Letter Sequence Approval |
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TAC:MF5092, Add Met Vs. Perform to Specification 1.4, Frequency (Approved, Closed) |
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MONTHYEARML14325A0072014-11-20020 November 2014 NRR E-mail Capture - Acceptance Review Regardin License Amendment Request for Surveillance Requirement 4.4.4.2 for Technical Specification 3/4.4.4, Reactor Coolant System Relief Valves. Project stage: Acceptance Review ML15240A1462015-08-28028 August 2015 NRR E-mail Capture - Millstone Power Station Unit 3, Supplement to License Amendment Request to Revise Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves (MF5092) Project stage: Other ML15225A0102015-08-28028 August 2015 Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves Project stage: Approval 2014-11-20
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Category:Letter
MONTHYEARML24240A1692024-09-18018 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) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24162A0882024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications 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 ML24141A1502024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2272024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 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 ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process 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 ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 2024-09-04
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24128A2772024-06-0404 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) 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) 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 ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23058A4542023-03-16016 March 2023 Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints ML23005A1702023-01-17017 January 2023 Correction to Issuance of Amendment No. 283 to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definition ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML22007A1512022-02-16016 February 2022 Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements ML21326A0992022-01-0707 January 2022 Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21262A0012021-11-0909 November 2021 Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate ML21227A0002021-10-0505 October 2021 Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident ML21222A2302021-09-0909 September 2021 Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227) ML21043A1622021-03-25025 March 2021 Issuance of Amendment No. 278 Regarding Revision to Battery Surveillance Requirements ML21026A1422021-02-23023 February 2021 Issuance of Amendment No. 342 Revision to Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML20161A0002020-07-15015 July 2020 Issuance of Amendment No. 276 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals 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 ML19340A0252020-01-30030 January 2020 Issuance of Amendment No. 337 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19150A3672019-05-30030 May 2019 Current Facility Operating License No. DPR-21, Tech Specs, Revised 5/30/2019 ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18246A0072018-09-25025 September 2018 Issuance of Amendment No. 335 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML18038B2002018-02-26026 February 2018 Issuance of Amendment Nos. 118, 334, and 271 to Revise Licensee'S Name (CAC Nos. MF9844, MF9845, and MF9848; EPID L-2017-LLA-0245 and EPID L-2017-LLA-0346) ML17025A2182017-01-24024 January 2017 Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis ML16308A4852016-12-22022 December 2016 Issuance of Amendment No. 331 Revision to Emergency Core Cooling System Technical Specification and Final Safety Analysis Report Ch. 14 to Remove Charging ML16249A0012016-09-30030 September 2016 Issuance of Amendments Small Break Loss of Coolant Accident Reanalysis ML16206A0012016-08-0404 August 2016 Issuance of Amendment No. 270 to Revise Technical Specification 5.6.3, Fuel Storage Capacity ML16193A0012016-07-28028 July 2016 Issuance of Amendments Removal of Severe Line Outage Detection from the Offsite Power System ML16131A7282016-07-28028 July 2016 Issuance of Amendment 268 Adopting Dominion Core Design and Safety Analysis Methods and Addressing the Issues Identified in Three Westinghouse Communication Documents ML16189A0762016-06-29029 June 2016 Supplement to Information Regarding License Amendment Request for Removal of Severe Line Outage Detection from the Offsite Power System ML16003A0082016-06-23023 June 2016 Issuance of Amendment No. 327 Proposed Technical Specification Changes for Spent Fuel Storage ML16068A3122016-03-31031 March 2016 Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing ML16011A4002016-01-29029 January 2016 Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15288A0042015-11-30030 November 2015 Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times ML15280A2422015-10-29029 October 2015 Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3 ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15225A0102015-08-28028 August 2015 Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15246A1422015-08-27027 August 2015 Connecticut, Inc. Millstone Power Station Unit 3 Supplement to License Amendment Request to Revise Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15225A0082015-08-26026 August 2015 Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML15187A3262015-07-29029 July 2015 Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C ML15187A1862015-07-28028 July 2015 Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692) ML15187A0112015-07-27027 July 2015 Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures ML15093A0022015-05-20020 May 2015 Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15098A0342015-05-20020 May 2015 Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A4412015-05-18018 May 2015 Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies ML14178A5992014-07-11011 July 2014 Issuance of Amendment Proposed Changes to Technical Specification 3/4 7.5, Ultimate Heat Sink (Tac MF1780) 2024-06-04
[Table view] Category:Safety Evaluation
MONTHYEARML24128A2772024-06-0404 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) 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) 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 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) 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 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23058A4542023-03-16016 March 2023 Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22201A5082022-07-28028 July 2022 Authorization and Safety Evaluation for Alternative Request No. IR-04-09 ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22039A3392022-03-0303 March 2022 Request for Alternative Frequency to Supplemental Valve Position Verification Testing Requirements in the Fourth 10-year Valve Inservice Testing Program ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML22007A1512022-02-16016 February 2022 Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements ML21326A0992022-01-0707 January 2022 Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21262A0012021-11-0909 November 2021 Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate ML21284A0062021-10-29029 October 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-04 and IR-4-02 ML21227A0002021-10-0505 October 2021 Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident ML21222A2302021-09-0909 September 2021 Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227) ML21174A0202021-08-0202 August 2021 Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML21167A3552021-07-16016 July 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-06 ML21167A2112021-06-30030 June 2021 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0081 Through L-2020-LLR-0088) ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML21043A1622021-03-25025 March 2021 Issuance of Amendment No. 278 Regarding Revision to Battery Surveillance Requirements ML21026A1422021-02-23023 February 2021 Issuance of Amendment No. 342 Revision to Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20312A0022020-12-10010 December 2020 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0027 Through L-2020-LLR-0032) ML20312A0012020-12-10010 December 2020 Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML20287A4712020-10-20020 October 2020 Proposed Alternative RR-05-05 to the Requirements of the ASME Code Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20252A0072020-09-15015 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 ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML20189A2062020-07-16016 July 2020 Relief Request IR-4-03 Concerning Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping ML20161A0002020-07-15015 July 2020 Issuance of Amendment No. 276 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals 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 ML20080K5082020-03-24024 March 2020 Alternative Request RR-05-03 for the Fifth 10-Year Inservice Inspection Interval ML19340A0252020-01-30030 January 2020 Issuance of Amendment No. 337 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19340A0012019-12-18018 December 2019 Proposed Alternative Request IR-4-01 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML19338G3722019-12-18018 December 2019 Alternative Requests RR-05-01 and RR-05-02 for the Fifth 10-Year Inservice Inspection Interval ML19340A0002019-12-13013 December 2019 Relief Request IR-3-39, Proposed Alternative to ASME Code Weld Preheat Requirements ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18290A6022018-11-13013 November 2018 Alternative Requests Related to the Fifth and Fourth 10-Year Interval Pump, Valve, and Snubber Inservice Testing Programs, Respectively (EPID L-2018-LLR- 0012 Through EPID L-2018-LLR-0022) ML18275A0122018-10-0404 October 2018 Alternative Request P-06 for the 'C' Charging Pump Test Frequency ML18246A0072018-09-25025 September 2018 Issuance of Amendment No. 335 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML18252A0032018-09-17017 September 2018 Alternative Requests RR-04-27 and IR-3-38 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography 2024-06-04
[Table view] Category:Technical Specifications
MONTHYEARML24128A2772024-06-0404 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) 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 ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21280A3282021-10-0707 October 2021 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program 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 ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels 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 ML17038A0062017-02-0101 February 2017 Technical Specifications 2016 Annual Report ML17025A2182017-01-24024 January 2017 Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis 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 ML16208A0512016-07-26026 July 2016 Clean Technical Specifications (TS) Pages for Millstone Power Station 1 (Docket No. 05000245), Administrative Changes for TS (L53121) ML16068A3122016-03-31031 March 2016 Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing ML16011A4002016-01-29029 January 2016 Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15288A0042015-11-30030 November 2015 Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times ML15280A2422015-10-29029 October 2015 Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3 ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15225A0102015-08-28028 August 2015 Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15225A0082015-08-26026 August 2015 Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML15187A3262015-07-29029 July 2015 Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C ML15187A1862015-07-28028 July 2015 Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692) ML15187A0112015-07-27027 July 2015 Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures ML15209A7292015-07-21021 July 2015 Response to Second Request for Additional Information Regarding Proposed Technical Specification Change for Spent Fuel Storage ML15098A0342015-05-20020 May 2015 Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A0022015-05-20020 May 2015 Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A4412015-05-18018 May 2015 Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies ML15044A0442015-02-0909 February 2015 Revised Response to Request for Additional Information Regarding License Amendment Request for Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures ML15021A1282015-01-15015 January 2015 Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14301A1122014-10-22022 October 2014 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML14154A0912014-05-28028 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. ML14073A0552014-04-0808 April 2014 Issuance of Amendment Calculated Containment Internal Pressure ML13346A7672013-12-18018 December 2013 Correction Letter to License Amendment Nos. 256 and 257 ML13155A1402013-05-28028 May 2013 Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage ML13133A0322013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink. ML13133A0332013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. ML12284A2132012-10-0404 October 2012 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML12250A6642012-08-28028 August 2012 Correction to Proposed Technical Specifications to Adopt TSTF-510 ML12220A0122012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12219A0732012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12202A0402012-07-17017 July 2012 License Amendment Request Regarding Removal of a License Condition, Proposed Technical Specifications Bases Change and FSAR Change for Ultimate Heat Sink Temperature Measurement ML12110A1142012-04-12012 April 2012 License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML12097A2002012-04-0202 April 2012 License Amendment Request to Revise Snubber Surveillance Requirements ML12032A2242012-01-25025 January 2012 License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3 ML11329A0032011-11-17017 November 2011 Proposed License Amendment and Exemption Request for Use of Optimized Zirlo Rod Cladding ML11193A2242011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 3 Through Attachment 6, Marked-up TS Pages and TS Bases Pages ML11193A2232011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 1 Through Attachment 3, Marked-up TS Page Changes 3/4 6-22 ML1102802082011-01-20020 January 2011 License Amendment Request to Revise Technical Specification (TS) 6.8.4.g, Steam Generator (SG) Program, and TS 6.9.1.7, Steam Generator Tube Inspection Report for Temporary Alternate Repair Criteria (H*) 2024-06-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David A Heacock President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 August 28, 2015
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 -ISSUANCE OF AMENDMENT RE: SURVEILLANCE REQUIREMENT 4.4.4.2, REACTOR COOLANT SYSTEM RELIEF VALVES (TAC NO. MF5092)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 264 to Renewed Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3. This amendment is in response to your application dated October 14, 2014, as supplemented by letter dated August 27, 2015. The amendment revises surveillance requirement (SR) 4.4.4.2 to remove the requirement to perform the surveillance for a pressurizer power-operated relief valve block valve that is being maintained closed in accordance with TS 3.4.4 Action a. A copy of the related Safety Evaluation is also enclosed.
Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-423
Enclosures:
- 1. Amendment No. 264 to NPF-49 2. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DOMINION NUCLEAR CONNECTICUT.
INC. DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 264 Renewed License No NPF-49 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Dominion Nuclear Connecticut, Inc. (DNC) dated October 14, 2014, as supplemented by letter dated August 27, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-49 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, revised through Amendment No. 264 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated into the license. DNC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date of issuance, and shall be implemented within 60 days of issuance.
Attachment:
Changes to the License and Technical Specifications Date of Issuance:
August 28, 2015 FOR THE NUCLEAR REGULATORY COMMISSION Benjamin Beasley, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ATTACHMENT TO LICENSE AMENDMENT NO. 264 RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. Remove 4 4 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. Remove 3/4 4-13 3/4 4-13 (2) Technical Specifications The Technical Specifications contained in Appendix A, revised through Amendment No. 264 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated into the license. DNC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) DNC shall not take any action that would cause Dominion Resources, Inc. (ORI) or its parent companies to void, cancel, or diminish DNC's Commitment to have sufficient funds available to fund an extended plant shutdown as represented in the application for approval of the transfer of the licenses for MPS Unit No. 3. (4) Immediately after the transfer of interests in MPS Unit No. 3 to DNC, the amount in the decommissioning trust fund for MPS Unit No. 3 must, with respect to the interest in MPS Unit No. 3, that DNC would then hold, be at a level no less than the formula amount under 10 CFR 50. 75. (5) The decommissioning trust agreement for MPS Unit No. 3 at the time the transfer of the unit to DNC is effected and thereafter is subject to the following: (a) The decommissioning trust agreement must be in a form
- acceptable to the NRC. (b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Dominion Resources, Inc. or its affiliates or subsidiaries, successors, or assigns are prohibited.
Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited. (c) The decommissioning trust agreement for MPS Unit No. 3 must provide that no disbursements or payments from the trust, other than for ordinary administrative expenses, shall be made by the trustee until the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC. (d) The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.
Renewed License No. NPF-49 Amendment No. 264 REACTOR COOLANT SYSTEM RELIEF VALVES SURVEILLANCE REQUIREMENTS 4.4.4. l In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE by: a. Performance of a CHANNEL CALIBRATION at the frequency specified in the Surveillance Frequency Control Program; and b. Operating the valve through one complete cycle of full travel during MODES 3 or 4 at the frequency specified in the Surveillance Frequency Control Program; and c. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV high pressurizer pressure actuation channels, but excluding valve operation, at the frequency specified in the Surveillance Frequency Control Program; and d. Verify the PORV high pressure automatic opening function is enabled at the frequency specified in the Surveillance Frequency Control Program. 4.4.4.2 Each block valve shall be demonstrated OPERABLE at the frequency specified in the Surveillance Frequency Control Program by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the ACTION requirements of Specification
3.4.4. MILLSTONE
-UNIT 3 3/4 4-13 Amendment No. 8-8, .f.3.3., +6+, U-9,+/-58 264 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 264 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT.
INC. DOCKET NO. 50-423 MILLSTONE POWER STATION. UNIT NO. 3
1.0 INTRODUCTION
By letter dated October 14, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14294A454), as supplemented by letter dated August 27, 2015 (ADAMS Accession No. ML 15240A146), Dominion Nuclear Connecticut, Inc. (DNC, the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC, the Commission) a license amendment request (LAR) for changes to the Millstone Power Station, Unit No. 3 (MPS3), Technical Specifications (TSs). The proposed amendment would revise surveillance requirement (SR) 4.4.4.2 to remove the requirement to perform the surveillance for a pressurizer power-operated relief valve (PORV) block valve that is being maintained closed in accordance with TS 3.4.4 Action a. Instead, the proposed amendment would revise SR 4.4.4.2 to expand the range of conditions under which testing of block valves specified in the Surveillance Frequency Control Program for the pressurizer PORVs would be unnecessary.
The supplemental letter dated August 27, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register (FR) on April 28, 2015 (80 FR 23601 ).
2.0 REGULATORY EVALUATION
In Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical specifications," the NRC established its regulatory requirements related to the content of TSs. Pursuant to 1 O CFR 50.36(c), TSs are required to include items in the following five specific categories related to station operation:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
Enclosure 2 In 10 CFR 50.36(c)(3), it states that, "surveillance requirements are requirements related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The MPS3 pressurizer PORV block valves are the subject of LCOs and SRs in TS 3/4.4.4, "Relief Valves." At the present time, the pressurizer PORV block valve test specified in SR 4.4.4.2, is required to be performed at the frequency specified in the Surveillance Frequency Control Program unless the pressurizer PORV block valve is closed for reasons other than excessive PORV seat leakage (i.e., Actions b. or c. of TS 3.4.4). The TS Task Force (TSTF) Traveler No. 284 (TSTF-284), Revision 3, provides guidance for the extension of the range of circumstances under which the quarterly testing of the pressurizer PORV block valve is not required in order to meet the Actions specified in TS 3.4.4. In response to the DNC LAR, the NRC staff considered whether this aspect of TSTF-284, Revision 3, may be applied to MPS3. The NRC staff also considered relevant information in the MPS3 Updated Final Safety Analysis Report (UFSAR) and TSs. In NUREG-1431, Revision 4, Standard Technical Specifications (STS) for Westinghouse Plants, and NUREG-1432, Revision 4, STS for Combustion Engineering Plants, licensees are excluded from performing the pressurizer PORV block valve surveillance specified in STS SR 3.4.11.1 when the block valve is closed in accordance with any of the actions of STS TS 3.4.11. In 10 CFR 50.46a, and as explained in NUREG-0737, it is required that each nuclear power reactor be provided with high point vents for the reactor coolant system, for the reactor vessel head, and for other systems required to maintain adequate core cooling if the accumulation of noncondensible gases would cause the loss of function of these systems. The criteria for acceptable venting systems include that high point vents must be remotely operated from the control room. The purpose of such systems is to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation.
3.0 TECHNICAL
EVALUATION
3.1 Background
The pressurizer PORVs are described in MPS3 UFSAR Section 5.4.13, "Safety and Relief Valves," and, among other things, they prevent actuation of the fixed reactor high pressure trip for all design transients up to and including the design step load decreases with steam dump and also limit the opening of the spring loaded pressurizer safety valves. The pressurizer PORVs also protect against an overpressurization event during low temperature operation.
1 The failure position of the pressurizer PORV is closed. The pressurizer is equipped with two PORVs, each of which has a block valve to be closed in the event that excessive PORV seat leakage is detected.
The pressurizer PORVs are not required to open in order to prevent the overpressurization of the RCS. The three pressurizer safety valves, by themselves, are sized to relieve enough steam to prevent an overpressurization of the RCS. Therefore, a loss of pressurizer PORV automatic control (or the closing of the associated block valves) and the subsequent failure of 1 See MPS3 UFSAR Section 5.2.2.11, "RCS Pressure Control during Low Temperature Operation." the PORVs to open will result in higher reactor coolant pressures, but will not cause any overpressurization event. The opening of the pressurizer PORV is a conservative assumption for the departure from nucleate boiling limited transients by tending to keep the primary system pressure down. As discussed in MPS3 UFSAR Section 5.4.7.2.3.5, "Safety Grade Cold Shutdown," depressurization to achieve cold shutdown would be accomplished by the pressurizer PORVs if pressurizer spray is unavailable or not effective.
However, as indicated in the LAR, not performing the surveillance on the block valve does not significantly reduce the assurance that the block valve is capable of opening to allow operation of the pressurizer PORV. The block valves have been demonstrated by operating experience to be reliable and are also subject to the motor-operated valve testing program. Consequently, the proposed amendment does not significantly reduce the confidence that the block valves can be opened in order to permit automatic or manual actuation of the pressurizer PORVs to depressurize the RCS. The current SR 4.4.4.2 requires that the pressurizer PORV block valves be subjected to an operability test, with a frequency as specified in the Surveillance Frequency Control Program, by operating each valve through one complete cycle of full travel unless (1) one block valve has been closed for reasons of PORV inoperability due to causes other than excessive seat leakage (i.e., ACTION b. of TS 3.4.4) or (2) both block valves have been closed for reasons of PORV inoperability due to causes other than excessive seat leakage (i.e., ACTION c. of TS 3.4.4). The licensee's proposed change to SR 4.4.4.2 would expand the range of conditions under which periodic operability testing of block valves for the pressurizer PORVs would be unnecessary to include any situation where a block valve is closed due to any Action in TS 3.4.4, which would include cases in which the pressurizer PORV block valve has been closed due to excessive seat leakage. As noted in Attachment 1 to the licensee's LAR, when a pressurizer PORV block valve has been closed due to excessive seat leakage, and the block valve is subsequently reopened, momentary opening of the PORV has been noted. This observed PORV behavior is consistent with the Westinghouse Bases for STS SR 3.4.11.1, in TSTF-284, Revision 3, which the licensee states in the LAR as: "Opening the block valve in this condition
[the block valve having been closed due to in inoperable PORV] increases the risk of an unisolable leak from the RCS since the PORV is already inoperable." Momentary opening of the pressurizer PORV could be a precursor to an unisolable leak in the RCS should the block valve fail to close. 3.2 Component Description As described in Attachment 1 to the LAR, MPS3 has two pressurizer PORVs. The pressurizer PORVs are solenoid-operated relief valves which are operated automatically or by remote manual control. The pressurizer PORVs and pressurizer steam bubble function to relieve RCS pressure during all design transients.
Operation of the pressurizer PORVs minimizes the undesirable opening of the spring-loaded pressurizer code safety valves. The pressurizer PORVs are also used for cold overpressure protection when any RCS cold leg temperature is at or below 226 degrees Fahrenheit
(°F). MPS3 TS 3.4.9.3, which applies to the use of the pressurizer PORVs for cold overpressure protection, would not be affected by the proposed change. Normally-open, motor-operated block valves are located between the pressurizer and the PORVs. Plant operators use the block valves to isolate the PORVs in case of excessive leakage or a stuck-open PORV. The block valves can be manually operated from the control room. A stuck-open pressurizer PORV is, in effect, a small break loss-of-coolant accident (SBLOCA).
As such, closing the block valve terminates the RCS depressurization and coolant inventory loss. The series arrangement of the PORVs and their block valves permits performing surveillances on the block valves during power operation.
The pressurizer PORVs, block valves, and associated controls are powered from vital buses that normally receive power from offsite power sources. They are also capable of being powered from emergency power sources in the event of a loss-of-offsite power. 3.3 Operability of Pressurizer PORV and Block Valves As presented by the licensee on pages 2 and 3 of 7 of Attachment 1 to the LAR, the operability of the pressurizer PORVs and block valves is determined on the basis of their capability to perform the following functions:
- 1. Control RCS pressure below the setting of the pressurizer code safety valves during an inadvertent emergency core cooling system (ECCS) or chemical and volume control system (CVCS) injection event or during a feed line break event. 2. Provide for RCS depressurization during safety grade cold shutdown.
- 3. Provide manual control of the block valve to: 1) isolate a stuck-open PORV, 2) isolate an inoperable PORV, 3) unblock a PORV, which was inoperable for excessive seat leakage, to allow the PORV to be used for control of RCS pressure and, 4) isolate a PORV in support of certain fire events. With one or both pressurizer PORVs inoperable, but able to automatically and manually open and close, either the PORV(s) must be restored, or the flow path(s) isolated within one hour. For this condition, the block valve(s) would be closed with power maintained to the associated block valve(s), since removal of power would render the block valve(s) inoperable.
Pressurizer PORV inoperability due to seat leakage does not prevent automatic or manual PORV use and does not create the possibility for a SBLOCA. For these reasons, the block valve may be closed; however, requiring power to be maintained to the valve allows quick access to the PORV for pressure control. Operation of the plant may continue with the pressurizer PORV(s) in this condition until the next refueling outage so that maintenance can be performed on the PORV(s) to address the degraded condition.
With one pressurizer PORV inoperable due to causes other than excessive seat leakage, it is necessary to either restore the PORV to operable status within the allowed outage time of one hour or isolate the flow path by closing and removing the power to the associated block valve. The pressurizer PORV must be restored to operable status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or cooldown to MODE 4 is required.
If more than one pressurizer PORV is inoperable due to causes other than excessive seat leakage, it is necessary to either restore at least one PORV within the allowed outage time of one hour or isolate the flow paths by closing and removing the power to the associated block valves and cooldown the RCS to MODE 4. Finally, the licensee notes that SR 4.4.4.2 has existed in the MPS3 TSs since their original issuance in January 1986. This SR was revised by MPS3 License Amendment No. 258, 2 which relocated its surveillance frequency to the Surveillance Frequency Control Program. 3.4 Licensee's Proposed Changes In Section 2 of Attachment 1 to the LAR, the licensee proposed to revise SR 4.4.4.2 to replace the specific exceptions to TS 3.4.4 Actions b or c with a statement that a pressurizer PORV block valve closed in accordance with any of the applicable actions of TS 3.4.4 would be excluded from the surveillance specified by SR 4.4.4.2. Specifically, the proposed change to the MPS3 SR 4.4.4.2 is as follows: (deleted text is in strike-through and added text is in italics and bold) Each block valve shall be demonstrated OPERABLE at the frequency specified in the Surveillance Frequency Control Program by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the ACTION requirements of ACTION b. or c. in Specification 3.4.4. A mark-up of the proposed TS page is provided in Attachment 2 to the LAR. Attachment 3 to the LAR contains a mark-up of the associated TS Bases, which are similar to the Westinghouse STS Bases for the block valve surveillance, and were provided by the licensee for information only. In a supplemental letter dated August 27, 2015, DNC submitted a correction to the Attachment 3 mark-up TS Bases. Specifically, the word "Operating" in the last sentence of the proposed TS Bases paragraph was changed to "Opening" which is consistent with the Westinghouse STS Bases for SR 3.4.11.1 in NUREG-1431.
In its supplement, the licensee provided a copy of the new TS Bases page with the revised wording for information only. 3.5 NRC Staff Evaluation of the Proposed Changes In reviewing the licensee's LAR, the NRC staff evaluated its consistency with TSTF-284, Revision 3, and the NUREG-1431, Revision 4, and NUREG-1432, Revision 4, STSs, as well as 2 See Amendment No. 258 issued February 25, 2014 (ADAMS Accession No. ML 14023A748). similar previously-approved LARs and their associated safety evaluations.
3 The NRC staff determined that the proposed change to the MPS3 pressurizer PORV block valve SR is consistent with the pressurizer PORV block valve SR contained in NUREG-1431, Revision 4, for Westinghouse plants, and NUREG-1432, Revision 4, for Combustion Engineering plants. The NRC staff also determined that the modified TS Bases section provided in Attachment 3 to the LAR is consistent with TSTF-284, Revision 3. The NRC staff considers the testing of the pressurizer PORV block valve to be unnecessary if the block valve has been closed due to an inoperable PORV. The additional assurance of block valve operability, gained from the surveillance test, is outweighed by the risk associated with the potential for an unisolable leak in the RCS. Accordingly, the NRC staff finds that the provision of TSTF-284, Revision 3, extending the range of circumstances under which the surveillance testing of the pressurizer PORV block valve is not required to any of the Actions closing the block valve, is acceptable.
Therefore, the NRC staff concludes that the licensee's request to remove the surveillance testing under the specific conditions of the revised PORV block valve SR 4.4.4.2 of TS 3/4.4.4 is acceptable.
3.6 Technical
Evaluation Conclusion The NRC staff has reviewed the licensee's proposed changes to TS 3/4.4.4, "Reactor Coolant System Relief Valves," for MPS3. The NRC staff concludes that the proposed changes are in accordance with the regulatory requirements listed in Section 2.0 of this safety evaluation and are consistent with supporting the current licensing basis.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified on August 3, 2015, of the proposed issuance of the amendment.
The State official had no comments.
5.0 ENVIRONMENTAL
CONSIDERATION The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes the SRs. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register (FR) on April 28, 2015 (80 FR 23601 ). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 1 O CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or 3 South Texas Project LAR dated September 30, 2004 (ML042800229) and subsequent Amendment No. 153 dated October 21, 2004 (ML042800363);
Millstone Power Station, Unit 2, LAR dated December 17, 2012(ML12362A012) and subsequent Amendment No. 314 dated March 26, 2013(ML13057A525). environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:
D. Palmrose Date: August 28, 2015 August 28, 2015 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 -ISSUANCE OF AMENDMENT RE: SURVEILLANCE REQUIREMENT 4.4.4.2, REACTOR COOLANT SYSTEM RELIEF VALVES (TAC NO. MF5092)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 264 to Renewed Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3. This amendment is in response to your application dated October 14, 2014, as supplemented by letter dated August 27, 2015. The amendment revises surveillance requirement (SR) 4.4.4.2 to remove the requirement to perform the surveillance for a pressurizer power-operated relief valve block valve that is being maintained closed in accordance with TS 3.4.4 Action a. A copy of the related Safety Evaluation is also enclosed.
Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-423
Enclosures:
Sincerely, IRA AChereskin For/ Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 1. Amendment No. 264 to NPF-49 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLl-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource ADAMS Accession No.: ML 15225A010 OFFICE NRR/DORL/LPLl-1
/PM NAME RGuzman DATE 8/13/15 OFFICE OGC NAME JWachutka DATE 8/17/15 RidsNrrDorllpl1-1 Resource RidsNrrDssStsb Resource RidsNrrLAKGoldstein Resource RidsNrrPMMillstone Resource RidsNrrDssSrxb Resource RidsRgn1 MailCenter Resource DPalmrose, NRR/DSS/SRXB RGrover, NRR/DSS/STSB
- SE memo dated June 17 2015 NRR/DORL/LPLl-1/LA NRR/DSS/SRXB/BC NRR/DSS/STSB/BC KGoldstein CJackson*
RElliott 8/14/15 6/17/15 8/25/15 NRR/DORL/LPLl-1
/BC NRR/DORL/LPLl-1
/PM BBeasley RGuzman (AChereskin for) 8/28/15 8/28/15 OFFICIAL RECORD COPY