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| Issue date | Title | Topic | |
|---|---|---|---|
| ML24032A111 | 1 February 2024 | Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval | |
| ML24032A466 | 16 January 2024 | Response to Comments on Draft Vpdes Permit No. VA0052451 | |
| ML23214A194 | 5 September 2023 | Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information - Report | Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake |
| ML23103A228 | 12 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 | Shutdown Margin Anticipated operational occurrence Post Accident Monitoring B.5.b Exemption Request Fuel cladding Fire Protection Program |
| ML22353A620 | 19 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 | |
| ML22255A010 | 28 June 2022 | Owner'S Activity Report | Through Wall Leak |
| ML22263A285 | 23 May 2022 | Alert and Notification System Evaluation Report_Ans Evaluation_Redacted Page 1-65 | |
| ML22119A172 | 13 April 2022 | Post-Accident Monitoring (PAM) Report | Post Accident Monitoring |
| ML21333A284 | 29 November 2021 | Requal Notification Letter | Job Performance Measure |
| ML21175A247 | 24 June 2021 | 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- | |
| ML21036A077 | 23 February 2021 | Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage | |
| ML21042B321 | 11 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 | |
| ML20254A347 | 8 September 2020 | Supplement to Operator License Examination Comments | |
| ML20247J616 | 3 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 | Incorporated by reference |
| ML20246G706 | 24 August 2020 | Enclosure 4: Attachment 1 - PWROG-18005-NP, Revision 2, Determination of Unirradiated Rt and Upper-Shelf Values of the North Anna Units 1 and 2 Reactor Vessel Materials | |
| ML20203M160 | 20 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 | Anchor Darling |
| ML20149K671 | 31 May 2020 | PWROG-19047-NP, Revision 0, North Anna, Units 1 and 2, Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis | Incorporated by reference Finite Element Analysis |
| ML20140A239 | 18 May 2020 | ASME Section XI Inservicee Inspection Program Proposed Inservice Inspection Alternative N1-15-NDE-002 | Boric Acid High Radiation Area Non-Destructive Examination Finite Element Analysis EVT-1 Pressure Boundary Leakage |
| ML20246G701 | 31 March 2020 | Enclosure 4: Attachment 3 - WCAP-18364-NP, Rev. 1, North Anna Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity for Subsequent License Renewal (SLR) | Incorporated by reference Exemption Request |
| ML20090B397 | 26 March 2020 | Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency | Weld Overlay Operating Basis Earthquake Finite Element Analysis License Renewal Subsequent License Renewal Thermal fatigue |
| ML20246G707 | 31 January 2020 | Enclosure 4: Attachment 4 - WCAP-11164-NP, Rev. 2, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for North Anna Units 1 and 2 Nuclear Power Plants for the Subsequent License Renewal | Safe Shutdown Earthquake Weld Overlay Hydrostatic Stress corrosion cracking License Renewal Subsequent License Renewal Pressure Boundary Leakage Pressure boundary leak Dissimilar Metal Weld Power Uprate Measurement Uncertainty Recapture Water hammer |
| ML19347A421 | 26 November 2019 | Owner'S Activity Report | |
| ML19249B774 | 29 August 2019 | Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) | Safe Shutdown Time of Discovery High winds Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Fire Barrier Safe Shutdown Earthquake Internal Flooding Reserve Station Service Transformer Operating Basis Earthquake Operator Manual Action FLEX Earthquake Fuel cladding Pressure Boundary Leakage Grace period |
| ML19249B768 | 29 August 2019 | Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) | Safe Shutdown Boric Acid Time of Discovery High winds Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Fire Barrier Time to boil Safe Shutdown Earthquake Internal Flooding Reserve Station Service Transformer Operating Basis Earthquake Operator Manual Action Emergency Lighting FLEX Earthquake Fuel cladding Pressure Boundary Leakage Grace period |
| ML19249B778 | 29 August 2019 | Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 | |
| ML19249B772 | 29 August 2019 | Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) | Safe Shutdown Time of Discovery High winds Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Fire Barrier Internal Flooding Reserve Station Service Transformer Operating Basis Earthquake Operator Manual Action FLEX Design basis earthquake Earthquake Fuel cladding Pressure Boundary Leakage Grace period |
| ML19106A356 | 23 April 2019 | Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage | |
| ML19011A172 | 4 January 2019 | Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) | Safe Shutdown Time of Discovery High winds Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Time to boil Reserve Station Service Transformer Operating Basis Earthquake FLEX Earthquake Fuel cladding Pressure Boundary Leakage Grace period |
| ML19011A173 | 4 January 2019 | Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents | Safe Shutdown Time of Discovery High winds Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Reserve Station Service Transformer Operating Basis Earthquake FLEX Earthquake Fuel cladding Pressure Boundary Leakage Grace period |
| ML19011A174 | 4 January 2019 | Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents | Safe Shutdown Time of Discovery High winds Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Reserve Station Service Transformer Operating Basis Earthquake FLEX Earthquake Fuel cladding Pressure Boundary Leakage Grace period |
| ML20246G709 | 31 October 2018 | Enclosure 4: Attachment 2 - WCAP-18353-NP, Rev. 0, Reactor Internals Fluence Evaluation for a Westinghouse 3-Loop Plant with Two Units - Subsequent License Renewal | Aging Management |
| ML18198A119 | 31 May 2018 | Attachment 5 to 18-233, ANP-3467NP, Rev. 0, North Anna Fuel-Vendor Independent Small Break LOCA Analysis Licensing Report | Loop seal Hydrostatic Exclusive Use Affidavit |
| ML17186A084 | 29 June 2017 | Flooding Focused Evaluation Summary | FLEX Fukushima Dai-Ichi Flooding Focused Evaluation |
| ML16187A323 | 24 June 2016 | Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24 | |
| ML15253A410 | 11 March 2016 | Enclosure 2 Screening Analysis Report | Ultimate heat sink Tornado Missile Fukushima Dai-Ichi Earthquake Generic Issues Program |
| ML15238A844 | 25 September 2015 | Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation | Safe Shutdown Ultimate heat sink Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Earthquake |
| ML15259A342 | 24 August 2015 | 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al | |
| ML15232A811 | 24 August 2015 | Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002 | Earthquake |
| ML15238B592 | 17 August 2015 | Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011 | Probabilistic Risk Assessment Operating Basis Earthquake Earthquake |
| ML15175A190 | 17 June 2015 | Owner'S Activity Report | Through-Wall Leak |
| ML15057A249 | 20 April 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 Relating to Recommendation 2.1 | Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML15058A034 | 23 February 2015 | Summary of Facility Changes, Tests and Experiments | Grab sample Surveillance Frequency Control Program |
| ML14133A011 | 7 May 2014 | March 12, 2012 Information Request Phase 2 Staffing Assessment Report | Safe Shutdown Health Physics Network High Radiation Area Ultimate heat sink Emergency Lighting FLEX Fukushima Dai-Ichi Severe Accident Management Guideline |
| ML14092A416 | 31 March 2014 | Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites)For Recommendation 2.1 | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Design basis earthquake Earthquake |
| ML14080A002 | 31 March 2014 | PNNL-22553, Final Assessment of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station. | Non-Destructive Examination Weld Overlay Nondestructive Examination Stress corrosion cracking Dissimilar Metal Weld Thermal fatigue |
| ML14084A327 | 27 March 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 | Unanalyzed Condition Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML14084A212 | 27 March 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 | Unanalyzed Condition Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML14283A046 | 28 February 2014 | MRP-375, Technical Basis for Reexamination Interval Extension for Alloy 690 PWR Reactor Vessel Top Head Penetration Nozzles (EPRI 3002002441), Attachment 1 | Boric Acid Non-Destructive Examination Probabilistic Risk Assessment VT-2 Finite Element Analysis Pressure Boundary Leakage Through-Wall Leak |
| ML13338A448 | 29 January 2014 | Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown Boric Acid High winds Shutdown Margin Loop seal Ultimate heat sink Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Tornado Generated Missile Fukushima Dai-Ichi Frazil ice Earthquake |
| ML14006A171 | 23 January 2014 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for North Anna Power Station, Units 1 and 2, TAC Nos.: MF0998 and MF0999 | Safe Shutdown Boric Acid High winds Shutdown Margin Loop seal Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Frazil ice Earthquake |