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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23068A1072023-03-0808 March 2023 End of Cycle 21 Steam Generator Tube Inspection Report Supplement ML22300A1002022-10-27027 October 2022 End of Cycle 21 Steam Generator Tube Inspection Report ML22213A1202022-08-19019 August 2022 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 21 ML21336A6252021-12-0101 December 2021 Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 27 ML21014A2262020-12-21021 December 2020 Inservice Inspection Program Owner'S Activity Report, Refueling Outage 20 ML20268A2252020-09-23023 September 2020 ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Third Period of the Fourth 10-Year Inspection Interval ML20198M6822020-07-15015 July 2020 Alternate Request RR-05-06 - Inspection Interval Extension for Steam Generator Pressure Retaining Welds and Full-Penetration Welded Nozzles ML20076A5492020-03-14014 March 2020 Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping ML20049A0882020-02-17017 February 2020 ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval ML20048A0062020-02-11011 February 2020 ASME Section XI Inservice Inspection Program: Relief Request for Limited Coverage Examinations Performed in the Second Period of the Fourth 10-Year Inspection Interval ML19275D2542019-09-19019 September 2019 End of Cycle 19 Steam Generator Tube Inspection Report ML19211B1672019-07-23023 July 2019 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 19 ML19100A1262019-03-19019 March 2019 Inservice Inspection Program Interval Change ML19023A0242019-01-11011 January 2019 Submittal of Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 25 ML18114A1052018-04-19019 April 2018 End of Cycle 18 Steam Generator Tube Inspection Report ML18066A0782018-03-0101 March 2018 In-service Testing Program for Pumps, Valves, & Snubbers Fifth & Fourth 10-Year Interval Updates for Units 2 & 3 ML18031A0932018-01-24024 January 2018 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 18 ML17269A0302017-09-18018 September 2017 End of Cycle 24 Steam Generator Tube Inspection Report ML17187A1362017-06-27027 June 2017 Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 24 ML16222A3512016-08-0202 August 2016 Submittal of End of Cycle 17 Steam Generator Tube Inspection Report ML16214A2432016-07-25025 July 2016 Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 17 ML16033A4712016-01-22022 January 2016 Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23 ML15356A3752015-12-14014 December 2015 End-of-Cycle 23 Steam Generator Tube Inspection Report ML15049A2932015-02-0909 February 2015 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 16 ML15050A0412015-02-0909 February 2015 End of Cycle 16 Steam Generator Tube Inspection Report ML15033A3732015-01-26026 January 2015 Response to Second Request for Addition Information Regarding Aging Management Program Description: Inservice Inspection - Reactor Vessel Internals, License Renewals Commitment #13 ML14220A0162014-08-0101 August 2014 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 22 ML14206A8372014-07-21021 July 2014 Response to Request for Additional Information Regarding Aging Management Program Description: Inservice Inspection - Reactor Vessel Internals, License Renewal Commitment #13 (MF3402) ML14188B1902014-06-26026 June 2014 End of Cycle 22 Steam Generator Tube Inspection Report ML14143A4082014-05-20020 May 2014 Examination Summary and Coverage Results ASME Section XI Inservice Inspection Program Alternative Request RR-04-15, Limited One-Sided Ultrasonic Examination Technique ML14051A1092014-02-0707 February 2014 Response to Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Alternative Request RR-04-15, Limited One-Sided Ultrasonic Examination Technique ML13284A0652013-10-0202 October 2013 End of Cycle 15 Steam Generator Tube Inspection Report ML13218A2642013-07-31031 July 2013 Information in Support of License Renewal Commitment #13 Program Description for Reactor Vessel Internals Inspections ML13045A4862013-02-0505 February 2013 Inservice Inspection Program-Owner's Activity Report, Refueling Outage 21 ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review ML12109A0442012-04-0606 April 2012 End of Cycle 14 Steam Generator Tube Inspection Report ML11207A4642011-07-18018 July 2011 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 20 ML1102502592011-01-20020 January 2011 Request for Additional Information Regarding Relief Requests for Limited Coverage Examinations Performed in the Second 10-Year Inspection Interval ML1022205272010-08-0505 August 2010 Fourth 10-Year Interval Inservice Inspection Program ML1025802042010-07-29029 July 2010 Fourth 10-Year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Request ML1021500712010-07-25025 July 2010 Inservice Inspection Program - Owner'S Activity Report ML1006404562010-03-0505 March 2010 CFR50.55a Relief Request IR-3-14, Update to the Risk-Informed Inservice Inspection Program for the Third 10-Year Inspection Interval ML1005011632010-02-0404 February 2010 Inservice Inspection Program - Owner'S Activity Report for Refueling Outage 19 ML0913106662009-04-28028 April 2009 Third 10-year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Requests ML0908503442009-03-13013 March 2009 Submittal of End of Cycle 12 Steam Generator Tube Inspection Report ML0905700482009-02-13013 February 2009 Submittal of Inservice Inspection Program - Owner'S Activity Report for 05/20/07 Through Refueling Outage 12, 11/24/08 ML0824104152008-08-0707 August 2008 Submittal of Inservice Inspection Program - Owner'S Activity Report ML0811401382008-04-11011 April 2008 Submittal of 2007 Steam Generator Tube Inspection Report ML0735312562007-12-0707 December 2007 Inservice Testing Program 10-Year Interval End Date Changes ML0722604282007-08-0303 August 2007 Inservice Inspection Program - Owner'S Activity Report for Refueling Outage 11 2023-03-08
[Table view] Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
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Dominion Nuclear Connecticut, Inc.
Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385
<lorn.com JUL 2 5 2016 U.S. Nuclear Regulatory Commission Serial No.16-254 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 license No. NPF-49 DOM~NION NUCllEAR CONNECl~CUl, ~NC.
MILLSTONE POWER SlAl~ON UNIT 3 .
INSERV~CE ~NSPlECT~ON fPROGRAM.:... OWNIER S ACT~V~lY RIEfPORT, 1
REFUJEUNG OUTAGE ~7 Dominion Nuclear Connecticut, Inc. (DNC) hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-1, Owner's Activity Report, for the period from November 18, 2014 through Refueling Outage 17, completed on May 13, 2016 for Millstone Power Station Unit 3. The enclosure is in accordance with the requirements of ASME Code Case N-532-4.
If you have any questions or require additional information, please contact Jeffry A.
Langan at (860) 444-5544.
Sincerely,
~~
B. L. Stanley Director, Nuclear Safety and Licensing - Millstone
Enclosure:
- 1. Owner's Activity Report, Refueling Outage 17, Revision 0.
- Commitments made in this letter: None
Serial No.16-254 MPS3 Owner's Activity Report Docket No. 50-423 Page 2 of 2 cc: U. S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager - Millstone Power Station U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.16-254 Docket No. 50-423 ENCLOSURE 1 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 Contents:
OAR-1 Report Number: MP3-3R17 Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service.
Table 2: Abstract of Repairs/Replacement Activities Required for Continued Service Prepared By: Date: 7;{/;&
I I Reviewed By: ~ 74--ME Code Case N-566-2 and found to B-P I 815.20 Valve 3RHS*MV8702B be acceptable for continued service as documented in CR1034435 and ETE-MP-2016-1058.
Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Inlet Flange be acceptable for continued service as documented in CR1036848 and ETE-MP-2016-1081.
Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Outlet Flange be acceptable for continued service as documented in CR1036860 and ETE-MP-2016-1081.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*V017 be acceptable for continued service as documented in CR1029017 and ETE-MP-2016-1006.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*MV8802B be acceptable for continued service as documented in CR1036511 and ETE-MP-2016-1079.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*MV8821A be acceptable for continued service as documented in CR1036483 and ETE-MP-2016-1079.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I B15.20 Valve 3SI L*V985 be acceptable for continued service as documented in CR1034279 and ETE-MP-2016-1048.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I B15.20 Valve 3RCS*SV8095B be acceptable for continued service as documented in CR1037278 and ETE-MP-2016-1084.
Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Servoce Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS* AV8037C be acceptable for continued service as documented in CR1034041 and ETE-MP-2016-1048.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*AV80378 be acceptable for continued service as documented in CR1033846 and ETE-MP-2016-1048.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*V107 be acceptable for continued service as documented in CR1034039 and ETE-MP-2016-1048 Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*MV8003A be acceptable for continued service as documented in CR1034272and ETE-MP-2016-1058.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*MV8003C be acceptable for continued service as documented in CR1034275 and ETE-MP-2016-1058.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to 8-P I 815.20 Valve 3RCS*MV8003D be acceptable for continued service as documented in CR1034281 and ETE-MP-2016-1058.
Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace section of 3 Pipe Spool Service Water line 02/03/2015 53102801095 3-SWP-003-324-3.
Replace section of 3 Pipe Spool Service Water line 12/16/2015 53102874177 3-SWP-003-276-3.
Replace section of 53102957056 3 Pipe Spool Service Water line 04/25/2016 53102797777 3-SWP-018-82-3.