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MONTHYEARML24086A4802024-03-22022 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 Project stage: Request 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 Project stage: Request ML24115A2622024-04-24024 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-14 Regarding Pressurizer and Steam Generator Pressure-Retaining Welds and Full-Penetration Welded Nozzles Project stage: Acceptance Review 2024-03-22
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Category:Letter
MONTHYEARML24289A0152024-10-21021 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) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (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) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 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 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 IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 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:Technical Specification
MONTHYEARML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement 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 ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22096A2212022-04-0606 April 2022 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML22032A2702022-01-28028 January 2022 Technical Specification Bases Pages ML22032A2692022-01-28028 January 2022 Technical Specification Bases Pages ML22027A7362022-01-27027 January 2022 Request for Enforcement Discretion from Technical Specification 3.5.2 ECCS Subsystems and Technical Specification 3.7.3 Reactor Plant Component Cooling Water System ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21047A4332021-02-15015 February 2021 Attachment 2: MPS3 Technical Specification Bases Pages ML21047A4322021-02-15015 February 2021 Attachment 1: MPS2 Technical Specification Bases Pages ML20252A1912020-09-0404 September 2020 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Deferral of the Millstone Unit 3 Steam Generator Inspections 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 ML20063L8232020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20065K9762020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20063L2872020-02-26026 February 2020 Technical Specification Bases Pages 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 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. ML19052A1612019-02-14014 February 2019 Changes to Technical Specification Bases ML16257A5632016-09-19019 September 2016 Correction Letter to Amendment No. 327 - Technical Specification Changes for Spent Fuel Storage ML16258A1442016-09-0101 September 2016 Administrative Correction to License Amendment 327, Technical Specification Changes to Spent Fuel Pool Storage ML16061A0732016-02-23023 February 2016 Changes to Technical Specification Bases ML16034A3582016-01-26026 January 2016 License Amendment Request, Spent Fuel Pool Heat Load Analysis ML15342A0282015-12-0101 December 2015 Supplement to License Amendment Request to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15246A1172015-08-31031 August 2015 Supplement to License Amendment Request to Revise TS 6.19, Containment Leakage Testing Program ML15065A3342015-02-26026 February 2015 Changes to Technical Specification Bases 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. ML14093A0272014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14093A0262014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14070A3462014-03-0606 March 2014 Changes to Technical Specification Bases ML13281A8092013-10-0202 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink ML13281A8042013-10-0202 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink ML13198A2712013-06-27027 June 2013 Supplement to License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. ML13120A1582013-04-25025 April 2013 License Amendment Request to Revise Technical Specification 6.8.4.F for Peak Calculated Containment Internal Pressure ML13079A2262013-03-0606 March 2013 Submittal of Changes to Technical Specification Bases ML12362A0122012-12-17017 December 2012 License Amendment Request to Revise Surveillance Requirement 4.4.3.2 Reactor Coolant System Relief Valves ML12081A1292012-03-0909 March 2012 Changes to Technical Specification Bases ML12032A2242012-01-25025 January 2012 License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3 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 ML1023904032010-08-19019 August 2010 Changes to Technical Specification Bases ML0925806592009-09-0909 September 2009 Changes to Technical Specification Bases ML0826104492008-09-0808 September 2008 Transmittal of Changes to Technical Specification Bases ML0723303092007-08-15015 August 2007 Reactor Coolant System Leakage Detection Systems (Lbdcrs 07-MP2-012 and 07-MP3-032) ML0720003962007-07-13013 July 2007 Attachment 4, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Mark-Up of Associated Technical Specifications Bases Pages ML0715605312007-05-31031 May 2007 Tech Spec Pages for Amendment 299 Steam Generator Tube Integrity ML0711002192007-04-12012 April 2007 Changes to Technical Specifications Bases ML0708807052007-03-28028 March 2007 License Amendment Request (LBDCR 07-MP2-007) Re Containment Spray Nozzle Surveillance ML0703101462007-01-30030 January 2007 Technical Specification, Pressurizer Water Level Limits ML0700300722007-01-0202 January 2007 Supplement to Proposed Technical Specification Change (LBDCR 04-MP3-011) Auxiliary Feedwater System Allowed Outage Time 2024-03-22
[Table view] Category:Amendment
MONTHYEARML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement 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 ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22027A7362022-01-27027 January 2022 Request for Enforcement Discretion from Technical Specification 3.5.2 ECCS Subsystems and Technical Specification 3.7.3 Reactor Plant Component Cooling Water System ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML20252A1912020-09-0404 September 2020 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Deferral of the Millstone Unit 3 Steam Generator Inspections 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 ML20063L8232020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation 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 ML16257A5632016-09-19019 September 2016 Correction Letter to Amendment No. 327 - Technical Specification Changes for Spent Fuel Storage ML15246A1172015-08-31031 August 2015 Supplement to License Amendment Request to Revise TS 6.19, Containment Leakage Testing Program ML14093A0272014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14093A0262014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML13281A8092013-10-0202 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink ML13281A8042013-10-0202 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink ML13120A1582013-04-25025 April 2013 License Amendment Request to Revise Technical Specification 6.8.4.F for Peak Calculated Containment Internal Pressure ML12362A0122012-12-17017 December 2012 License Amendment Request to Revise Surveillance Requirement 4.4.3.2 Reactor Coolant System Relief Valves ML0715605312007-05-31031 May 2007 Tech Spec Pages for Amendment 299 Steam Generator Tube Integrity ML0703101462007-01-30030 January 2007 Technical Specification, Pressurizer Water Level Limits ML0518101502005-06-28028 June 2005 Technical Specification Bases Pages ML0506706622005-02-25025 February 2005 Administrative Changes in Technical Specifications ML0326913862003-09-17017 September 2003 Amended TS Pages Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions ML0302805422003-01-16016 January 2003 Response to a Request for Additional Information, License Basis Document Change Request 2-1-02 Limiting Safety System Settings & Instrumentation ML0221201682002-07-19019 July 2002 Application for Amendment to NPF-49 to Modify Technical Specification Requirements for Missed Surveillances in Specification 4.0.3 & Modify Associated Technical Specification Bases ML0212901372002-05-0808 May 2002 Technical Specifications for Amendments Relocating Various Reactor Coolant System Technical Specifications to the Respective Unit'S Technical Requirements Manual ML0209200232002-03-29029 March 2002 Corrected TS Pages 3/4 3-39 & 3/4 3-41 ML0203701252002-02-0101 February 2002 Technical Specifications Pages Amendment 264 Revising the TSs and Bases Related to Reactor Coolant Pump Flywheel Inspection Requirements and Reactor Coolant System Structural Integrity ML0201103752002-01-11011 January 2002 Technical Specifications Pages for Amendment 263 Changes to TS Definitions for Core Alteration & Refueling Operations ML0201004062002-01-0808 January 2002 TS Pages for Amendment 262 Elimination of Requirements for Post-Accident Sampling ML0135202902002-01-0808 January 2002 Issuance of Amendment Elimination of Requirements for Post-Accident Sampling ML0135202162002-01-0808 January 2002 Issuance of Amendment Elimination of Requirements for Post-Accident Sampling ML0200702602002-01-0404 January 2002 Amendment 261 to TS Pages Emergency Diesel Generator Allowed Outage Time ML18088A9471976-04-19019 April 1976 Proposed Revisions to Environmental Technical Specifications ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2024-03-22
[Table view] |
Text
Dominion Energy Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com March 22, 2024 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 Serial No.
NRA/SS:
Docket No.
License No.24-002 RO 50-423 NFP-49 APPLICATION FOR TECHNICAL SPECIFICATION CHANGE TO EXTEND THE INSPECTION INTERVAL FOR REACTOR COOLANT PUMP FLYWHEELS USING THE CONSOLIDATED LINE-ITEM IMPROVEMENT PROCESS Pursuant to 10 CFR 50.90, Dominion Energy Nuclear Connecticut, Inc. (DENC) is submitting a license amendment request (LAR) to the Nuclear Regulatory Commission (NRC) to revise the Technical Specific ations (TS) for Millstone Power Station Unit 3 (MPS3).
The proposed amendment will extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years. The changes are consistent with Industry/Technical Specification Task Force (TSTF) Stan dard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)." The availability of this TS improvement was announced in the Federal Register on October 22, 2003, as part of the consolidated line-item improvement process (CLIIP). to this letter describes the proposed changes and the requested confirmation of applicability. Attachment 2 provides marked-up MPS3 TS pages showing the proposed changes.
The proposed amendment has been reviewed and approved by the station's Facility Safety Review Committee.
DENC requests approval of this LAR by March 22, 2025, with a 60-day impl ementation period.
In accordance with 10 CFR 50.91 (b), a copy of this LAR is being provided to the State of Connecticut.
Serial No.24-002 Docket No. 50-423 Page 2 of 3 If you have any questions or require additional information, please contact Mr. Shayan Sinha at (804) 273-4687.
Sincere
/
Jal Holloway Vice President -Nuclear Engineering and Fleet Support COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by James Holloway, 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 on behalf of that company, and that the statements in the dqcument are true to the best of his knowledge and belief.
Acknowledged before me this 22 day of r('(;lv--c\\r)
My Commission Expires: q \\'3of 2-0 2 "1-
,JULIE H HOUGH NOTARY PUBLIC 8066994 COMMONWE/-\\LTH OF VIRGINIA MY COMMISSION EXPIRES 09-30.2027 Attachments: 2024.
1.Description and Assessment of Proposed Change 2.Marked-up Technical Specification Pages Commitments made in this letter: None Notary Pu ic cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Rd., Suite102 King of Prussia, PA 19406-1415 Richard V. Guzman Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 9 E3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environ mental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No.24-002 Docket No. 50-423 Page 3 of 3 Serial No.24-002 Docket Nos. 50-423
Attachment 1
DESCRIPTION AND ASSESSMENT OF PROPOSED CHANGE
Dominion Energy Nuclear Connecticut, Inc.
Millstone Power Station Unit 3 Serial No.24-002 Docket No. 50-423 Attachment 1, Page 1 of 3
1.0
SUMMARY
DESCRIPTION
Pursuant to 10 CFR 50.90, Dominion Energy Nuclear Connecticut, Inc. (DENC) is submitting a license amendment request (LAR) to the Nuclear Regulatory Commission (NRC) to revise the Technical Specifications (TS) for Millstone Power Station Unit 3 (MPS3). The proposed LAR changes TS 6.17, Reactor Coolant Pump Flywheel Inspection Program. The revisions are consistent with Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, Revision to RCP Flywheel Inspection Program (WCAP-15666). The availability of this TS improvement was announced in the Federal Register on October 23, 2003, as part of the consolidated line-item improvement process (CLIIP).
2.0 DESCRIPTION
OF PROPOSED AMENDMENT
Consistent with the NRC-approved TSTF-421, the proposed TS change includes the following revision to TS 6.17:
The examination interval for the RCP flywheels is changed from at least once every 10-years coinciding with the Inservice Inspection schedule as required by ASME Section XI, to at least once every 20 years.
3.0 BACKGROUND
The background for this application is adequately addressed by the NRC Notice of Availability published on October 22, 2003, (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421, WCAP-15666, Extension of Reactor Coolant Pump Motor Flywheel Examination, and the related NRC safety evaluation (SE) dated May 5, 2003.
4.0 REGULATORY REQUIREMENTS AND GUIDANCE
The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590),
TSTF-421, WCAP-15666, and the related NRC SE.
Serial No.24-002 Docket No. 50-423 Attachment 1, Page 2 of 3
5.0 TECHNICAL ANALYSIS
DENC has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLIIP. This verification included a review of the NRC staffs model SE, as well as the information provided to support TSTF-421 (including WCAP-15666 and the related SE dated May 5, 2003). DENC has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC staff are applicable to MPS3 and justify this amendment for incorporation into the MPS3 TS.
6.0 REGULATORY ANALYSIS
A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC notices related to the CLIIP, TSTF-421, topical report WCAP-15666, and the associated SE.
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION
DENC has reviewed the proposed no significant hazards consideration determination published on June 24, 2003 (68 FR 37590) as part of the CLIIP. DENC has concluded that the proposed determination presented in the notice is applicable to MPS3 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
8.0 ENVIRONMENTAL EVALUATION
DENC has reviewed the environmental evaluation included in the model safety evaluation dated June 24, 2003 (68 FR 37590) as part of the CLIIP. DENC has concluded that the NRC staff's findings presented in that evaluation are applicable to MPS3 and the evaluation is hereby incorporated by reference for this application.
9.0 PRECEDENT
This application is being made in accordance with the CLIIP. DENC is not proposing any substantive variations or deviations from the TS changes described in TSTF-421 or the NRC staffs model SE published on June 24, 2003 (68 FR 37590). Note that MPS3 has not converted to STS; therefore, there are some administrative differences in TS numbering. The NRC approved an Amendment for DC Cook on January 31, 2020 (ADAMS Accession No: ML193478376), which followed a similar approach of only revising the TS section to reflect the new examination interval.
Serial No.24-002 Docket No. 50-423 Attachment 1, Page 3 of 3
10.0 REFERENCES
- 1. Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line-Item Improvement Process, published October 22, 2003, (68 FR 60422).
- 2. Federal Register Notice: Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line-Item Improvement Process, published June 24, 2003 (68 FR 37590).
- 3. Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, Revision to RCP Flywheel Inspection Program (WCAP-15666), Revision 0, November 2001.
- 4. WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination,"
July 2001.
- 5. NRC letter dated May 5, 2003, from H. Berkow to R. Bryan (WOG) transmitting Safety Evaluation of WCAP-15666
Serial No.24-002 Docket No. 50-423
Attachment 2
MARKED-UP TECHNICAL SPECIFICATIONS PAGES
Dominion Energy Nuclear Connecticut, Inc.
Millstone Power Station Unit 3 Serial No.24-002 Docket No. 50-423 Attachment 2, Page 1 of 1
1eimch 16, 2006 ADMINISTRATIVE CONTROLS
J-Limitations on the annual dose or dose commitment to any member of beyond the SITE BOUNDARY, due to releases of radioactivity and to radiation Y the public,
from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of Specification 4.0.2 and Specification 4.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
6.16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide ( 1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the REMODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- a. Monitoring, sampling, analysis, and reporting ofradiation and radionuclides in the environment in accordance with the methodology and param eters in the REMODCM.
- b. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made ifrequired by the results of this census, and
- c. Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive mat erials
in environmental sample matrices are perfonned as part of the quality assurance program for environmental monitoring.
6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM
This program shall provide for the inspection of each reactor coolant pump flywheel by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywhee ls at least once every ~
6.18 TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM
This program provides a means for processing changes to the Bases of these Technical Specifications:
- a. Changes to the Bases of the TS shall be made under appropriat e administrative controls and r eviews.
- b. Licensees may make changes to Bases without prior N RC approval provided the changes do not require either of the following:
- 1. A change in the TS incorporated in the license or
- 2. A chang e to updated FSAR or Bas es that r equires NRC approval pursuant to 10 CFR 50.59.
MILLSTONE - UNIT 3 6-26 Amendment No. -l--88, W4, i-H, ~,
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