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MONTHYEARML0805005192008-02-18018 February 2008 Response to Request for Additional Information on the Use of Alternative Examination Technique of Select Class 1 Piping Dissimilar Metal Welds (Request No. RR-89-64) Project stage: Response to RAI ML0807101012008-03-14014 March 2008 Request for Additional Information Regarding Examination Technique of Select Class 1 Piping Dissimilar Metal Welds Project stage: RAI ML0808605892008-03-26026 March 2008 Response to Request for Additional Information on the Use of Alternative Examination Technique of Select Class 1 Piping Dissimilar Metal Welds (Request No. RR-89-64) Project stage: Response to RAI ML0816504542008-06-13013 June 2008 Summary of Reactor Coolant Pump Dissimilar Metal Weld Examinations Project stage: Request ML0821704342008-09-0909 September 2008 Issuance of Relief Request Regarding Alternative Request RR-89-64 for Use of a Limited One-Sided Ultrasonic Examination Technique Project stage: Approval 2008-03-26
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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
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Dominion Nuclear Connecticut, Inc.
'000 Dominion Boulevard, Glen Allen, Virginia 21060
\X'd, Address: www.dom.com March 26, 2008 U. S. Nuclear Regulatory Commission Serial No.: 08-0047A Attention: Document Control Desk NSSLIMAE R1 One White Flint North Docket No.: 50-336 11555 Rockville Pike License No.: DPR-65 Rockville, Maryland 20852-2738 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON THE USE OF ALTERNATIVE EXAMINATION TECHNIQUE OF SELECT CLASS 1 PIPING DISSIMILAR METAL WELDS (REQUEST NO. RR-89-64, TAC NO. MD6911)
In a letter dated September 27, 2007, Dominion Nuclear Connecticut, Inc. (DNC) submitted Millstone Power Station Unit 2 Alternative Request RR-89-64. DNC requested Nuclear Regulatory Commission (NRC) approval of an alternative to use a limited, one-sided ultrasonic examination technique for eight 36-inch outside diameter welds. These welds are located on the reactor coolant system cold leg and are dissimilar metal welds with cast austenitic stainless steel safe ends that are welded with Alloy 82/182 material.
On January 30, 2008, the NRC issued a request for additional information (RAI) containing nine questions related to the DNC request. DNC letter dated February 18, 2008 provided a response to the questions. Subsequently, the NRC issued an additional question on February 28, 2008. A response to the additional question is provided in the attachment to this letter. The response is consistent with the information discussed in a telephone conference with the NRC staff on March 10, 2008.
Should you have further questions, please contact Margaret Earle at (804) 273-2768.
Sincerely,
>(Y;J-({7f Leslie Hartz { /
Vice President - Nuclear Support Services Commitments in this letter: None Attachment
Serial No. 08-0047A Docket No. 50-336 Response to RAI on RR-89-64 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. D. Hughey Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-883 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No. 08-0047A Docket No. 50-336 ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON THE USE OF ALTERNATIVE EXAMINATION TECHNIQUE OF SELECT CLASS 1 PIPING DISSIMILAR METAL WELDS (REQUEST NO. RR-89-64, TAC NO. MD6911)
MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No. 08-0047A Docket No. 50-336 Response to RAI on RR-89-64 Attachment Page 1 of 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON THE USE OF ALTERNATIVE EXAMINATION TECHNIQUE OF SELECT CLASS 1 PIPING DISSIMILAR METAL WELDS (REQUEST NO. RR-89-64, TAC NO. MD6911)
NRC QUESTION:
In EPRI report IR-2007-277, EPRI provided estimated coverage for the 7 welds in Alternative Request RR-89-64 but not weld P-8-C-1. Please provide the estimated ultrasonic examination coverage for weld P-8-C-1.
RESPONSE
The EPRI report does not contain field data for the specific nozzle P-8-C-1. Accordingly, the report does not include an estimate of the examination coverage expected to be obtained in 2R18 for the P-8-C-1 nozzle, or provide its photograph and detailed sketches of the weld profiles.
DNC performed a profile observation of the P-8-C-1 nozzle welds during refueling outage 2R17 in the fall of 2006 in planning for the use of this alternative examination. This profile observation was performed subsequent to commissioning of the EPRI report. Based upon the profile observation in 2R17, the component information of Table 3-1 in the EPRI report remains applicable to the P-8-C-1 nozzle. The design and weld profiles of the four inlet nozzles are comparable and Table 3-1 of the EPRI report that provides component information is also applicable to the P-8-C-1 nozzle. The assessment of estimated coverage shown by the report on the other three inlet nozzles P-4-C-1, P-13-C-1 and P-17-C-1 are representative of the capability of the examination technique to be used on the P-8-C-1 nozzle. DNC reviewed the available weld profiles of the P-8-C-1 nozzle and determined that coverage shown for the P-4-C-1 nozzle in the EPRI report can be applied as an estimate for the P-8-C-1 nozzle coverage assessment. Additionally, the observations and recommendations of Section 3.3 of the EPRI report remain applicable to the P-8-C-1 nozzle.