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 Issue dateTitleTopic
ML21264A53530 September 2021PWROG-19047-NP-A, Rev 0, North Anna Units 1 and 2 Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin AnalysisAnticipated operational occurrence
Safe Shutdown Earthquake
Hydrostatic
Incorporated by reference
Finite Element Analysis
Subsequent License Renewal
Earthquake
Affidavit
ML20182A69229 June 2020& ISFSI, Millstone Power Station, Units 1, 2 3, & ISFSI, North Anna Power Station, Units 1, 2 & ISFSI, Virgil C. Summer Station, Surry Power Station, Units 1 & 2 and ISFSI - Submission of Revision 28 of the Quality Assurance.Fitness for Duty
Shutdown Margin
Non-Destructive Examination
Grab sample
Commercial Grade Dedication
Hydrostatic
Coatings
Nondestructive Examination
Temporary Modification
Incorporated by reference
Condition Adverse to Quality
Aging Management
Process Control Program
License Renewal
Commercial Grade
Liquid penetrant
Fire Protection Program
Grace period
Overspeed trip
Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.30 November 2019PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.Anticipated operational occurrence
Safe Shutdown Earthquake
Earthquake
ML19175A07113 June 2019ISFSI, Millstone, Units 1, 2, 3, & ISFSI, North Anna, Units 1, 2 & ISFSI, Surry, Units 1 & 2 & ISFSI - Submittal of Revision 27 of the Quality Assurance Topical ReportFitness for Duty
Shutdown Margin
Non-Destructive Examination
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML18170A11414 June 2018PWROG-17033-NP, Revision 1, Update for Subsequent License Renewal: WCAP-13045, Compliance to ASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems.License Renewal
Subsequent License Renewal
ML18143B49731 May 2018Update for Subsequent License Renewal: WCAP-14535A, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination and WCAP-15666-A, Extension of Reactor Coolant Pump Motor Flywheel Examination.Non-Destructive Examination
Probabilistic Risk Assessment
Aging Management
License Renewal
Subsequent License Renewal
Liquid penetrant
Overspeed trip
ML18065A19428 February 2018Submittal of Approval Version of the Quality Assurance Topical Report, Revision 24-AFitness for Duty
Shutdown Margin
Non-Destructive Examination
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML18012A0984 January 2018Submittal of Topical Report VEP-NE-1-A Revision 0, Minor Revision 3, Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Technical Specifications & Topical Report.
ML17187A13228 June 2017Submittal of Topical Report VEP-NE-1, Revision 0.2-A, Relaxed Power Distribution Control Methodology and Associated Fq Surveillance Technical Specifications for Information OnlyExemption Request
ML16196A29211 July 2016ISFSI, Millstone, Units 1, 2 & 3, and ISFSI, North Anna, Units 1 & 2, and ISFSI, Surry, Units 1 & 2, and ISFSI Submission of Rev. 21 of Quality Assurance Topical Report for NRC Approval and Submission of Revision 22 for Information OnlyFitness for Duty
Shutdown Margin
Non-Destructive Examination
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML15313A14131 March 2015Topical Report, VEP-FRD-41-NP-A, Rev. 0.2, VEPCO Reactor System Transient Analyses Using the Retran Computer Code, March 2015Boric Acid
Shutdown Margin
Loop seal
Stroke time
Hydrostatic
Feedwater Heater
Fuel cladding
Power change
Power Uprate
Measurement Uncertainty Recapture
Affidavit
Overspeed trip
ML14188B13430 June 2014Nuclear Facility Quality Assurance Programs Description Topical Report DOM-QA-1, Rev. 16Fitness for Duty
Shutdown Margin
Non-Destructive Examination
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML13191A91317 June 2013ISFSI, Millstone, Units 1, 2, & 3 & ISFSI, North Anna, Units 1 & 2 & ISFSI and Surry, Units 1 & 2 & ISFSI - Submission of Revision 14 of the Quality Assurance Topical ReportFitness for Duty
Shutdown Margin
Non-Destructive Examination
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML11245A07715 August 2011ISFSI, Millstone, Units 1, 2, & 3 and ISFSI, North Anna, Units 1, & 2 and ISFSI and Surry, Units 1 & 2 and ISFSI - Re-Submission of Quality Assurance Topical ReportFitness for Duty
Shutdown Margin
Non-Destructive Examination
Commercial Grade Dedication
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML11180073028 June 2011Connecticut, Inc., Virginia Electric and Power Company, Submission of Revision 11 of the Quality Assurance Topical ReportFitness for Duty
Shutdown Margin
Non-Destructive Examination
Commercial Grade Dedication
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML08168050819 June 2008Stations - Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions
ML0631904676 November 2006Transmittal of Approved Topical Report DOM-NAF-3 NP-A, Gothic Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment.GOTHIC
Power Uprate
Stretch Power Uprate
Affidavit
ML06265018414 September 2006Approved Topical Report DOM-NAF-2, Rev 0.0-A, Reactor Core Thermal-Hydraulics Using the Vipre-D Computer Code Including Appendixes a & BExemption Request
Fuel cladding
ML0534701947 December 2005ISFSI Associated Radioactive Material Packages - DOM-QA-A Cover Page - IndexFitness for Duty
Shutdown Margin
Non-Destructive Examination
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML0530602661 November 2005Request for Approval of Topical Report DOM-NAF-3, Gothic Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment. Cover Letter Through Topical Report Page 40GOTHIC
Power Uprate
ML0530602731 November 2005Request for Approval of Topical Report DOM-NAF-3, Gothic Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment. Topical Report Page 40 Through EndGOTHIC
Stretch Power Uprate
ML0525104848 September 2005Stations Units 1 & 2, Millstone Power Station Units 2 & 3, Information Regarding a Lynxt Error Supporting the Request for Approval of Topical Report DOM-NAF-2 Reactor Core Thermal-hydraulics Using the VIPRE-D Computer .
ML04280011830 September 2004Request for Approval of Topical Report DOM-NAF-2 Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code Including Appendix a - Qualification of the F-ANP Bwu CHF Correlations in the Dominion VIPRE-D Computer CodeExemption Request
Fuel cladding
ML04280012230 September 2004Attachment 2 - Appendix a to Topical Report DOM-NAF-2, Qualification of the F-ANP Bwu CHF Correlations in the Dominion VIPRE-D Computer Code.
ML04247001824 August 2004Attachment 3 - Comparative Analysis of Current N45.2 Series QA Standards to NQA-1-1994 StandardsSafe Shutdown
Fitness for Duty
Shutdown Margin
Non-Destructive Examination
Grab sample
Offsite Dose Calculation Manual
Fire Barrier
Hydrostatic
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
Stress corrosion cracking
Eddy Current Testing
License Renewal
Commercial Grade
Liquid penetrant
Early Warning Fire Detection
Grace period
ML04247001924 August 2004Attachment 4 - Table of Where ANSI N18.7 Requirements Are Addressed by NQA-1-1994 Standards And/Or the New QA Topical ReportShutdown Margin
Coatings
Nondestructive Examination
Temporary Modification
ML04247001724 August 2004Attachment 2 - Discussion of Changes to Current QA Program Descriptions for the Above Dominion FacilitiesCoatings
Nondestructive Examination
Commercial Grade
ML04247002024 August 2004Attachment 5 - Current 10 CFR 50, Appendix B Quality Assurance Program Topical Report for North Anna and Surry Power Stations Associated Radioactive Material Packages and ISFSIFitness for Duty
Non-Destructive Examination
Offsite Dose Calculation Manual
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Early Warning Fire Detection
ML04247002124 August 2004Attachment 6 - Current 10 CFR 50, Appendix B Quality Assurance Program Topical Report for Millstone Power Stations and Associated Radioactive Material PackagesSafe Shutdown
Boric Acid
High Radiation Area
Offsite Dose Calculation Manual
Probabilistic Risk Assessment
Nondestructive Examination
Incorporated by reference
Condition Adverse to Quality
Process Control Program
Commercial Grade
Fire Protection Program
Grace period
Overspeed trip
ML0424700166 July 2004Attachment 1 - Proposed Nuclear Facility Quality Assurance Program Description - Topical Report DOM-QA-1, Revision 0, Final Draft July 06, 2004Fitness for Duty
Shutdown Margin
Non-Destructive Examination
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
License Renewal
Commercial Grade
Fire Protection Program
Overspeed trip
ML04259016930 June 2004VEP-FRD-41, Rev 0.1-A, Vepco Reactor System Transient Analyses Using the Retran Computer Code (Volume 1)Boric Acid
Shutdown Margin
Loop seal
Stroke time
Feedwater Heater
Power change
Affidavit
Overspeed trip
ML04107047215 April 2004Request for Approval of Topical Report DOM-NAF-2, Reactor Core Thermal-Hydraulics Using VIPRE-D Computer Code Including Appendix a, Qualification of F-ANP Bwu CHF Correlations in Dominion VIPRE-D Computer Code.Exemption Request
Fuel cladding
ML03323022512 November 2003Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application.Anticipated operational occurrence
Probabilistic Risk Assessment
Fuel cladding
Coast down
ML15313A14931 August 2003Topical Report, VEP-FRD-42, Rev. 2.1-A, Reload Nuclear Design Methodology, August 2003
ML15313A15431 August 2003Topical Report, VEP-NE-1, Rev. 0.1-A, VEPCO Relaxed Power Distribution Control Methodology and Associated Fq Surveillance Technical Specifications, August 2003Exemption Request
ML03268072029 August 2003Submittal of Approved Topical Report VEP-FRD-42, Revision 2.0-A, Reload Nuclear Design Methodology for ApplicationBoric Acid
Shutdown Margin
Loop seal
Power change
ML03169010811 June 2003Submittal of Approved Topical Report DOM-NAF-1-REV, 0.0-P-A Qualification of Studsvik Core Management System Reactor Physics Methods for Application to North Anna & Surry Power StationsBoric Acid
Power change
Affidavit
ML03091005321 March 2003Request for Additional Information on Topical Report VEP-FRD-42, Reload Nuclear Design MethodologyShutdown Margin
Loop seal
ML02338010125 November 2002Request for Additional Information, Topical Report DOM-NAF-1- Qualification of Studsvik Core Management System Reactor Physics Methods for Application to North Anna & Surry Power StationsAffidavit
ML02171079013 June 2002Attachment 2, Topical Report DOM-NAF-1, Qualification of the Studsvlk Core Management System Reactor Physics Methods for Application to North Anna Surry Power StationsBoric Acid
Power change
Affidavit
ML02091031422 March 2002Supplemental Information - NRC Bulletin 200-01, Circumferential Cracking of Reactor Vessel Head Penetration Nozzles Results of Metallurgical Investigation of Alloy 82/182 CrackingBoric Acid
Non-Destructive Examination
Weld Overlay
Stress corrosion cracking
ML19094A80128 May 1976Submits Thirty-Five Copies of Amendment Two to Topical Report Entitled, Quality Assurance Program-Operations Phase (VEP-1-A) for Approval