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 Issue dateTitleTopic
ML23325A20216 January 2024CFR Part 52 Construction Lessons-Learned Report
ML23024A15423 January 2023Proposed Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Potential Subsequent License Renewal ActivityIncorporated by reference
ML22279A98923 September 2022Restoration Project - Final Status Survey Release Record North Protected Area Yard Survey Unit 12201C - Revision 2
ML22069B11710 March 2022Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination)Weld Overlay
Dissimilar Metal Weld
DM weld
ML21175A24724 June 20212020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....-
ML20296A70822 October 2020(VCSNS) Unit 1 - Alternative Requests RR-4-25 for Elimination of Reactor Pressure Vessel Threads in Flange Examination for the Remainder of the Fourth 10-Year ISI IntervalFinite Element Analysis
Weak link
ML20203M16020 July 2020VA 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 & StatusAnchor Darling
ML19204A11717 July 2019Vigil C. Summer, Unit 1, Proposed Alternative Request RR-4-20 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of RadiographyNondestructive Examination
Dissimilar Metal Weld
ML19056A41431 January 2019Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Entrainment Performance StudiesLicense Renewal
ML19056A41331 January 2019Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Cooling Water System Data
ML19056A41231 January 2019Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Source Water Baseline Biological Characterization DataLicense Renewal
ML19056A41031 January 2019Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Source Water Physical DataGrab sample
License Renewal
ML19056A41131 January 2019Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Cooling Water Intake Structure Data
RC-18-0117, (Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk Assessment28 September 2018(Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk AssessmentSafe Shutdown
Ultimate heat sink
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Operating Basis Earthquake
FLEX
Fukushima Dai-Ichi
Large early release frequency
Earthquake
RC-17-0089, Focused Evaluation for External Flooding30 June 2017Focused Evaluation for External FloodingUltimate heat sink
FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
ML19056A41528 February 2017Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Appendix B, Entrainment Study, 2016 and Revised 2017
RC-16-0143, (VCSNS) Unit 1 - Report of Full Compliance and Final Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design...31 October 2016(VCSNS) Unit 1 - Report of Full Compliance and Final Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design...Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Time to boil
Safe Shutdown Earthquake
Operating Basis Earthquake
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Time Critical Operator Action
B.5.b Mitigating Strategies
Earthquake
RC-14-0048, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident26 March 2014Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi AccidentSafe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
ML19056A40828 February 2014Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Thermal Mixing Zone Evaluation, Addendum: Additional Modeling Cases for Revised Reservoir Ambient and Discharge Temperatures
ML14034A33921 February 2014Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Frazil ice
Battery sizing
B.5.b Mitigating Strategies
Earthquake
ML14037A22821 February 2014Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Virgil C. Summer Nuclear Station, Unit 1, TAC MF2338Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Frazil ice
Battery sizing
B.5.b Mitigating Strategies
Earthquake
RC-13-0130, WCAP-17758-NP, Rev. 0, Technical Basis for Westinghouse Embedded Flaw Repair for V.C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles and Attachment Welds.31 August 2013WCAP-17758-NP, Rev. 0, Technical Basis for Westinghouse Embedded Flaw Repair for V.C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles and Attachment Welds.Operating Basis Earthquake
Finite Element Analysis
RC-13-0038, Flooding Hazard Reevaluation Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task.12 March 2013Flooding Hazard Reevaluation Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task.Ultimate heat sink
Hydrostatic
Fukushima Dai-Ichi
RC-13-0037, Permanent ILRT Interval Extension Risk Impact Assessment1 March 2013Permanent ILRT Interval Extension Risk Impact AssessmentSafe Shutdown
High winds
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Large early release frequency
Earthquake
ML13072A08331 January 201312-4116.IPEC.V002, Revision 1, Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation: EA-12-051Boric Acid
High Radiation Area
Locked High Radiation Area
FLEX
Spent Fuel Pool Instrumentation
RC-12-0175, WCAP-17688-NP, Rev 0, V.C. Summer Unit 1 Seismic Walkdown Inspection Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic.30 November 2012WCAP-17688-NP, Rev 0, V.C. Summer Unit 1 Seismic Walkdown Inspection Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic.Safe Shutdown
Unanalyzed Condition
Boric Acid
High Radiation Area
Ultimate heat sink
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Coatings
Operating Basis Earthquake
Finite Element Analysis
FLEX
Aging Management
Fukushima Dai-Ichi
Large early release frequency
Earthquake
Scaffolding
Backfit
RC-12-0174, Final Flooding Walk Down Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near.26 November 2012Final Flooding Walk Down Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near.Unanalyzed Condition
High winds
Fukushima Dai-Ichi
Scaffolding
RC-12-0189, Engineering Services Technical Report TR02060-00120 November 2012Engineering Services Technical Report TR02060-001Unanalyzed Condition
High winds
Fukushima Dai-Ichi
Scaffolding
RC-12-0173, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles14 November 2012Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration NozzlesOperating Basis Earthquake
RC-12-0170, LTR-PAFM-12-137-NP, Rev. 1, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer, Unit 1, Reactor Vessel Head Penetration Nozzles.5 November 2012LTR-PAFM-12-137-NP, Rev. 1, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer, Unit 1, Reactor Vessel Head Penetration Nozzles.Operating Basis Earthquake
RC-12-0110, LTR-PAFM-12-86-NP, Rev. 0, Flaw Tolerance Evaluation to Support Re-categorization of V. C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements.27 June 2012LTR-PAFM-12-86-NP, Rev. 0, Flaw Tolerance Evaluation to Support Re-categorization of V. C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements.Hydrostatic
Finite Element Analysis
Liquid penetrant
Dissimilar Metal Weld
DM weld
ML19056A4079 January 2012Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Thermal Mixing Zone Evaluation
ML11321A17215 November 2011License Amendment Request - LAR-06-00055, and to Adopt NFPA 805 Performance - Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)Hot Short
Safe Shutdown
Boric Acid
Shutdown Margin
Mission time
Offsite Dose Calculation Manual
Fire Barrier
Anticipated operational occurrence
Time to boil
Safe Shutdown Earthquake
Internal Flooding
Enforcement Discretion
Probabilistic Risk Assessment
Operator Manual Action
Multiple Spurious Operation
Emergency Lighting
B.5.b
Significance Determination Process
Thermoset
Process Control Program
Large early release frequency
Exemption Request
Earthquake
Maintenance Rule Program
Fire Protection Program
ML19056A41630 September 2009Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Monticello Reservoir Ichthyoplankton Studies, September 2008 Through August 2009
ML0821900137 August 2008Monthly Operating Reports Second Quarter 2008Reserve Station Service Transformer
Power change
ML06041027631 July 2005V.C. Summer High Burnup LTA Inspection Report.
RC-05-0097, Core Operating Limits Report - Reference for Best Estimate Loss of Coolant Accident30 June 2005Core Operating Limits Report - Reference for Best Estimate Loss of Coolant AccidentShutdown Margin
ML06040022331 December 20041003361 - On-Line Monitoring of Instrument Channel Performance, Volume 1: Guidelines for Model Development and ImplementationCoast down
RC-06-0024, 1007930 - On-Line Monitoring of Instrument Channel Performance, Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation31 December 20041007930 - On-Line Monitoring of Instrument Channel Performance, Volume 3: Applications to Nuclear Power Plant Technical Specification InstrumentationReactor Vessel Water Level
ML03008029930 December 2002Special Report 2002-002
ML02276026427 September 2002Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Memorandum Dated 09/27/02 - Figure 20Finite Element Analysis
ML02277046127 September 2002Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Figures 21 - 70Finite Element Analysis
ML02304026819 September 2002Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course ManualSafe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Power-Operated Valves