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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]
Category:Report
MONTHYEARML23324A4222023-11-20020 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
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
ML23151A0742023-06-12012 June 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
ML23103A2282023-04-12012 April 2023
Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code
ML22353A6202022-12-19019 December 2022
Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code
ML22193A1432022-06-23023 June 2022
5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207
ML21175A2472021-06-24024 June 2021
2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....-
ML21113A1352021-04-27027 April 2021
Review of the Spring 2017 Steam Generator Tube Inspection Report
ML21042B3212021-02-11011 February 2021
Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code
ML20352A3342020-12-17017 December 2020
Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping
ML20345A3682020-12-16016 December 2020
Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports
ML20247J6162020-09-0303 September 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20171A5342020-08-13013 August 2020
Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment
ML20203M1602020-07-20020 July 2020
VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status
ML20105A0782020-04-14014 April 2020
Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components
ML19352B8982019-12-17017 December 2019
Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements
ML19246A1162019-10-0707 October 2019
Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21)
ML19249B7742019-08-29029 August 2019
Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated)
ML19249B7782019-08-29029 August 2019
Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1
ML19249B7682019-08-29029 August 2019
Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated)
ML19249B7722019-08-29029 August 2019
Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated)
ML19211B1682019-07-24024 July 2019
Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable
ML19070A2172019-04-0303 April 2019
Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation
ML19064A5902019-02-28028 February 2019
Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service
ML19011A1742019-01-0404 January 2019
Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents
ML19011A1722019-01-0404 January 2019
Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up)
ML19011A1732019-01-0404 January 2019
Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents
ML18256A2002018-10-0303 October 2018
Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (EPID L00495\05000336 L-2015-JLD-0011 and 00495\05000423\L-2015-JLD-0012)
ML18247A2752018-06-18018 June 2018
Technical Requirements Manual
ML17187A1692017-06-28028 June 2017
Mitigating Strategies Assessment (MSA) Report)
ML17108A3272017-04-0606 April 2017
Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation
ML17051A0012017-02-27027 February 2017
Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections
ML16193A6702016-06-30030 June 2016
ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015
ML15328A2682015-12-15015 December 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review
ML15275A2882015-10-19019 October 2015
Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections
ML15253A2062015-09-0101 September 2015
ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report.
ML15194A0572015-06-30030 June 2015
ISFSI - NRC Commitment Change Report for 2014
ML15078A2052015-03-12012 March 2015
to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 1 Through 2-57
ML15078A2082015-03-12012 March 2015
to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-172 Through the End
ML15078A2072015-03-12012 March 2015
to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-126 Through 2-171
ML15078A2062015-03-12012 March 2015
to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-58 Through 2-125
ML14220A0172014-07-30030 July 2014
Startup Test Report for Cycle 23
ML13338A4332014-01-31031 January 2014
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14013A2712014-01-30030 January 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML13357A3982014-01-24024 January 2014
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Milestone Power Station, Unit 2, TAC No.: MF0858
ML14006A1592014-01-0808 January 2014
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Millstone Power Station, Unit 3, TAC No.: MF0859
ML14087A0992013-10-17017 October 2013
10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure
ML13303B9072013-10-17017 October 2013
10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure
ML13192A1022013-07-18018 July 2013
Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46
2023-07-26
[Table view]
Category:Miscellaneous
MONTHYEARML23324A4302023-11-20020 November 2023
Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15
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
ML23151A0742023-06-12012 June 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
ML22353A6202022-12-19019 December 2022
Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code
ML21113A1352021-04-27027 April 2021
Review of the Spring 2017 Steam Generator Tube Inspection Report
ML20345A3682020-12-16016 December 2020
Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports
ML20247J6162020-09-0303 September 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20171A5342020-08-13013 August 2020
Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment
ML20105A0782020-04-14014 April 2020
Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components
ML19211B1682019-07-24024 July 2019
Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable
ML17187A1692017-06-28028 June 2017
Mitigating Strategies Assessment (MSA) Report)
ML17108A3272017-04-0606 April 2017
Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation
ML17051A0012017-02-27027 February 2017
Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections
ML16193A6702016-06-30030 June 2016
ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015
ML15328A2682015-12-15015 December 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review
ML15275A2882015-10-19019 October 2015
Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections
ML15194A0572015-06-30030 June 2015
ISFSI - NRC Commitment Change Report for 2014
ML14220A0172014-07-30030 July 2014
Startup Test Report for Cycle 23
ML14013A2712014-01-30030 January 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML13303B9072013-10-17017 October 2013
10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure
ML13192A1022013-07-18018 July 2013
Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML12362A3922012-11-30030 November 2012
Spent Fuel Pool Criticality Analysis with No Credit for Boraflex.
ML12353A2422012-11-27027 November 2012
Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3
ML12187A1752012-06-25025 June 2012
ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2010 and 2011, and Commitment Change Report for 2010 and 2011
ML12151A3592012-06-0707 June 2012
End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review
ML12046A8362012-01-31031 January 2012
Inservice Inspection Program - Owner'S Activity Report
ML12031A1472012-01-25025 January 2012
Day Report for Emergency Core Cooling System Model Changes of 10 CFR 50.46
ML1116002202011-06-13013 June 2011
Exhibit D (Part 3): Millstone 2001 Safstor Cost Analysis (Normal Dollars)
ML1028504382010-09-30030 September 2010
Attachments 2, 3, 5, 7, 8 & 9, to 10-579A, Westinghouse Electric Co. LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Revision 2, Dated Sep
ML1019403352010-06-30030 June 2010
Units, 1, 2, 3, & ISFSI, 10 CFR 50.59, 10 CFR 72.48 Change Report for 2008 and 2009, and the Commitment Change Report for 2009
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML1009702062010-03-29029 March 2010
Chemistry Procedure, Liquid Waste Sample Sink, Rev. 003-00
ML0931701762009-11-12012 November 2009
Part 3 of 4--Weld Overlay Examination Report 2R19
ML0931701732009-11-12012 November 2009
Part 2 of 4--Weld Overlay Examination Report 2R19
ML0931701662009-11-12012 November 2009
Part 1 of 4--Weld Overlay Examination Report 2R19
ML0931701852009-09-23023 September 2009
Part 4 of 4--Weld Overlay Examination Report 2R19
ML0921908942009-08-0404 August 2009
Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A
ML0913204602009-04-28028 April 2009
2008 Occupational Radiation Exposure Information
ML0901303822008-12-26026 December 2008
Revision 002 to CP 3804L Procedure Action Request, Pass Containment Air Sample, Dated 12/26/2008
ML0830903962008-10-24024 October 2008
End of Cycle 18 Steam Generator Tube Inspection Report
ML0827701132008-09-30030 September 2008
Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request
ML0819800752008-07-0707 July 2008
Revision to Control Room and OSC Assembly Area Building 475 1st Floor, and SAP Locker
ML0818406072008-07-0101 July 2008
Final Evaluation of Weld Overlay Examinations in Refueling Outage 18
ML0727504022007-09-27027 September 2007
Alternative Request RR-89-64 for Use of a Limited One-Sided Ultrasonic Examination Technique LBDCR 07-MP2-034
ML0720003902007-07-13013 July 2007
Attachment 1, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Descriptions, Technical Analysis and Regulatory Analysis for the Proposed Operating License and Technical Specifications Changes
ML0715203992007-05-30030 May 2007
Fy 2007 Final Fee Rule Workpapers
ML0713501882007-05-17017 May 2007
Review of Steam Generator Tube Inservice Inspection Report for the 2005 Refueling Outage at Millstone Power Station, Unit No. 2
ML0713502492007-05-0808 May 2007
Steam Generator Tube Plugging Report
ML0708805652007-03-28028 March 2007
Response to Request for Additional Information Regarding an Alternative for the Weld Overlay of Pressurizer Nozzle Welds
ML0705903272007-02-27027 February 2007
Fitness-For-Duty Program Semi-Annual Performance Data Report
2023-07-26
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