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| Issue date | Title | Topic | |
|---|---|---|---|
| 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 |
| 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 |
| 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 | |
| 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 |
| 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 Pressure Boundary Leakage Pressure boundary leak Dissimilar Metal Weld |
| 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 |
| 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 |
| ML19249B778 | 29 August 2019 | Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 | |
| 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 |
| 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 |
| 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 Dissimilar Metal Weld |
| 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 |
| 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 |
| ML13179A015 | 31 May 2013 | Units I and 2, Qualification of the ABB-NV and Wlop CHF Correlations in the Dominion VIPRE-D Computer Code | |
| ML12200A216 | 30 June 2012 | PNNL-21546 Evaluation of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station | Weld Overlay Nondestructive Examination Dissimilar Metal Weld |
| ML12143A135 | 8 May 2012 | NDE Results for Steam Generator Hot Leg Nozzle Full Structural Weld Overlays. Part 1 of 2 | Weld Overlay DM weld |
| ML12143A136 | 8 May 2012 | NDE Results for Steam Generator Hot Leg Nozzle Full Structural Weld Overlays. Part 2 of 2 | Weld Overlay DM weld |
| ML11290A170 | 12 October 2011 | Root Cause Evaluation Re Dual Unit Trip Following August 23, 2011 Earthquake | Temporary Modification Design basis earthquake Earthquake Fuel cladding Coast down |
| ML102390419 | 31 August 2010 | DOM-NAF-2, Rev. 0.2-A, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code. | B.5.b Mitigating Strategies Exemption Request Fuel cladding |
| ML11187A324 | 30 June 2010 | Justification for Extension of Temper Bead Limit to 1000 Square Inches for WOL of P1 and P3 Materials | Weld Overlay Finite Element Analysis Dissimilar Metal Weld |
| ML101620301 | 30 June 2010 | Radial-Hydride-Induced Embrittlement of High-Burnup Zirlo Cladding Exposed to Simulated Cask Drying Conditions | Finite Element Analysis Fuel cladding |
| ML102600216 | 13 May 2010 | Engineering Transmittal, ET-CEP-10-0006, Revision 0, Evaluation of Aluminum Conduit Seal Penetration Fire Tests, Dated May 13, 2010, North Anna and Surry Power Stations Units 1 and 2 (Redacted Version), Enclosure 2 | Boric Acid Fire Barrier Coatings Temporary Modification Cyber Security Aging Management Time Critical Operator Action B.5.b Mitigating Strategies Exemption Request Maintenance Rule Program Fire Protection Program |
| ML093070164 | 15 October 2009 | Technical Report No. EE-0116, Revision 5 | Offsite Dose Calculation Manual |
| ML082330474 | 13 August 2008 | Summary of Two Additional Facility Changes, Tests and Experiments, Not Included in Previous 03/28/2008 Submittal | |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
| ML080980229 | 4 April 2008 | Stations - Request for Approval of Appendix C of Fleet Report DOM-NAF-2 Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code | |
| ML080650563 | 29 February 2008 | Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors | Boric Acid High Radiation Area Mission time Safe Shutdown Earthquake Coatings Operating Basis Earthquake Finite Element Analysis Design basis earthquake Foreign Material Exclusion Fuel cladding Scaffolding |
| ML072740400 | 15 November 2007 | Corrective Actions for Generic Letter 2004-02 | Boric Acid Mission time Fire Barrier Safe Shutdown Earthquake Hydrostatic Coatings Operating Basis Earthquake Finite Element Analysis Design basis earthquake Foreign Material Exclusion Earthquake |
| ML071690502 | 15 June 2007 | Order - EA 03-009 Sixty Day Report, Reactor Pressure Vessel (RPV) Head Inspection Results | Boric Acid Liquid penetrant |
| ML073170678 | 19 May 2007 | SCS-00684, Rev. Draft-2, Design Report, ASME Bp&V Section III, Class 3, SS-45S8-18622-NSR Ball Valve, SS-45XS8-18623-NSR Ball Valve, Enclosure 2 | Finite Element Analysis |
| ML061100512 | 20 April 2006 | Virginia Electric and Power Company North Anna and Surry Power Stations 30-Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.26 | |
| ML033170024 | 13 October 2003 | American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Relief Request CMP-020 | Incorporated by reference |
| ML032110465 | 18 July 2003 | Realistic Large Break Loss of Coolant Accident Analysis Results for Proposed TS Changes & Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel | Boric Acid Exemption Request Fuel cladding |