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MONTHYEARML0806601082008-03-0505 March 2008 Supplemental Information Regarding Stretch Power Uprate License Amendment Request Project stage: Supplement ML0820010972008-08-0808 August 2008 Unit 3 - Request for Additional Information Regarding the Spent Fuel Pool Criticality Project stage: RAI ML0827701132008-09-30030 September 2008 Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request Project stage: Response to RAI ML0901402272009-02-0202 February 2009 Request for Additional Information Regarding the Spent Fuel Pool Criticality Amendment Request Project stage: RAI ML0900705162009-02-0303 February 2009 Request for Withholding Information from Pubic Disclosure Regarding Millstone Power Station, Unit No. 3 Project stage: Withholding Request Acceptance ML0919105142009-07-21021 July 2009 Spent Fuel Pool Criticality Amendment Request Schedule Project stage: Other ML0921803392009-08-0606 August 2009 Documents Referenced in July 21, 2009 Letter Project stage: Other ML1002004902010-01-26026 January 2010 Request for Additional Information Regarding Spent Pool Criticality Amendment Request Project stage: RAI ML1002700742010-01-27027 January 2010 Notice of Meeting with Dominion Nuclear Connecticut, Inc. to Discuss Responses to the Millstone Power Station, Unit No. 3 Spent Fuel Pool Criticality License Amendment Request for Additional Information Project stage: RAI ML1006101042010-03-0101 March 2010 Response to Request for Additional Information Questions 26, 27 & 29 Re Spent Fuel Pool Criticality License Amendment Request Project stage: Response to RAI ML1006403432010-03-0505 March 2010 Response to Questions 28 and 30 of Request for Additional Information Regarding a Spent Fuel Pool Criticality License Amendment Request Project stage: Request ML1007601162010-03-17017 March 2010 Summary of Meeting with DNC to Discuss Responses to the Request for Additional Information Regarding MPS3 Spent Fuel Pool Criticality License Amendment Request Project stage: RAI ML1007500242010-03-26026 March 2010 Issuance of Amendment Spent Fuel Pool Criticality Project stage: Approval 2009-08-06
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Category:Letter
MONTHYEARIR 05000245/20240012024-11-12012 November 2024 Safstor Inspection Report 05000245/2024001 ML24317A2562024-11-12012 November 2024 Core Operating Limits Report, Gycle 30 IR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report 2024-09-04
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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.3 - SPENT FUEL POOL CRITICIALITY AMENDMENT REQUEST SCHEDULE (TAC NO. MD8251)
Dear Mr. Heacock:
By letter dated July 13, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072000386), Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request for a stretch power uprate (SPU) of Millstone Power Station, Unit NO.3 (MPS3). Included in a supplement dated July 13, 2007 (ADAMS Accession No. ML072000281), was a request to amend the MPS3 spent fuel pool (SFP) storage requirements.
By letter dated March 5, 2008 (ADAMS Accession No. ML080660108), DNC separated the MPS3 SFP storage requirements request from the MPS3 SPU request.
Based on the March 5, 2008, letter the Nuclear Regulatory Commission staff separated DNC's request to amend the MPS3 SFP storage requirements from the SPU request. The schedule for the SFP storage requirements was developed based on the March 5, 2008 date.
TAC No. MD8251 was initiated on this date to track this work activity.
If you have any questions, please contact me at (301) 415-1603.
Carleen J. nders, Project Manager Plant Lice si g Branch 1-2 Division of perating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 cc: Distribution via Listserv
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.3 - SPENT FUEL POOL CRITICIALITY AMENDMENT REQUEST SCHEDULE (TAC NO. MD8251)
Dear Mr. Heacock:
By letter dated July 13, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072000386), Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request for a stretch power uprate (SPU) of Millstone Power Station, Unit NO.3 (MPS3). Included in a supplement dated JUly 13, 2007 (ADAMS Accession No. ML072000281), was a request to amend the MPS3 spent fuel pool (SFP) storage requirements.
By letter dated March 5, 2008 (ADAMS Accession No. ML080660108), DNC separated the MPS3 SFP storage requirements request from the MPS3 SPU request.
Based on the March 5, 2008, letter the Nuclear Regulatory Commission staff separated DNC's request to amend the MPS3 SFP storage requirements from the SPU request. The schedule for the SFP storage requirements was developed based on the March 5, 2008 date.
TAC No. MD8251 was initiated on this date to track this work activity.
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. 50-423 cc: Distribution via Listserv Distribution:
Public LPL1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrPMCSanders Resource RidsNrr LAABaxter Resource RidsRgn1 MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource ADAMS Accession number: ML091910514 OFFICE LPL 1-2/PM LPL1-2/LA LPL1-2/BC NAME CSanders ABaxter (SLittle for) HChernoff (RBEnnis)
DATE 7/20/09 7/15/09 7/21/09 Official Record Copy