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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. Dominio 5000 Dominion Boulevard, Glen Allen, Virginia 23060 Web Address: www.dom.com September 27, 2007 U. S. Nuclear Regulatory Commission Serial No. 07-0533 Attention: Document Control Desk MPS Lic/ME R2 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 ALTERNATIVE REQUEST RR-89-64 FOR USE OF A LIMITED ONE-SIDED ULTRASONIC EXAMINATION TECHNIQUE LBDCR 07-MP2-034 Pursuant to 10 CFR 50.55a(a)(3)(ii), Dominion Nuclear Connecticut, Inc. (DNC) requests approval of an alternative to the Millstone Power Station Unit 2 (MPS2)
Risk-Informed Inservice Inspection (RI-ISI) program to allow use of a limited one-sided ultrasonic test (UT) examination technique. A discussion of this request is provided as an attachment to this letter. This alternative is needed for eight 36-inch outside diameter (OD) reactor coolant system (RCS) cold leg dissimilar metal welds with cast austenitic stainless steel safe ends that are welded with Alloy 82/182 material.
The MPS2 RI-ISI program, as approved by the NRC, lists these welds as requiring UT examination for the purpose of identifying Primary Water Stress Corrosion Cracking (PWSCC). The RI-ISI program requires that the ASME Code Section Xl, 1989 Edition with no Addenda be used in conjunction with the UT examination requirements outlined in WCAP-14572 Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report." These requirements cannot be met because of the cast austenitic stainless steel safe end base material and the weld design configuration.
DNC proposes within this request to use a one-sided UT examination technique from the ferritic side of these RCS dissimilar metal welds supplemented with bare metal visual examination for the UT coverage that is outlined in the enclosed Electric Power Research Institute (EPRI) Internal Report IR-2007-277, "EPRI Review of Millstone Unit 2 Dissimilar Metal Weld Walkdown Information," dated June 2007.
DNC requests approval of this alternative request by April 1, 2008 to support the
'Ao<1
Serial No. 07-0533 Alternative Request RR-89-64 Page 2 of 2 MPS2 spring 2008 refueling outage. If you have any questions regarding this submittal, please contact Margaret Earle at (804) 273-2768.
Sincerely, Gerald T. Bischof Vice President - Nuclear Engineering Commitments in this letter: None
Attachment:
Alternative Request RR-89-64 For Use Of A Limited One-Sided Ultrasonic Examination Technique
Enclosure:
EPRI Internal Report, IR-2007-277, "EPRI Review of Millstone Unit 2 Dissimilar Metal Weld Walkdown Information," dated: June 2007 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. D. Hughey NRC Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop O-8B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No. 07-0533 Docket No. 50-336 ATTACHMENT ALTERNATIVE REQUEST RR-89-64 FOR USE OF A LIMITED ONE-SIDED ULTRASONIC EXAMINATION TECHNIQUE DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
Serial No. 07-0533 Docket No. 50-336 Alternative Request RR-89-64 Attachment Page 1 of 6 ATTACHMENT ALTERNATIVE REQUEST RR-89-64 FOR USE OF A LIMITED ONE-SIDED ULTRASONIC EXAMINATION TECHNIQUE CONTENTS 1.0 REASON FOR THE REQUEST ................................................................. 2 2.0 CODE COMPONENTS FOR WHICH THE ALTERNATIVE IS R E Q UE ST E D ............................................................................................ .. 3 3.0 CODE REQUIREMENTS FOR WHICH THE ALTERNATIVE IS R E Q UE ST E D ........................................................................................... . 4 4.0 PROPOSED ALTERNATIVES AND SUPPORTING INFORMATION ...... 4 5.0 DURATION OF THE PROPOSED REQUEST ........................................... 5 6.0 P R E C E D E N T S ............................................................................................ 6 7.0 R E F E R E NC E S .......................................................................................... .. 6 8.0 C O NC LU S IO N ........................................................................................... 6
Serial No. 07-0533 Docket No. 50-336 Alternative Request RR-89-64 Attachment Page 2 of 6 ATTACHMENT ALTERNATIVE REQUEST RR-89-64 FOR USE OF A LIMITED ONE-SIDED ULTRASONIC EXAMINATION TECHNIQUE ProposedAlternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
- Compliance With The Specified Requirements Results In A Hardship or Unusual Difficulty Without A Compensating Increase In The Level Of QualityAnd Safety -
1.0 REASON FOR THE REQUEST For the upcoming spring 2008 Millstone Power Station Unit 2 (MPS2) refueling outage (2R18), eight high safety significant (HSS) dissimilar metal welds located on the reactor coolant pump (RCP) inlet and outlet reactor coolant system (RCS) cold leg piping are scheduled for ultrasonic test (UT) examination. If for some reason the welds cannot be examined during 2R18, they are required to be examined by the end of the following refueling outage (2R19). Currently, MPS2 has these weld examinations scheduled under the Risk-Informed Inservice Inspection (RI-ISI) program(1 ) as HSS welds that are susceptible to Primary Water Stress Corrosion Cracking (PWSCC). The RI-ISI program refers to the 1989 Edition of Section XI with no Addenda (Reference 1), Figure IWB-2500-8, for the required volume examination and to the requirements in Examination Category R-A, Risk-Informed Piping Examinations within WCAP-14572 Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report,"
(Reference 2), Table 4.1-1. Figure IWB-2500-8 requires that the bottom one-third of the weld and some associated base material be volumetrically examined, but does not require examination of the entire weld end buttering material. Industry guidance contained in the Materials Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guidelines (MRP-139) (Reference 3) includes weld butter in the examination volume. Both the RI-ISI program requirement and the industry guidance require that some of the base material on either side of the weld and butter be UT examined.
The design configuration of the eight HSS dissimilar metal welds limits examination of the base material from the ferritic steel side of the welds. Currently, the only possible solution for improving the inspectability of these welds would be to machine the welds; however, machining the welds could result in violating the necessary minimum wall thickness of the pipe or elbow. Additionally, all of the eight welds are fabricated with cast austenitic stainless steel safe ends and no UT technique (1) NRC letter, "Safety Evaluation For Millstone Power Station, Unit No.2 - Risk-Informed Inservice Inspection Program (TAC No. MC1284)," dated April 1, 2005, (ADAMS Accession No. ML050740463).
Serial No. 07-0533 Docket No. 50-336 Alternative Request RR-89-64 Attachment Page 3 of 6 requirements exist to qualify by demonstration UT examination of this cast austenitic stainless steel material. Based on this discussion, this alternative request is being proposed to allow a limited UT examination of the eight welds from the ferritic pipe or elbow side of these welds.
2.0 CODE COMPONENTS FOR WHICH THE ALTERNATIVE IS REQUESTED Code components associated with the request consist of the eight 36-inch outside diameter (OD) HSS Class 1 cold leg dissimilar metal welds located within the RCS at the inlets and outlets of each RCP.
2.1 Category and System Details:
Code Class: All listed welds are ASME Code Class 1 welds.
System Welds: Welds are located in the RCS pressure boundary.
Code Category: Examination Category R-A, "Risk-Informed Piping Examinations."
Code Item No.: R 1.15, "Elements Subject to PWSCC."
2.2 Component Descriptions:
36-inch OD, RCP Inlet (Suction) Nozzles = (Safe-End-To-Elbow Welds) - Cast Austenitic Stainless Steel (P-8) - To - Ferritic Steel (P-I) With Alloy 82/182 Weld Material.
- 1. Weld No. P-4-C-1
- 2. Weld No. P-8-C-1
- 3. Weld No. P-13-C-1
- 4. Weld No. P-17-C-1 36-inch OD, RCP Outlet (Discharge) Nozzles = (Safe-End-To-Pipe Welds) -
Cast Austenitic Stainless Steel (P-8) - To - Ferritic Steel (P-i) With Alloy 82/182 Weld Material.
- 1. Weld No. P-5-C-3
- 2. Weld No. P-9-C-3
- 3. Weld No. P-14-C-3
- 4. Weld No. P-18-C-3
Serial No. 07-0533 Docket No. 50-336 Alternative Request RR-89-64 Attachment Page 4 of 6 3.0 CODE REQUIREMENTS FOR WHICH THE ALTERNATIVE IS REQUESTED MPS2 is in its third 10-year ISI interval, which started on April 1, 1999 and has been extended to end on March 31. 2010.(2) The 1989 Edition of Section XI with no Addenda (Reference 1) applies to the ISI program and the RI-ISI program. The 1995 Edition of Section XI with the 1996 Addenda, Appendix VIII, Supplement 10 (Reference 4) is used for UT examination performance demonstration requirements for dissimilar metal welds including the limitations in 10 CFR 50.55a(b). These requirements are implemented under the industry Performance Demonstration Initiative (PDI). Accordingly, the UT examination volume shown in Figure No. IWB-2500-8 (Reference 1) is required to be met under the RI-ISI program. In this figure the bottom one-third of the weld volume and a small portion of the base materials on each side of the weld must be covered by the UT examination. A similar Figure 2-3 is depicted on page 2-2 of the enclosure to this submittal. The required examination volume in Figure 2-3 is shown as C-D-F-E.
4.0 PROPOSED ALTERNATIVES AND SUPPORTING INFORMATION Based on: (1) the UT examination volume coverage that can be gained by multiple recommended search units (enclosure), (2) scanning the welds in the axial direction, and (3) the calculated coverage depicted and described in the enclosure, DNC has determined that it is possible to examine these dissimilar metal welds from the ferritic pipe or elbow side. This is true for both the RCP nozzle inlets and outlets.
In Summary Section 5 of the enclosure, EPRI essentially states that phased array technology (a different UT technology) could be used to improve the coverage on these dissimilar metal welds from the ferritic steel side of the welds. However, the sample configurations required to demonstrate this technology are not currently available. Future plans to have these sample configurations available will occur on a component-by-component basis.
Although DNC acknowledges the EPRI recommendation, DNC realizes the evaluation and application of this technology for the MPS2 subject welds will not be available until sometime in the future. The UT examination coverage that DNC can obtain using conventional techniques (described in the enclosure) forms the justification for this requested alternative.
To date, there is no qualified UT technique that has been demonstrated to be consistently reliable for cast stainless steel. Also, no ASME Code requirements exist to perform UT demonstrations for cast stainless steel. UT examination from the pipe (2) DNC letter to NRC, Millstone Units 2 & 3, Inservice Testing and Inservice Inspection Programs 10-Year Interval Changes," dated: May 3, 2007 (ADAMS Accession No. ML071350369).
Serial No. 07-0533 Docket No. 50-336 Alternative Request RR-89-64 Attachment Page 5 of 6 or elbow side of these eight welds will cover the full inside diameter of the welds for identification of any suspected circumferential PWSCC that may be present in the Alloy 82/182 weld material. Susceptibility to PWSCC is the reason that these welds were selected for examination under the RI-ISI program. However, limited coverage of this same Alloy 82/182 weld material when scanning these welds in the circumferential direction due to the OD configuration shows that it is possible to miss some axial oriented PWSCC if it does exist.
Understanding this situation and the limitation of the UT examination, DNC proposes as an alternative to the UT examination volume coverage requirements of Fig. IWB-2500-8 of the 1989 Edition of Section Xl, and Table 4-1.1 of WCAP-14572 Revision 1-NP-A, to perform a UT examination of the eight welds in this request with a PDI demonstrated procedure from the ferritic pipe or elbow side of the welds; and, perform a bare metal visual examination to provide the needed defense-in-depth in support of the limited UT for axial PWSCC when UT examination is not performed on these welds during a refueling outage. This proposed bare metal visual examination of these cold leg RCS welds exceeds the industry requirements available for use under ASME Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials Section Xl, Division 1." Code Case N-722 was approved by ASME on July 5, 2005 (Reference 5) and is currently listed for mandatory use as part of a proposed change to 10 CFR 50.55a (Federal Register, Vol. 72, No. 65, pp. 16731-16741, Thursday, April 5, 2007).
DNC is proposing this alternative to close out the MPS2 current 10-year ISI interval by performing these examinations to meet the requirements for the RI-ISI program and to follow the industry guidance of MRP-139. Due to the size of these welds, additional time is needed to determine the appropriate mitigation strategy for these welds in the future.
This alternative is supported by the fact that the eight welds are cold leg RCS welds.
They are not expected to be highly susceptible to PWSCC because of their lower operating temperature and industry experience has not shown any cracking in these specific types of welds.
5.0 DURATION OF THE PROPOSED REQUEST This request will be applied for the remainder of the current MPS2 third 10-year ISI interval, which is scheduled to end on March 31, 2010.
Serial No. 07-0533 Docket No. 50-336 Alternative Request RR-89-64 Attachment Page 6 of 6 6.0 PRECEDENTS A search of the NRC's electronic correspondence database, ADAMS, has not identified any similar requests by other Licensees regarding similar RCS piping welds.
7.0 REFERENCES
- 1. 1989 Edition, American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section Xl, no Addenda.
- 2. WCAP-14572 Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report," dated February 1999.
- 3. Material Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-1 39), EPRI, Palo Alto, CA: 2005. 1010087.
- 4. 1995 Edition, ASME Code, Section Xl, with the 1996 Addenda, Appendix VIII, Supplement 10.
- 5. ASME Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials Section Xl, Division 1," Approved by ASME on July 5, 2005.
8.0 CONCLUSION
The information outlined above and in the enclosure supports the DNC conclusion that a one-sided UT examination from the ferritic pipe or elbow side of the subject welds will provide detection capability for circumferential PWSCC. Additionally, it provides an increased frequency for bare metal visual examination that will be used to address the limitations for UT examination coverage for the detection of axial PWSCC. DNC believes that this proposed alternative request meets the intent of the MPS2 RI-ISI program for the eight HSS welds and that the proposal provides an acceptable alternative where compliance with the specified requirements results in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.