTACHMENT 2 SPENT FUEL POOL DATA FOR MILLSTONE UNIT 3 MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No.16-427 Docket No. 50-423 Attachment 2 Page 2 of 5 Spent Fuel Pool Data for Millstone Unit 3 NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review.of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012 (Reference 1), Enclosure 1, Item (9), requested each addressee, for which the ground 111otion response spectrum (GMRS) exceeds the safe shutdown earthquake (SSE) in the 1 to 10 Hz frequency range, to provide a spent fuel pool (SFP) seismic evaluation in response to NTTF Recommendation 2.1: Seismic. Specifically, plants were requested to consider "all seismically induced failures that can lead to draining of the SFP."
EPRI Report 3002007148 (Reference 2) provides guidance for the limited scope SFP.
seismic evaluation. The Millstone Unit 3 SFP has been evaluated consistent with the guidance provided in Reference 2. The table below lists the criteria from Section 3.3 of Reference 2 along with data for Millstone Unit 3 that confirms applicability of the EPRI Report 3002007148 criteria. The table confirms that the SFP is seismically adequate and can retain adequate water inventory for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with NTTF 2.1 Seismic evaluation criteria.
References:
- 1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated March 12, 2012
- 2. EPRI Report 3002007148, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation, February 2016
- 3. Dominion Nuclear Connecticut, Inc. Letter, "Millstone Power Station Units 2 and 3, Response to March 12, 2012 Information Request - Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1," dated March 31, 2014
- 4. NRC Letter, "Millstone Power Station, Units 2 and 3 - Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54{f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF3968 and MF3969)," dated December 15, 2015
Serial No.16-427 Docket No. 50-423 Attachment 2 Page 3 of 5
- 1. The site-specific GMRS peak The GMRS peak spectral acceleration in the Seismic spectral acceleration at any Hazard and Screening Report (Reference 3), as frequency should be less than or accepted by the NRC in the Staff Assessment equal to 0.8g. (Reference 4), is 0.4217g, which is ::;; 0.8g. Therefore, this criterion is met.
Structural* Parameters.
- 2. The structure housing the SFP The SFP is housed in the Fuel Building, which is a should be designed using an SSE Seismic Category I structure designed to the SSE.
with a peak ground acceleration Reference 3, Table 3.1.1-2 gives a tabular version of (PGA) of at least 0.1g. the design spectra. The Millstone Power Station Unit 3 SSE PGA is 0.17g, which is greater than 0.1g.
Therefore, this criterion is met.
- 3. The structural load path to the The structural load path from the foundation to the SFP should consist of some SFP consists of reinforced concrete in moment GOmbination of reinforced concrete resistant frames and shear walls. The pool walls are shear wall elements, reinforced nominally 72 inches thick with #11 rebar spaced at 12 concrete frame elements, post- inches on center. The pool is 'L' shaped with a tensioned concrete elements maximum length of 52 feet 6 inches and a maximum and/or structural steel frame width of 38 feet, and 41 feet 1 inch deep with a elements. nominal water level of 38 feet. The bottom slab is 8 feet thick and reinforcing is #11 rebar at 12 inches on center. Therefore, the structural load path to the SFP consists of reinforced concrete elements and this criterion is met.
- 4. The SFP structure should be The Fuel Building, which contains the SFP, is included included in the Civil Inspection in the Condition Monitoring of Structures Program Program performed in accordance (Civil Inspection Program) performed in accordance with Maintenance Rule. with 10 CFR 50.65, Maintenance Rule. Inspections of the structure are intended to ensure long term functionality. Therefore, this criterion is met.
Serial No.16-427 Docket No. 50-423 Attachment 2 Page 4 of 5
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- 5. To confirm applicability of the Piping attached to the SFP, which is part of the SFP piping evaluation in Section 3.2 of cooling and service water makeup systems, is seismic EPRI 3002007148, piping Category I up to the first valve and is evaluated to the attached to the SFP up to the first SSE. Therefore, this criterion is met.
valve should have been evaluated forthe SSE.
- 6. Anti-siphoning devices should be Passive anti-siphoning devices are installed on SFP installed on any piping that could piping that could lead, to siphoning of the pool lead to siphoning water from the inventory.
SFP. In addition, for any cases where active anti-siphoning Additionally, there are no anti-siphoning devices with devices are attached to 2-inch or extremely large extended operators attached to 2-inch smaller piping and have extremely or smaller piping.
large extended operators, the valves should be walked down to Therefore, this criterion is met.
confirm adequate lateral support.
- 7. To confirm applicability of the The SFP is 'L' shaped with a maximum length of 52 sloshing evaluation in Section 3.2 feet 6 inches, a maximum width of 38 feet, and a of EPRI 3002007148, the depth of 41 feet, with a nominal water level of 38 feet.
maximum SFP horizontal Therefore, this criterion is met.
dimension (length or width) should be less than 125ft, the SFP depth The Millstone Power Station GMRS maximum should be greater than 36ft, and spectral acceleration in the frequency range less than the GMRS peak Sa should be < or equal to 0.3Hz is 0.02g (Reference 3, Table 2.4-1),
0.1 g at frequencies equal to or which is less than 0.1 g. Therefore, this criterion is less than 0.3Hz. met.
Serial No.16-427 Docket No. 50-423 Attachment 2 Page 5 of 5
- 8. To confirm applicability of the The surface area of the SFP is approximately 1600 ft2, evaporation loss evaluation in which is greater than 500 ft2. The licensed reactor Section 3.2 of EPRI 3002007148, thermal power is 3650MWt, which is less than the SFP surface area should be 4000MWt per unit. Therefore, these criteria are met.
greater than 500ft2 and the licensed reactor core thermal power should be less than 4000MWt per unit.