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MONTHYEARML0830102332008-10-27027 October 2008 Electric Power Research Institute MRP-139 Deviation Notification Project stage: Request ML0913106662009-04-28028 April 2009 Third 10-year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Requests Project stage: Request ML0932105912009-12-10010 December 2009 Request for Additional Information Regarding Third 10-Year Interval Inservice Inspection Program Relief Request IR-3-05 Project stage: RAI ML1001905132010-01-14014 January 2010 Relief Request IR-03-05 Response to Request for Additional Information Regarding Proposed Alternative Related to Inservice Inspection of Weld Overlays for the Third 10-Year Interval Project stage: Response to RAI ML1013100062010-05-0606 May 2010 Relief Request Number IR-3-05 Supplemental Information Regarding Examination of Weld Overlays Project stage: Supplement 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 Project stage: Approval 2009-04-28
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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.
"(100 Dominion Boulevard, Glen Allen. Virginia .!\060
\\ "h :\ddress: www.dom.com October 27, 2008 U.S. Nuclear Regulatory Commission Serial No. 08-0523 Attention: Document Control Desk NLOS/GAW RO One White Flint North Docket No. 50-423 11555 Rockville Pike License No. NPF-49 Rockville, MD 20852-2738 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 ELECTRIC POWER RESEARCH INSTITUTE MRP-139 DEVIATION NOTIFICATION In accordance with the Nuclear Energy Institute (NEI) Guideline for the Management of Materials Issues (NEI 03-08, Rev 1), Dominion Nuclear Connecticut, Inc., (DNC) is providing notification of a deviation from the Electric Power Research Institute (EPRI)
Materials Reliability Program (MRP): Primary System Piping Butt Weld Inspection and Evaluation Guidelines (MRP-139). This notification is being sent consistent with the industry initiatives to provide timely communications to NRC staff regarding conformance with industry guidance. This notification is for information only and no response is requested.
The deviation relates to the mandatory visual examination requirements contained in MRP-139. Specifically, MRP-139 requires bare metal visual examination of the nozzle to safe end welds of both the inlet and outlet of the Reactor Pressure Vessel (RPV) during Millstone Power Station Unit 3 (MPS3) refueling outage 12 (3R 12) in the fall of 2008. These weld locations contain Alloy A 182 that is susceptible to primary water stress corrosion cracking (PWSCC). The required visual inspections would result in almost 30 rem dose impact. Accordingly, MPS3 has developed a basis for waiving the visual examinations while concurrently increasing volumetric inspection frequency. This strategy achieves the same objective and intent of the original MRP-139 requirement.
The technical justification demonstrates that any small flaws undetected by the volumetric ultrasonic test (UT) examinations would remain within the acceptable limits of the ASME Code for the period between qualified UT examinations. The RPV inlet and outlet nozzles were most recently inspected from the inside diameter by UT examination during the spring of 2007 3R11. No recordable indications were identified. In accordance with the alternative plan described in the deviation report to the EPRI Materials Reliability Program, the outlet nozzle will next be inspected by UT examination in the spring of 2010 3R13 and the inlet nozzle will next be inspected by UT examination in the fall of 2011 3R14. Also in accordance with the alternative plan, subsequent inspections will be performed every two refueling outages for the RPV outlet nozzle and every three refueling outages for the inlet nozzle. If the nozzle
Serial No. 08-0523 Docket No. 50-423 MRP-139 Deviation Notification Page 2 of 3 welds are mitigated to preclude PWSCC growth, the inspection plan will be modified in accordance with MRP guidance.
The technical justification for the deviation has been prepared and concurrence by an independent third party materials expert has been obtained in accordance with NEI 03-08 requirements. The deviation has been processed through the station corrective action program and is documented in plant records. It is expected that this deviation will continue while the MRP-139 requirement remains in effect, or until the locations are mitigated to prevent propagation of potential PWSCC.
If you have any questions regarding this notification, please contact Mr. Geoffrey Wertz at (804) 273-3572.
Sincerely, an Price President - Nuclear Engineering 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 Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8B3 Rockville, MD 20852-2738 Ms. T. M. Mensah, Senior Project Manager Special Projects Branch Division of Policy and Rulemaking U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-12E5 Rockville, MD 20852-2738
Serial No. 08-0523 Docket No. 50-423 MRP-139 Deviation Notification Page 3 of 3 NRC Senior Resident Inspector Millstone Power Station