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MONTHYEARML1032300042010-11-18018 November 2010 Withdrawal of Alternative Request IR-3-12 for the Use of ASME Code Case N-513-2 Project stage: Withdrawal ML1032303802010-11-22022 November 2010 Withdrawal of Relief Request IR-3-12 Regarding the Use of American Society of Mechanical Engineering Code Case N-513-2 Project stage: Withdrawal 2010-11-18
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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 November 22, 2010 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.3 - WITHDRAWAL OF RELIEF REQUEST IR-3-12 REGARDING THE USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERING CODE CASE N-513-2 (TAC NO. ME3932)
Dear Mr. Heacock:
By letter dated May 28, 2009 (Agencywide Document Access and Management System (ADAMS) Accession No. ML101380042), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted relief request IR-3-12 for Millstone Power Station, Unit NO.3 (IVIPS3). The proposed relief request would allow DNC to use American Society of Mechanical Engineers (ASME) Code Case N-513-2 during the third 1O-year inservice inspection interval at MPS3. The 2004 Edition of ASME Section XI is the Code of Record for the third 1O-year inservice inspection interval at MPS3.
Code Case N-513-2 was approved for use by the NRC in Regulatory Guide (RG) 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1;"
however, Code Case N-513-2 is only applicable for the ASIVIE Code 1983 Edition with the Winter 1985 Addenda through the 2001 Edition with the 2003 Addenda. Code Case N-513-2 allows for the temporary acceptance of flaws in moderate energy Class 2 or 3 piping. The NRC issued RG 1.147, Revision 16, in October 2010, approving the use of ASME Code Case N-513-3. Code Case N-513-3 supersedes Code Case N-513-2 and is applicable for the ASME Code 1983 Edition with the Winter 1985 Addenda, through the 2007 Edition with the 2008 Addenda. Subsequently, by letter dated November 18,2010 (ADAMS Accession No.
ML103230004), DNC withdrew relief request IR-3-12 because it is no longer needed.
The purpose of this letter is to advise that the above-cited request is being treated as withdrawn and TAC No. ME3932 will be closed.
If you have any questions, please contact me at 301-415-1603.
Si.* ~cerelr'* ~
\[J \\ \n.'~r -
c~een~\ Sand ,Project Manager Plant Li er\!sing Branch 1-2 Division' Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 cc: Distribution via Listserv
November 22,2010 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.3 - WITHDRAWAL OF RELIEF REQUEST IR-3-12 REGARDING THE USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERING CODE CASE N-513-2 (TAC NO. ME3932)
Dear Mr. Heacock:
By letter dated May 28, 2009 (Agencywide Document Access and Management System (ADAMS) Accession No. ML101380042), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted relief request IR-3-12 for Millstone Power Station, Unit NO.3 (MPS3). The proposed relief request would allow DNC to use American Society of Mechanical Engineers (ASME) Code Case N-513-2 during the third 1O-year inservice inspection interval at MPS3. The 2004 Edition of ASME Section XI is the Code of Record for the third 1O-year inservice inspection interval at MPS3.
Code Case N-513-2 was approved for use by the NRC in Regulatory Guide (RG) 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1;"
however, Code Case N-513-2 is only applicable for the ASME Code 1983 Edition with the Winter 1985 Addenda through the 2001 Edition with the 2003 Addenda. Code Case N-513-2 allows for the temporary acceptance of flaws in moderate energy Class 2 or 3 piping. The NRC issued RG 1.147, Revision 16, in October 2010, approving the use of ASME Code Case N-513-3. Code Case N-513-3 supersedes Code Case N-513-2 and is applicable for the ASME Code 1983 Edition with the Winter 1985 Addenda, throuqh the 2007 Edition with the 2008 Addenda. Subsequently, by letter dated November 18, 2010 (ADAMS Accession No.
ML103230004), DNC withdrew relief request IR-3-12 because it is no longer needed.
The purpose of this letter is to advise that the above-cited request is being treated as withdrawn and TAC No. ME3932 will be closed.
If you have any questions, please contact me at 301-415-1603.
Sincerely,
/raJ Carleen J. Sanders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 cc: Distribution via Listserv Distribution:
PUBLIC Branch Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDciCpnbResource RidsNrrLAABaxter Resource RidsNrrPMMilistone Resource RidsOgcRp Resource RidsRgn1 MailCenter Resource K. Hoffman, NRR ADAMS Accession No'.. ML103230380 OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC NAME CSanders ABaxter HChernoff (w/comment)
DATE 11/22/10 11/22/10 11/22/10 OFFICAL RECORD COPY