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MONTHYEARML0830903962008-10-24024 October 2008 End of Cycle 18 Steam Generator Tube Inspection Report Project stage: Request ML0907503752009-04-13013 April 2009 Review of Steam Generator Tube Inspection Report for 2008 Refueling Outage Project stage: Approval ML0915402032009-05-20020 May 2009 Response to Request for Additional Information 2008 Steam Generator Tube Inspections Project stage: Response to RAI ML0919103652009-07-21021 July 2009 Nuclear Regulatory Commission Staff Review of the 2008 Steam Generator Tube Inspections Project stage: Approval 2009-04-13
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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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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2009 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.2 - NUCLEAR REGULATORY COMMISSION (NRC) STAFF REVIEW OF THE 2008 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. ME0094)
Dear Mr. Heacock:
By letters dated October 24, 2008, and May 20, 2009 (Agencywide Document Access and Management System Accession Nos. ML083090396 and ML091540203, respectively),
Dominion Nuclear Connecticut, Inc., (DNC or the licensee) submitted information pertaining to the 2008 steam generator tube inspections performed at Millstone Power Station, Unit 2 (MPS2) during the cycle 18 refueling outage.
The NRC staff has reviewed the information DNC provided and concludes that DNC has provided the information required by the MPS2 Technical Specifications and that no additional follow-up is required at this time. The NRC staff's review is enclosed. This closes TAC No. ME0094.
If you have any questions, please contact me at 301-415-1603.
Sit;, ,~L Carleen J. San , Project Manager Plant Licensing nch 1-2 Division of Opera Ing Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
As stated cc w/encl: Distribution via Listserv
REVIEW OF 2008 STEAM GENERATOR TUBE INSPECTIONS MILLSTONE POWER STATION, UNIT NO.2 DOCKET NO. 50-336 By letters dated October 24, 2008, and May 20, 2009 (Agencywide Document Access and Management System Accession Nos. ML083090396 and ML091540203, respectively),
Dominion Nuclear Connecticut, Inc., (DNC or the licensee) submitted information pertaining to the 2008 steam generator (SG) tube inspections performed at Millstone Power Station, Unit NO.2 (MPS2) during the cycle 18 refueling outage.
MPS2, has two SGs, each one contains approximately 8,523 thermally treated Alloy 690 tubes.
Each tube has a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.0445 inches. The tubes were hydraulically expanded at both ends for the full depth of the tubesheet. The tubes are supported by type 410 stainless steel lattice grids.
DNC provided the scope, extent, methods, and results of their SG tube inspections in the October 24, 2008, and May 20, 2009, letters. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
Based on its review of DNC's submittals, the U.S. Nuclear Regulatory Commission (NRC) staff has the following observations and comments:
- As of the 2008 refueling outage, the SGs had operated for approximately 117 effective full-power months (EFPM). The SGs have operated for approximately 101 EFPM in their 144 EFPM sequential period.
- There are no tubes in close proximity to each other.
- There is one tube in SG 1 that was only partially expanded into the tubesheet. The tube is not expanded for approximately 10 inches near the top of the tubesheet.
Based on a review of the information provided, the NRC staff concludes that DNC provided the information required by the MPS2 Technical Specifications. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure
JUly 21,2009 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 SUB"IECT: MILLSTONE POWER STATION, UNIT NO.2 - NUCLEAR REGULATORY COMMISSION (NRC) STAFF REVIEW OF THE 2008 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. ME0094)
Dear Mr. Heacock:
By letters dated October 24, 2008, and May 20, 2009 (Agencywide Document Access and Management System Accession Nos. ML083090396 and ML091540203, respectively),
Dominion Nuclear Connecticut, Inc., (DNC or the licensee) submitted information pertaining to the 2008 steam generator tube inspections performed at Millstone Power Station, Unit 2 (MPS2) during the cycle 18 refueling outage.
The NRC staff has reviewed the information DNC provided and concludes that DNC has provided the information required by the MPS2 Technical Specifications and that no additional follow-up is required at this time. The NRC staff's review is enclosed. This closes TAC No. ME0094.
If you have any questions, please contact me at 301-415-1603.
Sincerely, Ira!
Carleen J. Sanders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL 1-2 rlf RidsNrrDorlLpl1-2 Resource RidsNrrPMCSanders Resource RidsNrrLAABaxter Resource RidsOgcRp Resource RidsAcrsAcnw_MailCenter Resource RidsRgn1 MailCenter Resource RidsNrrDorlDciCsgb Reource K. Karwoski, NRRlDCI/CSGB ADAMS Accession N0.: ML091910365 *B memo dated OFFICE LPL1-2/PM LPL 1-2/LA DCI/CSGB LPL 1-2/BC NAME CSanders ABaxter (SLittie for) MGavrilas HChernoff (RBEnnis for)
DATE 7/20109 7/5109 06124/2009* 7121109 Official Record Copy