Letter Sequence Request |
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MONTHYEARML0332403732003-11-0505 November 2003
Special Report - Steam Generator Tube Inservice Examination
Project stage: Request
ML0406908742004-02-26026 February 2004
Technical Specifications Annual Report
Project stage: Request
ML0515802802004-04-25025 April 2004
Request for Additional Information Regarding Millstone 2 Steam Generator Tube Inspection Reports for the 2003 Outage
Project stage: RAI
ML0426704162004-09-23023 September 2004
Response to Request for Additional Information Regarding Steam Generator Tube Inspection Summary for Fall 2003 Outage
Project stage: Response to RAI
ML0515803152004-10-0404 October 2004
Review of Millstone Unit 2 Steam Generator Tube Inspection Reports for Their 2003 Outage
Project stage: Approval
ML0430703522004-11-0909 November 2004
Review of Steam Generator Tube Inservice Inspection Report for the 2003 Refueling Outage at Millstone, Unit 2
Project stage: Approval
2004-11-09
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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] |
Text
Dominion Nuclear Connecticut, Inc.
Millstone Power Station D mno Rope Ferry Road Waterford, CT 06385 NOV 5 2JQ Docket No. 50-336 B19007 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Power Station, Unit No. 2 Special Report - Steam Generator Tube Inservice Examination This special report is being submitted pursuant to the requirements of Plant Technical Specifications 6.9.2.j and 4.4.5.1.5.a. Specification 4.4.5.1.5.a requires a special report be submitted to the commission within 15 days following completion of each steam generator tube inservice inspection, to document the number of tubes plugged.
The end of cycle 15 eddy current inspections were completed on October 25, 2003.
The inspection examined one hundred percent of the tubes in steam generator number 2, or approximately 50 percent of the total population of tubes. 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 identified flaws in two (2) tubes resulting from fan bar wear (less than 11 percent throughwall), and five (5) tubes with loose part wear or single volumetric indications (less than 24 percent throughwall). The loose parts which caused the tube damage were located below the first support plate and removed from the steam generator during the Foreign Object Search and Retrieval. The complete results of the steam generator tube inspection will be included in the Annual Operating Report, which is expected to be issued in February 2004.
There are no regulatory commitments contained within this letter.
Should you have any questions regarding this submittal, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.
Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.
J. Alan Price Site V President - Millstone cc: See next page AN -7
0
~ L U.S. Nuclear Regulatory Commission B19007/Page 2 Attachment (1) cc: H. J. Miller, Region I Administrator R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 Millstone Senior Resident Inspector
Docket No. 50-336 B19007 Attachment 1 Millstone Power Station, Unit No. 2 Steam Generator Tube Plugging 15 Day Report Tables
-. r U.S. Nuclear Regulatory Commission B19007/Attachment 1/Page 1 Millstone Power Station, Unit No. 2 Steam Generator Tube Plugcginn 15 Day Report Tables Table 1 - Millstone 2R15 ECT Summary S/G 2 Number of Tubes (S/G 2 Only) 8523 Number of Tubes Inspected F/L w/ Bobbin Probe 8523 Number of Tubes Incomplete w/ Bobbin Probe 0 Number of Tube Inspections w/ MRPC (Total) 214
. Hot Leg Transitions - Original Scope 140
- Hot Leg Transitions - Expansion 0
- Hot Leg Misc. Special Interest - Diagnostic Exams and from 56 Previous History (number of tubes)
- Cold Leg Misc. Special Interest - Diagnostic Exams and from 16 Previous History (number of tubes)
. U-bend Misc. Special Interest - Diagnostic Exams (number of 2 tubes).
Tubes with Max Fan Bar Wear 240% 0 Tubes with Max Fan Bar Wear >20% but < 40% 0 Tubes with Max Fan Bar Wear < 20% 2 Tubes with Max Volumetric Hot Leg Ž 40% 0 Tubes with Max Volumetric Hot Leg Ž220% but < 40% 3 Tubes with Max Volumetric Hot Leg < 20% 0 Tubes with Max Volumetric Cold Leg 240% 0 Tubes with Max Volumetric Cold Leg 20% but < 40% 2 Tubes with Max Volumetric Cold Leg < 20% 0 Tubes Plugged 0 Table 2 - MRPC Diagnostic Exams from History and Current Indications All Hot Leg Straight Cold Leg Straight Fan Bars -U-bend Exams Exams Exams Exams Scheduled/Tubes Scheduled/Tubes Scheduled/Tubes Scheduled/Tubes 88/74 68/56 16/16 2/2 Tubes were scheduled multiple times on the Hot Leg Programs to allow for additional information, e.g., positive identification or flaw sizing.
U.S. Nuclear Regulatory Commission B19007/Attachment 1/Page 2 Table 3 - Percent Indications (Maximum Indication per Tube)
Percent Range Hot Leg Straight Cold Leg Straight Fan Bars (U-bend) 1 -19% 0 0 2 20 - 29% 3 2 0 30-39% 0 0 0 40 -100% 0 0 0
