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MONTHYEARML0830903962008-10-24024 October 2008 End of Cycle 18 Steam Generator Tube Inspection Report Project stage: Request ML0907503752009-04-13013 April 2009 Review of Steam Generator Tube Inspection Report for 2008 Refueling Outage Project stage: Approval ML0915402032009-05-20020 May 2009 Response to Request for Additional Information 2008 Steam Generator Tube Inspections Project stage: Response to RAI ML0919103652009-07-21021 July 2009 Nuclear Regulatory Commission Staff Review of the 2008 Steam Generator Tube Inspections Project stage: Approval 2009-04-13
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:Report
MONTHYEARML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22193A1432022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20352A3342020-12-17017 December 2020 Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19352B8982019-12-17017 December 2019 Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML19246A1162019-10-0707 October 2019 Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML19070A2172019-04-0303 April 2019 Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation ML19064A5902019-02-28028 February 2019 Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML18256A2002018-10-0303 October 2018 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (EPID L00495\05000336 L-2015-JLD-0011 and 00495\05000423\L-2015-JLD-0012) ML18247A2752018-06-18018 June 2018 Technical Requirements Manual ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15253A2062015-09-0101 September 2015 ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report. ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML15078A2052015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 1 Through 2-57 ML15078A2082015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-172 Through the End ML15078A2072015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-126 Through 2-171 ML15078A2062015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-58 Through 2-125 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13357A3982014-01-24024 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Milestone Power Station, Unit 2, TAC No.: MF0858 ML14006A1592014-01-0808 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Millstone Power Station, Unit 3, TAC No.: MF0859 ML14087A0992013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 2023-07-26
[Table view] Category:Miscellaneous
MONTHYEARML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12362A3922012-11-30030 November 2012 Spent Fuel Pool Criticality Analysis with No Credit for Boraflex. ML12353A2422012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12187A1752012-06-25025 June 2012 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2010 and 2011, and Commitment Change Report for 2010 and 2011 ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review ML12046A8362012-01-31031 January 2012 Inservice Inspection Program - Owner'S Activity Report ML12031A1472012-01-25025 January 2012 Day Report for Emergency Core Cooling System Model Changes of 10 CFR 50.46 ML1116002202011-06-13013 June 2011 Exhibit D (Part 3): Millstone 2001 Safstor Cost Analysis (Normal Dollars) ML1028504382010-09-30030 September 2010 Attachments 2, 3, 5, 7, 8 & 9, to 10-579A, Westinghouse Electric Co. LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Revision 2, Dated Sep ML1019403352010-06-30030 June 2010 Units, 1, 2, 3, & ISFSI, 10 CFR 50.59, 10 CFR 72.48 Change Report for 2008 and 2009, and the Commitment Change Report for 2009 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1009702062010-03-29029 March 2010 Chemistry Procedure, Liquid Waste Sample Sink, Rev. 003-00 ML0931701762009-11-12012 November 2009 Part 3 of 4--Weld Overlay Examination Report 2R19 ML0931701732009-11-12012 November 2009 Part 2 of 4--Weld Overlay Examination Report 2R19 ML0931701662009-11-12012 November 2009 Part 1 of 4--Weld Overlay Examination Report 2R19 ML0931701852009-09-23023 September 2009 Part 4 of 4--Weld Overlay Examination Report 2R19 ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0913204602009-04-28028 April 2009 2008 Occupational Radiation Exposure Information ML0901303822008-12-26026 December 2008 Revision 002 to CP 3804L Procedure Action Request, Pass Containment Air Sample, Dated 12/26/2008 ML0830903962008-10-24024 October 2008 End of Cycle 18 Steam Generator Tube Inspection Report ML0827701132008-09-30030 September 2008 Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request ML0819800752008-07-0707 July 2008 Revision to Control Room and OSC Assembly Area Building 475 1st Floor, and SAP Locker ML0818406072008-07-0101 July 2008 Final Evaluation of Weld Overlay Examinations in Refueling Outage 18 ML0727504022007-09-27027 September 2007 Alternative Request RR-89-64 for Use of a Limited One-Sided Ultrasonic Examination Technique LBDCR 07-MP2-034 ML0720003902007-07-13013 July 2007 Attachment 1, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Descriptions, Technical Analysis and Regulatory Analysis for the Proposed Operating License and Technical Specifications Changes ML0715203992007-05-30030 May 2007 Fy 2007 Final Fee Rule Workpapers ML0713501882007-05-17017 May 2007 Review of Steam Generator Tube Inservice Inspection Report for the 2005 Refueling Outage at Millstone Power Station, Unit No. 2 ML0713502492007-05-0808 May 2007 Steam Generator Tube Plugging Report ML0708805652007-03-28028 March 2007 Response to Request for Additional Information Regarding an Alternative for the Weld Overlay of Pressurizer Nozzle Welds ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report 2023-07-26
[Table view] |
Text
Dominion Nuclear Connecticut, Inc.
Millstone Power Station S Dominion Rope Ferry Road, Waterford, CT 06385 OCT 2 4 2008 U.S. Nuclear Regulatory Commission Serial No. 08-0627 Attention: Document Control Desk NSS&L/MLC RO One White Flint North Docket No. 50-336 11555 Rockville Pike License No. DPR-65 Rockville, MD 20852-2738 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 2 END OF CYCLE 18 STEAM GENERATOR TUBE INSPECTION REPORT In accordance with the Millstone Power Station Unit 2 (MPS2) Technical Specification (TS), Section 6.9.1.9, Dominion Nuclear Connecticut, Inc., hereby submits, the End of Cycle (EOC) 18 Steam Generator Tube Inspection Report. The report is submitted within 180 days after initial entry into MODE 4 following completion of an inspection performed in accordance with TS 6.26, Steam Generator (SG) Program.
The report includes the following:
- a. The scope of inspections performed on each SG,
- b. Active degradation mechanisms found,
- c. Nondestructive examination techniques utilized for each degradation mechanism,
- d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
- e. Number of tubes plugged during the inspection outage for each active degradation mechanism,
- f. Total number and percentage of tubes plugged to date, and
- g. The results of condition monitoring, including the results of tube pulls and in-situ testing.
If you have any questions or require additional information, please contact Mr. William D.
Bartron at (860) 444-4301.
Sincerely, A. J. ,:dkdan Site VP - Millstone A- 0(-17
ýAw
Serial No. 08-0627 Docket No. 50-336
Enclosures:
(1)
Commitments made in this letter: None.
cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ms. C. J. Sanders NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-B3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No. 08-0627 Docket No. 50-336 ENCLOSURE Millstone Power Station Unit 2 End of Cycle 18 Steam Generator Tube Inspection Report MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 1 of 11 End of Cycle 18 Steam Generator Tube Inspection Report Millstone Power Station Unit 2 (MPS2) is a two loop Combustion Engineering (CE) pressurized water reactor (PWR) with Babcock and Wilcox (B&W) replacement Steam Generators (SGs). Each SG was designed to contain 8523 U-bend thermally treated Inconel 690 tubes. One hot leg tubesheet hole in SG 1 was plugged during construction and the opposing cold leg hole was not drilled, thus SG 1 has 8522 tubes. The tubing is nominally 0.750 inches outside diameter with a 0.0445 inch nominal wall thickness.
During replacement SG fabrication, the tubes were installed using a two-step hydraulic expansion process over the full depth of the 21.06 inch thick tubesheet. The tubesheet was drilled on a triangular pitch with 1.0 inch spacing. There are 141 rows and 167 columns in each SG. To minimize small radius U-bends, tubes in rows 1 through 3 were installed using a staggered arrangement. This resulted in the termination of tubes at different locations between the hot and cold legs. For these rows, the tube identification follows the hot leg row/column naming convention. Secondary side tube support structures include seven lattice grid supports on the vertical section of the tubes and twelve fan bar assemblies on the U-bend section of the tubes. All lattice grid supports are full supports. SG replacement was completed in the fall of 1992 during MPS2's Refueling Outage 11 (2R1 1). The new SGs have accrued 9.762 Effective Full Power Years (EFPY) of operation as of the End of Cycle (EOC) 18 (April 2008). The 910 MW unit operates with a hot leg temperature of 601 degrees Fahrenheit.
The MPS2 SG eddy current testing (ECT) conducted at EOC 18 was completed on April 24, 2008. Initial entry into Mode 4 following completion of the inspections occurred on May 12, 2008. The examinations, personnel, and equipment conformed to the requirements of NEI 97-06, Rev. 2, Steam Generator Program Guidelines; EPRI Pressurized Water Reactor Steam Generator Examination Guidelines, Rev. 6; and MPS2 Technical Specifications (TSs).
In accordance with MPS2 TSs, a SG tube inspection report is required. TS Section 6.9.1.9 states:
A report shall be submitted within 180 days after initialentry into MODE 4 following completion of an inspection performed in accordancewith TS 6.26, Steam Generator(SG) Program. The report shall include:
- a. The scope of inspectionsperformed on each SG, For both SG 1 and SG 2, a 100% full length bobbin coil examination was scheduled to be performed on all tubes from the tube end of the hot leg (TEH) to the tube end of the cold leg (TEC). This was accomplished for the majority of the tubes. The remaining tubes were examined from 07C to TEH, 07C to TEC, 07H to TEH, or 07H to TEC to complete the full length bobbin inspection. See Attachment 1, "Acronyms," for explanation of acronyms. See Attachment 2, "Millstone Power Station Unit 2 Steam Generator Arrangement," for illustration of steam generator component locations.
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 2 of 11 For both SG1 and SG 2, the rotating pancake coil (RPC) examinations included a 140 tube sample of hot leg tubesheet expansion transitions (TSH +3"/-3") in the periphery area of each SG. In addition, a total of 1012 (438 in SG 1 and 574 in SG 2) locations were examined with RPC. These locations included 2R15 and 2R16 historical locations which consisted of previously reported bulges (BLG), dings (DNG), dents (DNT), non-quantifiable historical indications (NQH), partial tubesheet expansion (PTE), possible loose part (PLP),
percent through-wall indications (%TW), and volumetric indications (VOL). These locations also included 2R1 8 bobbin coil special interest (SI) locations of ding (DNG), dent (DNT) distorted expansion indications (DEI), deposit (DEP), loose part indications (LPI),
non-quantifiable indications (NQI), possible loose parts (PLP), various hot leg and cold leg bounding locations, and tubes that were observed with flex gasket material protruding from the tube ends. The inspection summary is documented in Table 1.
Table 1 - Millstone 2R18 ECT Summary SG 1 SG 2 Total Number of Tubes (SG 1 and SG 2) 8,522 8,523 17,045 Number of Tubes Inspected F/L w/Bobbin Probe 8,522* 8,523* 17,045 Previously Plugged Tubes 0 0 0 Number of Tubes Incomplete w/Bobbin Probe due to Obstruction 0 0 0 Number of Inspections w/MRPC (Total) 578 714 1292
- Hot Leg Transitions - Original Scope (tubes) 140 140 280 eHot Leg Transitions - Scope Expansion (tubes) 0 0 0
- Hot Leg Misc. Special Interest - Diagnostic Exams and from 75 92 167 Previous History (locations)
- Cold Leg Transitions - Original Scope (tubes) 0 0 0
- Cold Leg Transitions - Scope Expansion (tubes) 0 0 0 sCold Leg Misc. Special Interest - Diagnostic Exams and from 98 144 242 Previous History (locations) oU-Bends - Original Scope (locations) 0 0 0 eU-bend. Special Interest - Diagnostic Exams and from 51 97 148 Previous History (locations) oPLP / SVI Bounding Special Interest (locations) 214 241 455 Tubes with Max FB Wear > 40 % 0 0 0 Tubes with Max FB Wear >20% but <40% 0 0 0 Tubes with Max FB Wear <20% 2 2 4 Tubes with Max SVI / VOL / WAR> 40 % 2 0 2 Tubes with Max SVI / VOL / WAR>20% but <40% 2 10 12 Tubes with Max SVI / VOL / WAR<20% 3 1 4 Tubes Plugged as a result of SVI / VOL / WAR> 37 % 2 0 2 Tubes Plugged as a result of no qualified sizing 5 0 5 Tubes Plugged as a result of FB Wear > 37 % 0 0 0 Tubes Plugged as a result of an Obstruction 0 0 0 Tubes Plugged on a discretionary basis (loose part wear with part 1 2 3 not removed) I I I Total Tubes Plugged as a Result of this Inspection 8 2 10
- For 102 tubes in SG 1 and 260 tubes in SG 2, the bobbin exam was a combination of two examinations from opposite legs with overlap at the upper support structure.
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 3 of 11
- b. Active degradationmechanisms found, Two mechanical tube degradation mechanisms - fan bar wear and foreign object wear were identified during this examination. There was no evidence of any corrosion-related degradation.
- c. Nondestructive examination techniques utilized for each degradation mechanism, Table 2 identifies the examination techniques utilized for each identified degradation mechanism.
- d. Location, orientation (if linear), and measuredsizes (if available)of service induced indications, Table 3 identifies the service induced indications reported during the examination.
- e. Number of tubes plugged during the inspection outage for each active degradationmechanism, In SG 1, seven wear indications were reported. Five were located at the tubesheet interface and not in the freespan and were caused by a transient loose part. Since there was no qualified technique for sizing indications at this location, all five tubes were removed from service by plugging. Two additional indications were located above the cold leg secondary side tubesheet interface and were caused by loose part wear. The loose part that caused the wear could not be removed by Foreign Object Search and Retrieval (FOSAR). The maximum depth sizing for these two indications was 67% and 58%. Both tubes along with a third adjacent tube were removed from service by plugging and stabilization. These three tubes box the loose part that could not be removed.
In SG 2, a wear indication was located above the hot leg secondary side tubesheet interface and was caused by a loose part. The maximum depth sizing was 11% TW. The loose part, a piece of flexitallic gasket, was still present and could not be removed. The tube with the wear indication along with an adjacent tube also in contact with the foreign object, were both removed from service by plugging and stabilization.
- f. Total number and percentage of tubes plugged to date, and A total of eight tubes were plugged in SG 1 during this outage and none had been previously plugged. Eight of 8522 tubes or 0.094% of the tubes in SG 1 have been plugged to date. A total of two tubes were plugged in SG 2 during this outage and none had been previously plugged. Two of 8523 tubes or 0.024% of the tubes in SG 2 have been plugged to date.
- g. The results of condition monitoring, including the results of tube pulls and in-situ testing.
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 4 of 11 No tubes were pulled and no in-situ pressure tests were performed. The condition monitoring assessment concluded that the structural integrity, operational leakage and accident induced leakage performance criteria were not exceeded during the operating interval preceding 2R18.
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 5 of 11 Table 2- Degradation Mechanisms and Available Inspection Techniques Degradation Location Likelihood Detection Best Estimate Sizing Technique, Tech. Sizing Tech. Sizing Technique, 2R18 Sample Size Mechanism of Near- Technique, ETSS Technique POD ETSS Number Correlation Regression Coef. Personnel Sizing Term Number (r2) (slope, intercept) Std Err (%TW)
Initiation Wear Tube to Tube Contact Low Bobbin, 96004.3 1.0 (>10%TW) Bobbin, 96004.3 0.98 0.96, 2.92 3.52, 0.86 100%, full length bobbin 0.98 (>40%TW) in both SGs
+Point, 96910.1 1.0 (>21%TW) +Point, 96910.1 0.92 1.01, 4.3 6.68, NA bobbin identified points of interest, +point / 0.115" 0.115", 96911.1 0.115", 96911.1 0.92 1.22, 0.07 7.49, 3.22 exams in both SGs 00 Wear Tube at Fan Bar Medium Bobbin, 96004.3 1.0 (>10%TW) Bobbin, 96004.3 0.98 0.96, 2.92 3.52, 0.86 1 %, full length bobbin (existing mechanism) 0.98 (>40%TW) in both SGs
+Point, 96910.1 1.0 (>21%TW) +Point, 96910.1 0.92 1.01, 4.3 6.68, NA bobbin identified points of interest, +point / 0.115" 0.115", 96911.1 0.115", 96911.1 0.92 1.22, 0.07 7.49, 3.22 exams in both SGs Wear Tube at Foreign Object Medium Bobbin, 96005.2 0.98 (>20%TW) Bobbin, 96005.2 0.17 0.27, 28.42 13.36, 1.73 100%, full length bobbin (existing mechanism) 0.88 (>40%TW) in both SGs
+Point, 96910.1 1.0 (>21%TW) +Point, 96910.1 0.92 1.01, 4.3 6.68, NA 0.115", 96911.1 0.115", 96911.1 0.92 1.22, 0.07 7.49, 3.22 +point/ 0.115" diagnostic exams Pitting Tube at Secondary Side Low Bobbin, 96005.2 0.98 (>20%TW), Bobbin, 96005.2 0.17 0.27, 28.42 13.36, 1.73 100%, full length in both Sludge/Deposits 0.88 (>40%TW) SGs Thinning Tube at support Low Bobbin, 96001.1 0.96 (>20%TW), Bobbin, 96001.1 0.74 0.97, -6.61 13.20, 0.89 100%, full length in both structures 0.98 (>40%TW) SGs Impingement Tube at support Very Low NA NA NA NA NA NA NA structures
[GA/SCC (OD) Tube Freespan, Non Very Low Bobbin, 96008.1 1.0 (>20%TW), Bobbin, 96008.1 0.55 0.74, 9.56 20.62, NA 100%, full length in both Volumetric/AxialDented Support 0.89 (>40%TW) SGs Intersections, Sludge Regions SCC (OD) Tube Freespan, Dented Very Low +Point, 21409.1 1.0 (>35%TW), +Point, 21409.1 0.15 0.33, 25.61 17.88, NA bobbin identified points of Axial and/or and Non Dented Support 0.98 (axial) 0.95 (% degraded area) (% degraded (% degraded (% degraded interest, +point exams in circumferential Intersections, Sludge (circ) area) area) area) both S&s Regions, Expansion Transition SCC (OD) Freespan including Very Low Bobbin, 24013.1 0.95 (>60%TW), NA NA NA NA 100%, full length bobbin Circumferential Dent > 5.0 volt in both SGs SCC (OD) Expansion Very Low +Point, 21410.1 1.0 (>42%TW) +Point, 0.02 0.13, 60.1 24.50 bobbin identified points of Transition 0.7 (<41%TW) 21410.1 interest, +point exams in both SGs Volumetric Freespan Medium +Point, 21998.1 1.0 (>10%TW) +Point, 21998.1 0.88 1.02, 5.81 6.28 +point/ 0.115" diagnostic exams
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 6 of 11 Table 2 - Degradation Mechanisms and Available Inspection Techniques (continued)
Degradation Location Likelihood Detection Best Estimate Sizing Technique, Tech. Sizing Tech. Sizing Technique, 2R18 Sample Size Mechanism of Near- Technique, ETSS Technique POD ETSS Number Correlation Regression Coef. Personnel Sizing 2
Term Number (r ) (slope, intercept) Std Err (%TW)
Initiation SCC (OD) Dented Structural Very Low +Point, 22401.1 1.0 (>53%TW) +Point, 22401.1 0.02 1.3, 74.55 14.44 bobbin identified points of Supports interest, +point exams in
+Point, 22842.1 1.0 (44%TW) +Point, 22842.1 0.56 0.52, 0.03 0.26 both SGs SCC (ID) Tube Expansion Very Low +Point, 20510.1 0.96 (>30%TW) +Point, 20510.1 0.77 0.82, 2.83 7.69 +Point diagnostic exams Circumferential Transition, Within (%degraded area) (% degraded (% degraded (% degraded Tubesheet, Dents, Near area) area) area)
Seal Weld, Plugs +Point, 96701.1 0.67(21-41%TW) +Point 96701.1 0.85 0.84, 10.32 9.56 1.0 (>42%TW)
CC (ID) Tube Expansion Very Low +Point, 20511.1 1.0 (>37%TW) +Point, 20511.1 0.29 0.36, 18.91 7.60 +Point diagnostic exams Axial Transition, Within (%degraded area) (% degraded (% degraded (%degraded Tubesheet, Dents, Tack area) area) area)
Expansion, Plugs, <2.Ov Bobbin, 96012.1 Dents at TSP / Freespan
+Point, 96703.1 1.0 (>17%TW) +Point, 96703.1
(% degraded area) 0.83 0.90, 0,77 10.06 (Axial Length) 0.83 1.00, 0.13 0.28 5CC (ID) Low Row U-bends Very Low +Point, 96511.3 1.0 (>27%TW) +Point, 96511.3 0.22 0.34, 31.96 17.61, NA bobbin identified points of Axial and/or interest, +point exams in circumferential both SGs PWSCC Axial Dents Very Low +Point, 96703.1 1.0 (>10%TW) +Point, 96703.1 0.98 0.90, 7.56 15.28 Bobbin identified points of interest Wear Circumferential Groove Medium +Point, 27901.0 1.0 (>31%TW) +Point, 27901.0 0.98 1.05, -1.97 2.30 Additional diagnostic wear (foreign object Axial Groove +Point, 27902.0 1.0 (>8%TW) +Point, 27902.0 1.0 0.98, 1.89 2.32 techniques for loose part not present) Tapered Football +Point, 27903.0 1.0 (>21%TW) +Point, 27903.0 1.0 0.97, 2.80 2.11 sizing (freespan) Tapered Round Hole +Point, 27904.0 1.0 (>32%TW) +Point, 27904.0 0.98 1.00, 0.48 1.99 Flat Wear +Point, 27905.0 1.0 (>7%TW) +Point, 27905.0 1.0 1.09, -4.31 2.05 Tapered Wear +Point, 27906.0 1.0 (>11%TW) +Point, 27906.0 1.0 0.96, 1.67 1.43 45 deg. Tapered Wear +Point, 27907.0 1.0 (>13%TW) +Point, 27907.0 0.98 1.05, -2.10 2.59 Corrosion Support Structures Very Low Bobbin, no NA NA NA NA NA 100%, full length in both Induced Tube specific ETSS SGs Denting Plug Installation Plug/Tube Interface Low Engineering review plug installation parameters and plug video after installation; Use to date of 1-690 welded plugs. SG 1 Deficiencies
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 7 of 11 Table 3 - Service Induced Indications SG I ROW COL VOLTS DEG PCT CHN LOCATION ELEVFROM 2 7 0.25 0 20 P5 TSH -0.07 3 8 0.15 0 13 P5 TSH -0.02 4 9 0.08 0 7 P5 TSH -0.02 5 10 0.08 0 8 P5 TSH -0.02 8 11 0.37 0 27 P5 TSH 0.09 40 155 0.37 115 11 P2 F06 -1.71 76 141 0.94 0 58 6 TSC 0.24 78 141 1.31 0 67 6 TSC 0.11 140 93 0.43 112 12 P2 F08 -0.54 SG 2 ROW COL VOLTS DEG PCT CHN LOCATION ELEVFROM 37 120 0.31 78 9 P2 F07 -0.7 28 5 0.25 0 29 6 01C -2.59 29 4 0.19 0 25 6 01C -1.86 40 81 0.17 79 30 6 TSH 0.12 59 10 0.16 0 23 6 01C -6.8 98 143 0.11 0 26 6 TSH 8.51 99 80 0.43 76 11 P2 F06 1.31 118 41 0.15 0 11 6 TSH 12.43 119 42 0.17 80 29 6 TSH 12.78 123 46 0.13 64 27 6 TSH 17.61 124 45 0.20 75 31 6 TSH 19.23 125 48 0.3 81 37 6 TSH 19.38 126 49 0.34 93 39 6 TSH 19.82
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 8 of 11 Attachments Attachment Title 1 Acronyms 2 Millstone Power Station Unit 2 Steam Generator Arrangement
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 9 of 11 Attachment I Acronyms B&W Babcock & Wilcox BLG Bulge CHN Channel COL Column DEG Degrees DEP Deposit DNG Ding DNT Dent ECT Eddy Current Testing EFPY Effective Full Power Years ELEV Elevation ETSS Examination Technique Specification Sheet FB Fan Bar F/L Full Length FOSAR Foreign Object Search and Retrieval IGA Intergranular Attack LPI Loose Part Indication MBM Manufacturing Burnish Mark MP 2 Millstone Unit 2 NQH Non-Quantifiable Historical Indication NQI Non-Quantifiable Indication OXP Over Expansion PCT Percent Through-Wall PLP Possible Loose Part POD Probability of Detection PTE Partial Tubesheet Expansion
%TW Percent Through-Wall RPC Rotating Pancake Coil SCC Stress Corrosion Cracking SG 1 Steam Generator Number 1 SG 2 Steam Generator Number 2 SLG Sludge SSI Secondary Side Inspection SVI Single Volumetric Indication TEC Tube End Cold-leg TEH Tube End Hot-leg TSC Top of Tube Sheet Cold-leg TSH Top of Tube Sheet Hot-leg VOL Volumetric Indication WAR Wear Indication
Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 10 of 11 Attachment 2 Millstone Power Station Unit 2 Steam Generator Arrangement
Serial No.16-127 Request for Withholding Proprietary Information Enclosure 6 Page 2 of 2 Serial No. 08-0627 Docket No. 50-336 EOC18 SG Tube Inspection Report Page 11of11
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