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| Issue date | Title | Topic | |
|---|---|---|---|
| ML24032A466 | 16 January 2024 | Response to Comments on Draft Vpdes Permit No. VA0052451 | |
| ML23324A422 | 20 November 2023 | Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 | Non-Destructive Examination Aging Management License Renewal Subsequent License Renewal EVT-1 Power Uprate Stretch Power Uprate |
| 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 |
| ML23167B007 | 31 May 2023 | Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary | Subsequent License Renewal |
| 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 |
| ML22193A143 | 23 June 2022 | 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 | Safe Shutdown Boric Acid Time of Discovery Shutdown Margin High Radiation Area Fire Barrier Stroke time Hydrostatic Emergency Lighting Functionality Assessment Large early release frequency Operability Determination Severe Accident Management Guideline Earthquake Pressure Boundary Leakage Recently irradiated fuel Continuous fire watch Fire Protection Program Fire Watch Hourly Fire Watch Early Warning Fire Detection Downpower Coast down Power Uprate Measurement Uncertainty Recapture |
| ML22263A285 | 23 May 2022 | Alert and Notification System Evaluation Report_Ans Evaluation_Redacted Page 1-65 | |
| ML22263A364 | 23 May 2022 | Alert and Notification System Evaluation Report - ANS Evaluation Redacted Pages 1 - 95 | |
| ML22263A369 | 1 May 2022 | Alert and Notification System Evaluation Report - ANS Evaluation Redacted Pages 96-190 | |
| ML22119A172 | 13 April 2022 | Post-Accident Monitoring (PAM) Report | Post Accident Monitoring |
| ML21175A247 | 24 June 2021 | 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- | |
| 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 | |
| ML20352A334 | 17 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 | VT-2 Biofouling Through-Wall Leakage Scaffolding |
| ML20296A680 | 22 October 2020 | ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative S1-I5-ISL-05 and S2-15-ISL-06 | Finite Element Analysis Weak link |
| 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 |
| ML20035C759 | 16 January 2020 | Redacted - Kewaunee, Request for Exemption from Certain Code of Federal Regulation Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System | Tornado-Generated Missile Exemption Request Earthquake |
| ML19352B898 | 17 December 2019 | Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements | Incorporated by reference Fuel cladding |
| ML19246A116 | 7 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) | Internal Flooding Hydrostatic Fukushima Dai-Ichi |
| 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 |
| 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 |
| ML19249B778 | 29 August 2019 | Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 | |
| ML19235A068 | 19 August 2019 | 3M Interam Website | Fire Barrier Coatings Earthquake |
| ML19235A080 | 19 August 2019 | Thermo-Lag Website | Coatings |
| ML19235A079 | 19 August 2019 | Pyrocrete Website | |
| ML19235A078 | 19 August 2019 | Mineral Wool Website | |
| ML19235A077 | 19 August 2019 | Micarta Website | |
| ML19235A076 | 19 August 2019 | Marinite Website | Coatings |
| ML19235A075 | 19 August 2019 | Marinite Slide Plates Products - Piping Tech | |
| ML19235A069 | 19 August 2019 | Bio K-10 Website | |
| ML19235A070 | 19 August 2019 | Cera Blanket Website | |
| ML19235A071 | 19 August 2019 | Cerafiber Website | |
| ML19235A072 | 19 August 2019 | Duxseal Website | |
| ML19235A073 | 19 August 2019 | Gypsum Website | |
| ML19235A074 | 19 August 2019 | Kbs Sealbags Website | |
| ML19204A358 | 30 June 2019 | WCAP-18258-NP, Revision 1, Flaw Tolerance Evaluation for Susceptible Reactor Coolant Loop Cast Austenitic Stainless Steel Elbow Components for Surry Units 1 and 2. | Safe Shutdown Earthquake Aging Management Earthquake |
| ML19106A356 | 23 April 2019 | Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage | |
| ML19070A217 | 3 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 | Fukushima Dai-Ichi |
| ML19095A602 | 2 April 2019 | Enclosure 2 - SLRA Mark-Ups Change Notice 2 | Boric Acid Ultimate heat sink Non-Destructive Examination Fire Barrier Coatings Temporary Modification Aging Management Foreign Material Exclusion Moisture barrier License Renewal Subsequent License Renewal Earthquake Control of Heavy Loads Biofouling EVT-1 Liquid penetrant Pressure Boundary Leakage Through Wall Leak Through-Wall Leakage Fire Protection Program Dissimilar Metal Weld Power Uprate Measurement Uncertainty Recapture |
| ML19064A590 | 28 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 | Safe Shutdown Earthquake Operating Basis Earthquake Design basis earthquake Pressure boundary leak |
| 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 |
| 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 |
| 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 |
| 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 |