Letter Sequence Approval |
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MONTHYEARML0923702962009-08-19019 August 2009 Alternative Request IR-3-13 for the Use of Alternative Dissimilar Metal Weld Examination Depth-Sizing Requirements from ASME Code, Section XI Project stage: Request ML1003301492010-02-0101 February 2010 Response to Request for Additional Information Regarding Relief Request IR-3-13 Proposed Alternative for Dissimilar Metal Weld Examination Depth-Sizing Requirements Project stage: Response to RAI ML1008407382010-04-15015 April 2010 Issuance of Relief Requests IR-3-13 Regarding Use of American Society of Mechanical Engineering Code, Section XI, 2004 Edition Project stage: Approval 2010-02-01
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Category:Code Relief or Alternative
MONTHYEARML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML22201A5082022-07-28028 July 2022 Authorization and Safety Evaluation for Alternative Request No. IR-04-09 ML21284A0062021-10-29029 October 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-04 and IR-4-02 ML21174A0202021-08-0202 August 2021 Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML21167A3552021-07-16016 July 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-06 ML20312A0012020-12-10010 December 2020 Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML20312A0022020-12-10010 December 2020 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0027 Through L-2020-LLR-0032) ML20287A4712020-10-20020 October 2020 Proposed Alternative RR-05-05 to the Requirements of the ASME Code Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20189A2062020-07-16016 July 2020 Relief Request IR-4-03 Concerning Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping ML20080K5082020-03-24024 March 2020 Alternative Request RR-05-03 for the Fifth 10-Year Inservice Inspection Interval ML19340A0012019-12-18018 December 2019 Proposed Alternative Request IR-4-01 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML19338G3722019-12-18018 December 2019 Alternative Requests RR-05-01 and RR-05-02 for the Fifth 10-Year Inservice Inspection Interval ML19340A0002019-12-13013 December 2019 Relief Request IR-3-39, Proposed Alternative to ASME Code Weld Preheat Requirements ML19275D2522019-09-24024 September 2019 Alternative Request RR-05-03, Extension of ASME Code Case N-770-2 Volumetric Inspection Frequency for Reactor Coolant Pump Inlet and Outlet Nozzle Dissimilar Metal Butt Welds ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML18290A6022018-11-13013 November 2018 Alternative Requests Related to the Fifth and Fourth 10-Year Interval Pump, Valve, and Snubber Inservice Testing Programs, Respectively (EPID L-2018-LLR- 0012 Through EPID L-2018-LLR-0022) ML18252A0032018-09-17017 September 2018 Alternative Requests RR-04-27 and IR-3-38 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML18066A5222018-02-28028 February 2018 Proposed Alternative Requests RR-04-27 and IR-3-38 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography in Accordance with 10 CFR 50.55(z)(1) ML17132A1872017-05-25025 May 2017 Alternative Relief Requests RR-04-24 and IR-3-30: Reactor Pressure Vessel Threads in Flange ML17135A2962017-05-25025 May 2017 Alternative Relief Request RR-04-25 Boric Acid Pump P-19B Stuffing Box Cover ML17122A3742017-05-0303 May 2017 Alternative Relief Request RR-04-26 Boric Acid Pump P-19B Stuffing Box Cover ML17125A2522017-04-28028 April 2017 ASME Section XI Relief Request RR-04-26 ML17090A1102017-03-29029 March 2017 ASME Section XI Relief Request RR-04-25 ML16363A0892017-01-23023 January 2017 Alternative Relief RR-04-23 and IR-3-28 from the Requirements of ASME Code Section XI Regarding Radiographic Examinations ML16277A6782016-10-18018 October 2016 Alternative Request RR-04-22 to Implement Extended Reactor Vessel Inservice Inspection Interval ML16172A1352016-07-13013 July 2016 Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML16038A0012016-02-16016 February 2016 Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel Inservice Inspection Interval ML15257A0052015-09-21021 September 2015 Relief from the Requirements of ASME Code Section XI Regarding Radiographic Examinations ML15216A3632015-07-30030 July 2015 ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval ML15216A3592015-07-30030 July 2015 ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval ML15082A4092015-04-24024 April 2015 Alternative Use of Weld Overlay as Repair and Mitigation Technique ML14217A2032014-09-0404 September 2014 Relief from the Requirements of the ASME Code Section XI, Requirements for Repair/Replacement of Class 3 Service Water Valves (Tac No. MF1314) ML14163A5862014-07-10010 July 2014 Relief from the Inservice Testing Requirements of American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML14091A9732014-04-0404 April 2014 Issuance of Relief Request RR-04-16 Regarding Use of Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML1130001002011-11-0909 November 2011 Issuance of Relief Request RR-04-12 Regarding the Temporary Non-Code Compliant Condition of the Class 3 Service Water System 10 Inch Emergency Diesel Generator Supply Piping Flange ML11234A0772011-08-19019 August 2011 Relief Request RR-04-12 for the Temporary Non-Code Compliant Condition of the Class 3 Service Water System 10 Inch Emergency Diesel Generator Supply Piping Flange ML1118810292011-07-27027 July 2011 Issuance of Relief Request RR-04-04 Regarding Use of Alternative Pressure Testing Requirements ML1118706002011-07-22022 July 2011 Issuance of Relief Request RR-04-05 Regarding Use of Alternative Pressure Testing Requirements ML1106800802011-03-24024 March 2011 Issuance of Relief Request lR-3-14 -- Use of Risk-Informed Inservice Inspection Program Plan ML1014700992010-06-11011 June 2010 Issuance of Relief Request IR-3-05 Regarding Use of American Society of Mechanical Engineering Code, Section XI, Appendix Viii ML1012412192010-05-13013 May 2010 Relief Request IR-3-02 Regarding Use of American Society of Mechanical Engineering Code, Section XI, 2004 Edition ML1010400422010-04-29029 April 2010 Issuance of Relief Request lR-3-11 Regarding Use of American Society of Mechanical Engineering Code, Section XI, 2004 Edition ML0935702372010-04-26026 April 2010 Issuance of Relief Request RR-89-67 Regarding the Repair of Reactor Coolant Pump Seal Cooler Return Tubing and Weld ML1011301872010-04-19019 April 2010 ASME Section XI Inservice Inspection Program Relief Request for Limited Coverage Examinations Performed in the Second 10-Year Inspection Interval ML1008407382010-04-15015 April 2010 Issuance of Relief Requests IR-3-13 Regarding Use of American Society of Mechanical Engineering Code, Section XI, 2004 Edition ML1006801182010-04-0606 April 2010 Issuance of Relief Request IR-3-01 Regarding Use of American Society of Mechanical Engineering Code, Section XI, Appendix Viii ML1009002002010-03-30030 March 2010 Relief Requests RR-04-02, Alternative VT-2 Pressure Testing Requirements for the Lower Portion of the Reactor Pressure Vessel, and RR-04-03, Alternative Evaluation Criteria for Code Case N-513-2, Temporary Acceptance of Flaws In.. ML1006404462010-03-12012 March 2010 Issuance Relief ML1005402202010-02-19019 February 2010 Relief Request IR-3-01 Supplemental Information Re Snubber Inspection and Testing for Third 10-Year Interval ML0923901412009-08-24024 August 2009 Relief Request for Millstone Power Station, Unit 3, Relief Request IR-3-04, Response to Request for Additional Information for Alternative Brazed Joint Assessment Methodology 2023-07-31
[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
[Table view] Category:Safety Evaluation
MONTHYEARML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23058A4542023-03-16016 March 2023 Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22201A5082022-07-28028 July 2022 Authorization and Safety Evaluation for Alternative Request No. IR-04-09 ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22039A3392022-03-0303 March 2022 Request for Alternative Frequency to Supplemental Valve Position Verification Testing Requirements in the Fourth 10-year Valve Inservice Testing Program ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML22007A1512022-02-16016 February 2022 Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements ML21326A0992022-01-0707 January 2022 Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21262A0012021-11-0909 November 2021 Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate ML21284A0062021-10-29029 October 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-04 and IR-4-02 ML21227A0002021-10-0505 October 2021 Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident ML21222A2302021-09-0909 September 2021 Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227) ML21174A0202021-08-0202 August 2021 Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML21167A3552021-07-16016 July 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-06 ML21167A2112021-06-30030 June 2021 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0081 Through L-2020-LLR-0088) ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML21043A1622021-03-25025 March 2021 Issuance of Amendment No. 278 Regarding Revision to Battery Surveillance Requirements ML21026A1422021-02-23023 February 2021 Issuance of Amendment No. 342 Revision to Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20312A0022020-12-10010 December 2020 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0027 Through L-2020-LLR-0032) ML20312A0012020-12-10010 December 2020 Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML20287A4712020-10-20020 October 2020 Proposed Alternative RR-05-05 to the Requirements of the ASME Code Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20252A0072020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML20189A2062020-07-16016 July 2020 Relief Request IR-4-03 Concerning Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping ML20161A0002020-07-15015 July 2020 Issuance of Amendment No. 276 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML20140A3692020-06-24024 June 2020 Issuance of Amendment No. 339 Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time ML20080K5082020-03-24024 March 2020 Alternative Request RR-05-03 for the Fifth 10-Year Inservice Inspection Interval ML19340A0252020-01-30030 January 2020 Issuance of Amendment No. 337 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19338G3722019-12-18018 December 2019 Alternative Requests RR-05-01 and RR-05-02 for the Fifth 10-Year Inservice Inspection Interval ML19340A0012019-12-18018 December 2019 Proposed Alternative Request IR-4-01 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML19340A0002019-12-13013 December 2019 Relief Request IR-3-39, Proposed Alternative to ASME Code Weld Preheat Requirements ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18290A6022018-11-13013 November 2018 Alternative Requests Related to the Fifth and Fourth 10-Year Interval Pump, Valve, and Snubber Inservice Testing Programs, Respectively (EPID L-2018-LLR- 0012 Through EPID L-2018-LLR-0022) ML18275A0122018-10-0404 October 2018 Alternative Request P-06 for the 'C' Charging Pump Test Frequency ML18246A0072018-09-25025 September 2018 Issuance of Amendment No. 335 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML18252A0032018-09-17017 September 2018 Alternative Requests RR-04-27 and IR-3-38 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML18225A0202018-08-29029 August 2018 ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80 ML18038B2002018-02-26026 February 2018 Issuance of Amendment Nos. 118, 334, and 271 to Revise Licensee'S Name (CAC Nos. MF9844, MF9845, and MF9848; EPID L-2017-LLA-0245 and EPID L-2017-LLA-0346) 2024-01-12
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 April 15, 2010 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO.3-ISSUANCE OF RELIEF REQUESTS IR-3-13 REGARDING USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERING CODE, SECTION XI, 2004 EDITION (TAC NO. ME2125)
Dear Mr. Heacock:
By letter dated August 19, 2009, and supplemented by letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML092370296 and ML100330149, respectively), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) requested relief from certain examination requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2004 Edition, no Addenda. The February 1,2010, letter contained Revision 1 to Relief Request IR-3-13, which superseded IR-3-13 in its entirety. IR-3-13, Revision 1, proposes the use of alternative dissimilar metal weld examination depth-sizing requirements at Millstone Power Station, Unit NO.3 (MPS3).
The results of the Nuclear Regulatory Commission (NRC) staff's review, as contained in the enclosed safety evaluation, indicate that the use of alternative dissimilar metal weld examination depth-sizing requirements provide an acceptable level of quality and safety.
Therefore, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(ii), the NRC authorizes the use of alternate dissimal metal weld examination depth sizing requirements for the remainder of the third 1O-year inservice inspection (lSI) interval at MPS3. The third 10-year lSI interval for MPS3 began on April 23, 2009, and is scheduled to be completed on April 22, 2019.
All other ASME Code,Section XI requirements for which relief has not been specifically requested and approved remain applicable, including a third party review by the Authorized Nuclear Inservice Inspector.
D. Heacock -2 If you have any questions, please contact the Project Manager, Carleen Sanders, at 301-415-1603.
Sincerely, V~h~ Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc wi encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST IR-3-13 FOR THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT NO.3 DOCKET NUMBER 50-423
1.0 INTRODUCTION
By letter dated August 19, 2009, and supplemented by letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML092370296 and ML100330149, respectively), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) requested relief from certain examination requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2004 Edition, no addenda. The February 1, 2010, letter contained Revision 1 to Relief Request IR-3-13, which supersedes IR-3-13 in its entirety. IR-3-13, Revision 1, proposes the use of alternative dissimilar metal weld examination depth-sizing requirements at Millstone Power Station, Unit NO.3 (MPS3). This relief is requested pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.55a(a)(3)(i).
The third 10-year inservice inspection (lSI) interval began on April 23,2009 and ends on April 22, 2019.
2.0 REGULATORY REQUIREMENTS The lSI of the ASME Code Class 1, 2, and 3 components is performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i). 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the licensee demonstrates that:
(i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Enclosure
-2 Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre service examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
The ASME Code of Record for the MPS3 third 10-year lSI interval is the 2004 Edition with no Addenda of Section XI of the ASME Code. In addition, as required by 10 CFR 50.55a(b )(2)(xv),
ASME Code,Section XI, 2001 Edition with no Addenda is used for Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems.
The regulatory requirements in 10 CFR 50.55a(g)(6)(ii)(E) define the requirements for reactor coolant pressure boundary bare metal visual inspections. All licensees of pressurized water reactors (PWR) plants shall augment their lSI program by implementing ASME Code Case N-722 subject to the conditions specified in paragraphs 10 CFR 50.55a(g)(6)(ii)(E)(2) through (4).
3.0 TECHNICAL EVALUATION
3.1 Applicable Code Edition and Addenda The Code of Record for the third 10-year lSI program at MPS3 is the ASME Code,Section XI, 2004 Edition with no Addenda. In addition, volumetric examinations are to be conducted in accordance with the 2001 Edition with no Addenda of the ASME Code,Section XI, Appendix VIII, Supplement 10.
3.2 Components for Which Relief is Requested Code Class: Class 1 System: Reactor Coolant System Examination Categories: N/A Code Item Numbers: ASME Code,Section XI, Code Case N-722 B15.90 for Hot Leg Nozzle Welds B15.95 for Cold Leg Nozzle Welds
-3 I
I Weld Identification Number I' Internal j Diameter Wall Thickness (inches) l I (inches) 11301-121-A Inlet Nozzle-to-Safe End (RC Loop 3) 1--2-7-.5--'-----2-.3-2-----1 301-121-B Inlet Nozzle-to-Safe End (RC Loop 4) 27.5 2.32
!301-121-C Inlet Nozzle-to-Safe End (RC Loop'"1-)1--2~-*-1--*_-2-.3-2------1 I . I 1301-121-0 Inlet Nozzle-to-Safe End (RC Loop 2) [
!302-121-A Outlet NozZl'e-to-Safe End (RC Loop 3)r-*-zg-..
27.5
--r---**----.. .*2A5.. --***-..*** ..-*j 2.32 1302-121-B Outlet Nozzle-to-Safe End (RC Loop 4) I . 29 1 2.45 j 1302-12..1-C{)u . . tletNozzle-to-Safe End (R.C LOOP. 1.
1302-121-0 Outlet Nozzle-to-Safe End (RCLOQP*'2r-*-29-..
)1 29 I. . _*2A5
_*T---**.... 2.45 J J
lMaterials: Nozzle is S~~.08 Cla~~ ..~~~~fe Endj~_~A*182.~316,.and weld metal is Alloy 82/182 I 3.3 Applicable Code Requirement 10 CFR 50.55a mandates the use of Code Case N-722, "Additional Examinations for Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 MaterialsSection XI, Division 1." Code Case N-722 requires bare metal visual examinations of the welds on the outside surface at varying frequencies. Code Case N-722, Table 1, Note 5 allows ultrasonic examination, performed from the inside or outside surface, in lieu of the visual examination. For IVIPS3, bare metal visual examination of the welds is extremely difficult to perform, therefore, MPS3 will volumetrically examine these welds with ultrasonic testing (UT). The UT examinations of the welds will be performed from the inside surface in accordance with the performance demonstration requirements of the ASME Code, 2001 Edition with no Addenda,Section XI, Appendix VIII, Supplement 10 as they pertain to Table IWB-2500-1, Examination Category B-F welds. Application of UT requirements specifies a demonstrated Root Mean Square Error (RMSE) of 0.125 inches if depth sizing is used. Code Case N-722, Table 1, Note 5 requires the hot leg nozzle-to-safe end welds are be examined every refueling outage.
MPS3 relief request IR-3-10 authorizes an alternate examination frequency for these welds of every other refueling outage.
Code Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, Division I," which has been approved by the NRC staff in Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 15, provides an alternative to the Appendix VIII, Supplement 10 qualification requirements for dissimilar metal piping welds. Paragraph 3.3(c) indicates that "[e]xamination procedures, equipment, and personnel are qualified for depth-sizing when the RMSE of the flaw depth measurements, as compared to the true flaw depths, does not exceed 0.125 in. [inches] (3 mm)."
-4 3.4 DNC Proposed Alternative and Basis for Use The licensee stated that a request for relief from the required RMSE in depth sizing is needed because, to date, although qualified for detection and length sizing on these welds, examination vendors have not been able to meet the established RMSE of 0.125 inch for depth sizing when ultrasonic examinations are performed from the inside surface of the pipe. To date, the licensee has not chosen an examination vendor for the UT of the reactor vessel dissimilar metal nozzle to-safe end welds. However, the licensee's examination vendor will be chosen from the available vendors that have demonstrated their ability to meet the depth-sizing qualification requirement with a RMSE of no greater than 0.224 inches.
The licensee proposes to use the maximum RMSE values that have been demonstrated and approved previously for other licensees. The licensee states that in the event an indication is detected that requires depth sizing, the difference between the required RMSE and the demonstrated RMSE of the selected vendor will be added to the measured through-wall extent for comparison with applicable acceptance criteria.
3.5 Duration of Proposed Alternative The proposed alternative is requested for the remainder of the third 10-year lSI interval for MPS3, which began on April 23, 2009, and ends on April 22, 2019.
4.0 STAFF EVALUATION ASME Code,Section XI, Code Case N-695 is referenced in the licensee's lSI program and has been approved by the NRC staff per Regulatory Guide 1.147, Revision 15. ASME Code,Section XI, Appendix VIII, Supplement 10 and Code Case N-695 require that examination procedures, equipment, and personnel be qualified for depth-sizing such that the RMSE of the flaw depth measurements, as compared to true depths, do not exceed 0.125 inch.
The nuclear industry is in the process of qualifying personnel to Appendix VIII, Supplement 10/Code Case N-695 requirements, as implemented through industry's Performance Demonstration Initiative (POI) Program which is managed by the Electric Power Research Institute (EPRI). However, for ultrasonic examinations performed from the inside surface of a pipe weld, personnel have been unsuccessful at achieving the ASME Code-required 0.125 inch RMSE flaw depth sizing criterion. The NRC staff acknowledges that achieving the 0.125 inch RMSE is not feasible at this time. Although the licensee has not chosen an examination vendor, they propose to choose an examination vendor from the available vendors that have demonstrated their ability to meet the depth-sizing qualification requirement with an RMSE of no greater than 0.224 inches instead of the required 0.125 inches. In the event an indication is detected that requires depth sizing, the difference between the required RMSE and the demonstrated RMSE will be added to the measured through-wall extent. The maximum possible difference between the required RMSE and the demonstrated RMSE is
=
0.224 inches - 0.125 inches 0.099 inches. This total flaw depth will then be assessed against the applicable acceptance criteria specified in Section IWB-3600 of the ASME Code for flaw evaluation.
-5 The NRC staff finds that compliance with the ASME Code-required RMSE value is not feasible at this time. Also, the NRC staff finds that the licensee's proposed alternative of adding the difference between the ASME Code-required RMSE and the demonstrated RMSE to the measured through-wall extent, in addition to the use of the acceptance standards specified in Section IWB-3600 of the ASME Code, provide an acceptable level of quality and safety.
5.0 CONCLUSION
Based on the above review, the NRC staff has determined that requiring the licensee to qualify procedures, personnel, and equipment to meet the maximum error of 0.125 inch RMSE for crack depth sizing is not feasible at the present time. The licensee's proposal of adding the difference between the ASME Code-required RMSE and the demonstrated RMSE to the measured through-wall extent, in addition to the use of the acceptance standards specified in Section IWB-3600 of the ASME Code, provides an acceptable level of quality and safety.
Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for the remainder of the MPS3 third 10-year lSI interval.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved by the NRC staff remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: C. Nove Date: April 15, 2010
D. Heacock -2 If you have any questions, please contact the Project Manager, Carleen Sanders, at 301-415-1603.
Sincerely, Ira! (REnnis for)
Harold Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
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DATE 4/12/10 4/7110 03/01/2010 4/15/10 OFFICAL RECORD COpy