Letter Sequence Supplement |
---|
|
|
MONTHYEARML19023A4272019-01-17017 January 2019 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Request ML19234A1112019-08-14014 August 2019 License Amendment 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 Bus Switchyard Components Project stage: Request ML19277E8392019-09-26026 September 2019 E-mail from R.Guzman to S.Sinha - Draft Unacceptable with Opportunity to Supplement Requested Action: LAR to Revise TS 3.8.1.1, Extension of AOT Project stage: Draft Other ML19284A3972019-10-0303 October 2019 Response to NRC Request for Additional Information on License Amendment Request to Adopt 10 CFR 50.69 Project stage: Response to RAI ML19277B9082019-10-0707 October 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time Project stage: Acceptance Review ML19304A2942019-10-22022 October 2019 Supplement to Proposed License Amendment 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 Bus Switchyard Componen Project stage: Supplement ML19304B1542019-10-31031 October 2019 Acceptance Review Determination (E-mail 10/31/19) Extension of TS 3.8.1.1 Allowed Outage Time Project stage: Acceptance Review ML19361A0382019-12-23023 December 2019 12/23/19 E-mail from R.Guzman to S. Sinha - Draft Request for Additional Information Planned Audit of LAR to Revise TS 3.8.1.1 Project stage: Draft RAI ML20028C1952020-01-21021 January 2020 1/21/2020 E-mail from R.Guzman to S. Sinha Setup of Online Reference Portal for LAR to Revise TS 3.8.1.1 Project stage: Other ML20023D0372020-01-23023 January 2020 Request for Additional Information (E-mail Dated 1/23/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating Project stage: RAI 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. Project stage: Response to RAI ML20050F9212020-02-19019 February 2020 Request for Additional Information (E-mail Dated 2/19/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating Project stage: RAI 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 Project stage: Response to RAI ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components Project stage: Supplement ML20140A3692020-06-24024 June 2020 Issuance of Amendment No. 339 Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time Project stage: Approval 2019-09-26
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 2024-09-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis ML23123A2792023-05-0202 May 2023 License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits and Exemption Request for Use of M5 Cladding ML23013A2242023-01-13013 January 2023 Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure Temperature Limitation Figures ML22362A1022022-12-28028 December 2022 Proposed License Amendment Request to Supplement Spent Fuel Pool Criticality Safety Analysis ML22146A0272022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant. ML22096A2212022-04-0606 April 2022 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21053A3422021-02-22022 February 2021 Proposed License Amendment Request to Clarify Shutdown Bank Technical Specification Requirements and Add Alternative Control Rod Position Monitoring Requirements ML20343A2432020-12-0808 December 2020 Proposed License Amendment Request Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A, Revision 1 ML20343A2592020-12-0808 December 2020 Supplement to Proposed License Amendment Request to Revise the Millstone Unit 2 Technical Specifications for Steam Generator Frequency ML20324A7032020-11-19019 November 2020 Proposed License Amendment Request Measurement Uncertainty Recapture Power Uprate ML20310A3242020-11-0505 November 2020 Proposed License Amendment Request, Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) ML20282A5942020-10-0808 October 2020 Proposed License Amendment Request to Revise the Millstone Unit 2 Technical Specifications for Steam Generator Inspection Frequency ML20224A4572020-08-11011 August 2020 Connecticut. Inc. Millstone Power Station Unit 3, Proposed License Amendment Request for a One-Time Extension of the Millstone Unit 3 Steam Generator Inspections ML20121A2172020-04-30030 April 2020 Proposed Technical Specifications Change Battery Surveillance Requirements ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML20065K9762020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20063L8232020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML19353A0222019-12-17017 December 2019 License Amendment Request to Revise TS 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML19304A2942019-10-22022 October 2019 Supplement to Proposed License Amendment 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 Bus Switchyard Componen ML19217A2082019-07-30030 July 2019 Proposed License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML19109A1002019-04-11011 April 2019 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month. ML19023A4272019-01-17017 January 2019 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18128A0492018-05-0303 May 2018 License Amendment Request Regarding Proposed Technical Specifications Changes for Spent Fuel Storage and New Fuel Storage ML18100A0552018-04-0404 April 2018 License Amendment Request to Revise Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML17284A1792017-10-0404 October 2017 Proposed License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML17171A2322017-06-15015 June 2017 License Amendment Request to Revise the Company Name ML17018A0002017-02-0707 February 2017 Issuance of Amendment Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 ML16354A4242016-12-14014 December 2016 License Amendment Request to Revise Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 for the Remainder of Cycle 24 ML16159A2592016-09-0606 September 2016 Enclosure 1 Millstone Power Station, Unit No. 1 Issuance of Amendment Administrative Changes and Corrections to the Technical Specifications ML16153A0262016-05-25025 May 2016 Proposed License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis ML16153A0272016-05-25025 May 2016 ANP-3316(NP), Revision 0, Millstone, Unit 2, M5 Upgrade, Realistic Large Break Loca Analysis Licensing Report. ML16153A2342016-05-23023 May 2016 Supplement to License Amendment Request for Administrative Changes to the Permanently Defueled Technical Specifications ML16034A3582016-01-26026 January 2016 License Amendment Request, Spent Fuel Pool Heat Load Analysis ML16029A1682016-01-25025 January 2016 License Amendment Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML15246A1172015-08-31031 August 2015 Supplement to License Amendment Request to Revise TS 6.19, Containment Leakage Testing Program ML15246A1182015-08-31031 August 2015 License Amendment Request to Revise Technical Specification 5.6.3, Fuel Storage Capacity ML15246A1242015-08-27027 August 2015 Connecticut, Inc. Millstone Power Station Unit 2 Supplement to License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML15183A0222015-06-30030 June 2015 License Amendment Request for Removal of Severe Line Outage Detection from the Offsite Power System ML15134A2442015-05-0808 May 2015 License Amendment Request to Adopt Dominion Core Design and Safety Analysis Methods and to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev. 1, NSAL-15-1, and 06-IC-03 ML15065A3342015-02-26026 February 2015 Changes to Technical Specification Bases ML15021A1282015-01-15015 January 2015 Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14310A1872014-10-31031 October 2014 License Amendment Request to Revise the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML14301A1122014-10-22022 October 2014 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML14188B1892014-06-30030 June 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C. ML14133A0092014-05-0808 May 2014 License Amendment Request, Implementation and Engineered WCAP-15376, Reactor Trip System Instrumentation Test Times and Engineered Safety Feature Actuation System Instrumentation Test and Completion Times ML14093A0282014-03-28028 March 2014 License Amendment Request for Administrative Changes to the Permanently Defueled Technical Specifications ML14093A0262014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14093A0272014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14070A3462014-03-0606 March 2014 Changes to Technical Specification Bases 2023-09-26
[Table view] Category:Report
MONTHYEARML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 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 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 ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 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 ML22193A1432022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report 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 ML20352A3342020-12-17017 December 2020 Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19352B8982019-12-17017 December 2019 Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML19246A1162019-10-0707 October 2019 Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21) ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML19070A2172019-04-0303 April 2019 Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation ML19064A5902019-02-28028 February 2019 Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML18256A2002018-10-0303 October 2018 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (EPID L00495\05000336 L-2015-JLD-0011 and 00495\05000423\L-2015-JLD-0012) ML18247A2752018-06-18018 June 2018 Technical Requirements Manual ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 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 ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15253A2062015-09-0101 September 2015 ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report. ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML15078A2062015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-58 Through 2-125 ML15078A2082015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-172 Through the End ML15078A2072015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-126 Through 2-171 ML15078A2052015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 1 Through 2-57 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13357A3982014-01-24024 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Milestone Power Station, Unit 2, TAC No.: MF0858 ML14006A1592014-01-0808 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Millstone Power Station, Unit 3, TAC No.: MF0859 2024-06-10
[Table view] Category:Miscellaneous
MONTHYEARML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 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 ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report 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 ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 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 ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12362A3922012-11-30030 November 2012 Spent Fuel Pool Criticality Analysis with No Credit for Boraflex. ML12353A2422012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12187A1752012-06-25025 June 2012 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2010 and 2011, and Commitment Change Report for 2010 and 2011 ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review ML12046A8362012-01-31031 January 2012 Inservice Inspection Program - Owner'S Activity Report ML12031A1472012-01-25025 January 2012 Day Report for Emergency Core Cooling System Model Changes of 10 CFR 50.46 ML1116002202011-06-13013 June 2011 Exhibit D (Part 3): Millstone 2001 Safstor Cost Analysis (Normal Dollars) ML1028504382010-09-30030 September 2010 Attachments 2, 3, 5, 7, 8 & 9, to 10-579A, Westinghouse Electric Co. LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Revision 2, Dated Sep ML1019403352010-06-30030 June 2010 Units, 1, 2, 3, & ISFSI, 10 CFR 50.59, 10 CFR 72.48 Change Report for 2008 and 2009, and the Commitment Change Report for 2009 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1009702062010-03-29029 March 2010 Chemistry Procedure, Liquid Waste Sample Sink, Rev. 003-00 ML0931701762009-11-12012 November 2009 Part 3 of 4--Weld Overlay Examination Report 2R19 ML0931701732009-11-12012 November 2009 Part 2 of 4--Weld Overlay Examination Report 2R19 ML0931701662009-11-12012 November 2009 Part 1 of 4--Weld Overlay Examination Report 2R19 ML0931701852009-09-23023 September 2009 Part 4 of 4--Weld Overlay Examination Report 2R19 ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0913204602009-04-28028 April 2009 2008 Occupational Radiation Exposure Information ML0901303822008-12-26026 December 2008 Revision 002 to CP 3804L Procedure Action Request, Pass Containment Air Sample, Dated 12/26/2008 ML0830903962008-10-24024 October 2008 End of Cycle 18 Steam Generator Tube Inspection Report ML0827701132008-09-30030 September 2008 Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request ML0819800752008-07-0707 July 2008 Revision to Control Room and OSC Assembly Area Building 475 1st Floor, and SAP Locker ML0818406072008-07-0101 July 2008 Final Evaluation of Weld Overlay Examinations in Refueling Outage 18 ML0727504022007-09-27027 September 2007 Alternative Request RR-89-64 for Use of a Limited One-Sided Ultrasonic Examination Technique LBDCR 07-MP2-034 ML0720003902007-07-13013 July 2007 Attachment 1, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Descriptions, Technical Analysis and Regulatory Analysis for the Proposed Operating License and Technical Specifications Changes ML0715203992007-05-30030 May 2007 Fy 2007 Final Fee Rule Workpapers ML0713501882007-05-17017 May 2007 Review of Steam Generator Tube Inservice Inspection Report for the 2005 Refueling Outage at Millstone Power Station, Unit No. 2 ML0713502492007-05-0808 May 2007 Steam Generator Tube Plugging Report ML0708805652007-03-28028 March 2007 Response to Request for Additional Information Regarding an Alternative for the Weld Overlay of Pressurizer Nozzle Welds ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report 2023-07-26
[Table view] |
Text
Dominion Energy Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 ~ Dominion Dominion Energy.com ~ Energy April 14, 2020 U. S. Nuclear Regulatory Commission Serial No.20-109 Attention: Document Control Desk NRA/SS RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION ENERGY NUCLEAR CONNECTICUT, INC .
MILLSTONE POWER STATION UNIT 2 SUPPLEMENT TO LICENSE AMENDMENT REQUEST TO REVISE TS 3.8.1.1, "A.G. SOURCES OPERATING," TO SUPPORT MAINTENANCE AND REPLACEMENT OF THE MILLSTONE UNIT 3 'A' RESERVE STATION SERVICE TRANSFORMER AND 345 KV SOUTH BUS SWITCHYARD COMPONENTS By letter dated August 17, 2019 (ADAMS Accession No. ML19234A111) , and supplemented by letter dated
- October 22 , 2019 (ADAMS Accession No. ML19304A294), Dominion Energy Nuclear Connecticut, Inc. (DENC) submitted a license amendment request (LAR) to revise Millstone Power Station Unit 2 (MPS2)
Technical Specifications (TS). The LAR proposes to revise TS 3.8.1.1 , "AC . Sources -
Operating ," to add a new Required Action a.3 that provides an option to extend the allowed outage time (AOT) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 10 days for one inoperable offsite circuit.
The LAR also proposes a one-time allowance to the new proposed Required Action a.3 that extends the AOT to 35 days for one inoperable offsite circuit. This one-time allowance is needed for replacement of the Millstone Power Station Unit 3 (MPS3) 'A' reserve station service transformer, its associated equipment, and other 345 kV south bus switchyard components that are nearing the end of their dependable service life.
This supplement revises risk management action #6 in Attachment 4 of the October 22 ,
2019 LAR supplement, to clarify the scope of equipment that is applicable to this action . provides a description and assessment of the proposed changes . provides the updated TS markup . Attachment 3 provides the updated TS Bases insert pages (for information only) , to replace the corresponding pages previously submitted in the October 22 , 2019 LAR supplement. Attachment 4 provides an updated risk management action summary.
Pursuant to the provisions of 10 CFR 50.92 , the revised change proposed herein does not affect the conclusion of the Significant Hazards Consideration presented in the October 22, 2019 LAR supplement.
Serial No: 20-109 Docket No. 50-336 Page 2 of 3 Should you have any questions regarding this submittal, please contact Shayan Sinha at (804) 273-4687.
Sincerely, Mark D. Sartain Vice President- Nuclear Engineering & Fleet Support COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mark D. Sartain, who is Vice President - Nuclear Engineering and Fleet Support of Dominion Energy 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 statem~s in the docume~t are true to the best of his knowledge and belief.
Acknowledged before me this Ji_ day of Apn / ,2020.
My Commission Expires: 1:t)a(ch 31,, ZOZZ l
DIANE E. AITKEN Notary Public NOTARY PUBUCl REG. 17763111--
COMMONWEALTH OF v m -
WCOMMISSION EXPIRES MARCH 11.2022
Attachment:
- 1. Description and Assessment of Proposed Changes
- 2. Updated Mark-Up of Proposed Technical Specification Changes
- 3. Updated Mark-Up of Proposed Technical Specification Bases Insert Pages - For Information Only
- 4. Updated Risk Management Action Summary Commitments made in this letter: See Attachment 4
Serial No: 20-109 Docket No. 50-336 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No.20-109 Docket No. 50-336 ATTACHMENT 1 DESCRIPTION AND ASSESSMENT OF PROPOSED CHANGES DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
Serial No.20-109 Docket No. 50-336 Attachment 1, Page 1 of 3 1.0
SUMMARY
By letter dated August 17, 2019 (ADAMS Accession No. ML19234A111 ), and supplemented by letter dated October 22, 2019 (ADAMS Accession No. ML19304A294),
Dominion Energy Nuclear Connecticut, Inc. (DENG) submitted a license amendment request (LAR) to revise Millstone Power Station Unit 2 (MPS2) Technical Specifications (TS). The LAR proposes to revise TS 3.8.1.1, "A.G. Sources - Operating," to add a new Required Action a.3 that provides an option to extend the allowed outage time (AOT) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 10 days for one inoperable offsite circuit. The LAR also proposes a one-time allowance to the new proposed Required Action a.3 that extends the AOT to 35 days for one inoperable offsite circuit. This one-time allowance is needed for replacement of the Millstone Power Station Unit 3 (MPS3) 'A' reserve station service transformer (RSST), its associated equipment, and other 345 kV south bus switchyard components that are nearing the end of their dependable service life.
This supplement revises risk management action #6 in Attachment 4 of the October 22, 2019 LAR supplement, to clarify the scope of equipment that is applicable to this action.
2.0 DESCRIPTION
OF CHANGE DENG included eight risk management actions in Attachment 4 of the October 22, 2019 LAR supplement, which were also included in the TS Bases mark-up. Risk management action #6 is shown below:
"TS required systems, subsystems, trains, components, and devices that depend on the remaining power sources will be verified to be operable and positive measures will be provided to preclude subsequent testing or maintenance activities on these systems, subsystems, trains, components, and devices."
DENG proposes to revise this action as follows:
TS required systems, subsystems, trains, components, and devices that depend on the remaining pov'ler sources The Tier 2 equipment listed below will be verified to be operable OPERABLE/FUNCTIONAL, and positive measures will be provided to preclude subsequent testing or maintenance activities on these systems, subsystems, trains, components, and devices. this equipment (except for testing required to restore or maintain OPERABILITY/FUNCTIONALITY):
- MPS3 Diesel-driven Fire Water Pump Ml-7 (which is common to MPS2 andMPS3)
- MPS2 High Pressure Safety Injection (HPSI) Pumps P41A, P41B, P41C (and associated equipment)
Serial No.20-109 Docket No. 50-336 Attachment 1, Page 2 of 3 A clean version of the risk management action summary, including the updated risk management action #6, is provided in Attachment 4. Because the TS markup in the October 22, 2019 LAR supplement included a requirement stating that the risk management actions contained in DENG letter 19-282B, Attachment 4 remain in effect during the permanent 10-day and one-time 35-day AOTs, the TS mark-up also needed to be updated to modify the letter reference. A revised TS markup is provided in Attachment 2, which now cites Attachment 4 of this submittal letter for the updated list of risk management actions. It should be noted that the TS mark-up in Attachment 2 also includes TS changes from the RAI response in DENG letter 20-033, dated February 11, 2020 (ADAMS Accession No. ML20048A019). Attachment 3 provides the updated TS Bases insert pages (for information only) to replace the corresponding pages previously submitted in the October 22, 2019 LAR supplement.
3.0 TECHNICAL EVALUATION
OF CHANGE During development of the RAI response in DENG letter 20-070, dated March 19, 2020 (ADAMS Accession No. ML20079K424) DENG identified a conflict with the wording of risk management action #6 as it pertains to the MPS2 LAR. Risk management action #6 (from the October 22, 2019 LAR supplement) states:
"TS required systems, subsystems, trains, components, and devices that depend on the remaining power sources will be verified to be operable and positive measures will be provided to preclude subsequent testing or maintenance activities on these systems, subsystems, trains, components, and devices."
The MPS2 Limiting Condition for Operation (LCO) 3.8.1.1 requires two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system to be OPERABLE. It was determined that the underlined wording in risk management action #6 was not applicable to this MPS2 LAR, because the MPS electrical system design allows each individual offsite power source (of the three sources that can be credited in MPS2 TS LCO 3.8.1.1) to power both trains of plant equipment.
These design capabilities are detailed in Attachment 1, Section 3.3 of the October 22, 2019 LAR supplement. Also, as described in Attachment 1, Section 4.2.2 of the October 22, 2019 LAR supplement, two offsite power sources for MPS2 will be energized through two separate paths and available for use under the proposed maintenance configuration (though independence is lost at breaker 13T).
The October 22, 2019 LAR supplement identified a requirement to protect Tier 2 equipment during the permanent 10-day and one-time 35-day AOTs in Attachment 1, Section 4.4.1. This supplement revises the scope of risk management action #6 to focus on verifying the status of the Tier 2 equipment and providing positive measures to preclude testing and maintenance during the proposed TS Required Actions with extended AOTs.
Serial No.20-109 Docket No. 50-336 Attachment 1, Page 3 of 3 Additionally, one component in the Tier 2 list (MPS3 Diesel-driven Fire Water Pump M?-7, which is common to MPS2 and MPS3) has FUNCTIONALITY requirements provided in the MPS3 Technical Requirements Manual (TRM) 3.7.12.1 but does not have OPERABILITY requirements per any of the MPS2/3 TS LCOs. For this reason, the descriptor "TS" has been removed and references to "OPERABILITY" have been changed to "OPERABILITY/FUNCTIONALITY" in the updated risk management action
- 6. An allowance was also added to permit testing of the Tier 2 equipment for the purpose of restoring or maintaining equipment OPERABILITY or FUNCTIONALITY.
Pursuant to the provisions of 10 CFR 50.92, the revised change proposed herein does not affect the conclusion of the Significant Hazards Consideration presented in the October 22, 2019 LAR supplement.
Serial No.20-109 Docket No. 50-336 ATTACHMENT 2 UPDATED MARK-UP OF PROPOSED TECHNICAL SPECIFICATION CHANGES DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
Serial No.20-109 Docket No. 50-336 Attachment 2, Page 1 of 1 MMek 1e, ilQQe 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and
- b. Two separate and independent diesel generators each with a separate fuel oil supply tattle containing a minimum of 12,000 gallons of fuel.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Inoperable Equipment Required ACTION .f'
- a. One offsite a.I Perform Surveillance Requirement 4.8.1.1.1 for circuit remaining offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
(within 10 days* if Required AND ACTION e.3 is met) a.2 Restore the inoperable site circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the
,-----, following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
AND a.3 With MPS3 in MODE 5, 6, or defueled, the MPS3 'A' RSST inoperable, and the MPS3 'A' NSST energized with breaker 1SG-13T-2 (13T) and associated disconnect switches closed, restore either offsite circuit to OPERABLE status within 10 days* if the following requ irements are met :
- Within 30 days prior to enterin& the 10-<lay*AOT, the availability of the supplemental power sourc,, (MPS3 SBO diesel generator) shall be verified.
- During the 10-<lay*AoT, the availability of the supplementa l power source shall be checked once per shift . If the supplemental power sou rce becomes unavailable at anytime during the 10-day*AoT, restore to available status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN with in the follow ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- The risk management actions contained in DENC letter 20-109, Attachment 4 (also provided in TS Bases 3/4.8), shall remain in effect during the 10-<lay* AOT.
- To faci~ate replacement of the MPS3 'A' RSST and associated equipmen~ use of a one-lime 35-<lay aDowe<I outage time is permitted provided the requirements 01 Required ACTION a.3 are met. The W0<1< shal be completed no later than the end of MPS3 Retleling Outage 22 (fall 2023).
MILLSTONE - UNIT 2 3/4 8-1 Amendment No. # , m , m , :E+,
m,~,~
Serial No.20-109 Docket No. 50-336 Attachment 3, Page 1 of 2 MPS2 TS Bases Insert Required Action a.3 provides an option that can be entered for the configuration where the Millstone Unit 3 'A' RSST is inoperable and the Millstone Unit 3 'A' NSST is energized with breaker 15G-13T-2 closed. This option to extend 10-day AOT allows for performance of Millstone Unit 3 'A' RSST and/or 345 kV south bus switchyard component maintenance and repair activities in this configuration while Millstone Unit 2 is operating.
Required Action a.3 can only be entered if the availability of a supplemental power source, which is the Millstone Unit 3 SBO diesel generator, has been verified by testing within 30 days prior to entering the extended AOT. The verification testing is performed by bringing the Millstone Unit 3 SBO diesel generator to its rated voltage and frequency for more than 5 minutes and ensuring all its auxiliary support systems are available or operational. While in the Required Action, the availability of supplemental power source must also be checked once per shift. This check consists of administratively examining logs or other information to determine if the Millstone Unit No. 3 SBO diesel generator is out of service for maintenance or other reasons. The check also includes local visual observation of MPS3 SBO diesel generator once per shift, along with confirmation of correct switch configuration and indicated power availability once per day.
To provide additional defense-in-depth during the 10-day AOT, the following risk management actions are taken:
- 1. The AOT will be used no more than once every 18 month refueling interval for Unit 3 to perform maintenance on the Millstone Unit 3 'A' RSST and/or 345 kV south bus switchyard components.
- 2. The AOT will not be scheduled when adverse or inclement weather and/or unstable grid conditions are predicted or present.
- 3. The load dispatcher will be contacted once per day to ensure no significant grid perturbations are expected during the AOT.
- 4. Component testing or maintenance of safety systems and important non-safety equipment in the offsite power systems that can increase the likelihood of a plant trip will be avoided. No elective maintenance within the switchyard that could challenge offsite power availability will be scheduled, other than 345 kV south bus switchyard maintenance and repairs as permitted in action 5.
- 5. During concurrent maintenance and repair activities on 345 kV south bus switchyard components, 345 kV line 310 (Millstone to Manchester line) will be removed from service to prevent a loss of load trip of Unit 2 from a 310 line fault.
- 6. TS required systems, subsystems, trains, components, and devices that depend on the remaining power sources The Tier 2 equipment listed below will be verified to be operable OPERABLE/FUNCTIONAL, and positive measures will be provided to preclude subsequent testing or maintenance activities on tA-ese
Serial No.20-109 Docket No. 50-336 Attachment 3, Page 2 of 2 systems, subsystems, trains, components, and devices. this equipment (except for testing required to restore or maintain OPERABILITY/FUNCTIONALITY):
- Unit 3 Diesel-driven Fire Water Pump M7-7 (which is common to MPS2 andMPS3)
- Unit 2 High Pressure Safety Injection (HPSI) Pumps P41A, P41B 1 P41C (and associated equipment)
- 7. The Unit 2 turbine-driven auxiliary feedwater pump will be controlled as protected equipment.
- 8. The status of the Unit 2 EDGs will be monitored once per shift.
If the supplemental power source becomes unavailable at any time during the 10-day AOT, it shall be restored to available status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Opening breaker 13T and its associated disconnect switches results in exiting the Required ACTION with the 10-day AOT, because this would restore the Millstone Unit 3 'A' NSST to OPERABLE status as an offsite circuit.
To facilitate replacement of the Unit 3 'A' RSST and associated equipment, use of a one-time 35-day AOT is permitted provided the supplemental power source requirements of the Required ACTION for the 10-day AOT are met, and the related risk management actions are taken. The work shall be completed no later than the end of Unit 3 Refueling Outage 22 (fall 2023).
Serial No.20-109 Docket No. 50-336 ATTACHMENT 4 UPDATED RISK MANAGEMENT ACTION
SUMMARY
DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
Serial No.20-109 Docket No. 50-336 Attachment 4, Page 1 of 1 The AOT will be used no more than once every 18 month refueling During the time MPS3 'A' 1 interval for MPS3 to perform maintenance on the MPS3 'A1 RSST RSST is inoperable and and/or 345 kV south bus switchyard components. breaker 13T is closed.
During the time MPS3 'A' The AOT will not be scheduled when adverse or inclement weather 2 RSST is inoperable and and/or unstable grid conditions are predicted or present.
breaker 13T is closed.
During the time MPS3 'A' The load dispatcher will be contacted once per day to ensure no 3 RSST is inoperable and significant grid perturbations are expected during the AOT.
breaker 13T is closed.
Component testing or maintenance of safety systems and important non-safety equipment in the offsite power systems that During the time MPS3 'A' can increase the likelihood of a plant trip will be avoided. No 4 RSST is inoperable and elective maintenance within the switchyard that could challenge breaker 13T is closed.
offsite power availability will be scheduled, other than 345 kV south bus switchyard maintenance and repairs.
During concurrent maintenance and repair activities on 345 kV During the time MPS3 'A' south bus switchyard components, the 345 kV offsite line 310 will 5 RSST is inoperable and be removed from service, to prevent a loss of load trip of MPS2 breaker 13T is closed.
from a 310 line fault.
The Tier 2 equipment listed below will be verified to be OPERABLE/FUNCTIONAL, and positive measures will be provided to preclude subsequent testing or maintenance activities on this equipment (except for testing required to restore or maintain OPERABILITY/FUNCTIONALITY):
- MPS2 EDGs H7A, H7B During the time MPS3 'A' 6
- MPS3 Diesel-driven Fire Water Pump M7-7 (which is breaker 13T is closed.
common to MPS2 and MPS3)
- MPS2 High Pressure Safety Injection (HPSI) Pumps P41A, P41B, P41C (and associated equipment)
During the time MPS3 'A' The MPS2 turbine-driven auxiliary feedwater pump will be 7 RSST is inoperable and controlled as protected equipment.
breaker 13T is closed.
During the time MPS3 'A' 8 The status of the MPS2 EDGs will be verified once per shift. RSST is inoperable and breaker 13T is closed.