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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. lr h *
- Millstone Power Station :51 Dominion Rope Ferry Road Waterford, CT17 06385 MAY 2 2005 U. S. Nuclear Regulatory Commission Serial No.: 05-282 Attention: Document Control Desk MPS Lic/RWM Rev 0 Washington, DC 20555 Docket No.: 50-336 License No.: DPR-65 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION, UNIT 2 SPECIAL REPORT - STEAM GENERATOR TUBE INSERVICE EXAMINATION This special report is being submitted pursuant to the requirements of Plant Technical Specifications 4.4.5.1.5.a. Specification 4.4.5.1.5.a requires that a report be submitted to the commission within 15 days following completion of each inservice inspection of the steam generator tubes to document the number of tubes plugged in each generator.
Eddy current inspections, conducted at the end of cycle 16, were completed on April 25, 2005. One hundred percent of the tubes in steam generator (SG) number 1, or approximately fifty percent of the total population of tubes in all SGs, were examined.
No tubes were removed from service as a result of the examination.
The tables contained within Attachment 1 briefly summarize the number of tubes examined, types of examinations, and results. Eddy current testing (ECT) identified flaws in two tubes resulting from fan bar wear (less than 9 percent through wall). No further growth was observed since initial identification of these flaws during the refueling outage for cycle 14. Loose parts that were expected due to degradation of a condensate strainer screen have been removed from both steam generators during sludge lancing and the Foreign Object Search and Retrieval (FOSAR). No foreign material related damage was identified. The complete results of the SG tube inspection will be included in the Annual Operating Report.
If you should have any questions regarding this submittal, please contact Mr. Dave W.
Dodson at (860) 447-1719, extension 2346.
Very truly yours, J. Price Site ice President - Millstone Commitments contained within this letter: None cc: See next page
Serial No.: 05-282 Docket No.: 50-336 Special Report for SG Inspections Page 2 Attachments: Tables 1 and 2 cc: U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses Senior Project Manager, Millstone Unit 2 U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station
Serial No.: 05-282 Docket No.: 50-336 Special Report for SG Inspections ATTACHMENT 1 TABLES 1 AND 2 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)
MILLSTONE POWER STATION, UNIT 2
Serial No.: 05-282 Docket No.: 50-336 Special Report for SG Inspections Attachment 1 / Page 1 of 1 Table 1: Refueling Outage 16 Eddy Current Test Summary Number of Tubes (SG 1 Only) 8522 Number of Tubes Inspected F/L w/Bobbin Probe 8522 Number of Locations Inspected w/Rotating Probe (Total) 298
- Hot Leg Transitions - Original Scope 142
- Hot Leg Transitions - Expansion 0
- Hot Leg Misc. Special Interest - Diagnostic Exams 60
- Cold Leg Misc. Special Interest - Diagnostic Exams 82
- U-bend Misc. Special Interest - Diagnostic Exams 14 Tubes with Max Fan Bar Wear >= 40% 0 Tubes with Max Fan Bar Wear >= 20% but < 40% 0 Tubes with Max Fan Bar Wear <20% 2 Tubes Plugged 0 Tubes Sleeved 0 Table 2: Rotating Probe Diagnostic Exams from Historical and Current Indications Hot Leg Cold Leg U-bend PTE 1 0 0 PLP 2 4 0 Previous DNT/DNG 3 9 8 Indications BLG 2 0 0 OXP 19 14 0 Fan Bar Wear 0 0 1 Bobbin I-Codes 3 0 2 Refueling Bobbin PLPs 3 8 0 Outage 16 PLP Bounding and 27 46 0 Indications Resulting PLPs -
DNT/DNG 0 1 3 Total 60 82 14