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Issue date | Title | From | To | |
---|---|---|---|---|
NRC Generic Letter 1988-05 | 17 March 1988 | NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants | Miraglia F Office of Nuclear Reactor Regulation | |
NRC Generic Letter 1988-07 | 7 April 1988 | NRC Generic Letter 1988-007: Modified Enforcement Policy Relating to 10 CFR 50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants. | Miraglia F Office of Nuclear Reactor Regulation | |
ML20155D227 | 3 June 1988 | Forwards Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. Detailed Evaluation of Components to Be Completed by 880930 | Dominion Nauman D | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification | 2 August 1988 | NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical Specifications | Miraglia F Office of Nuclear Reactor Regulation | |
ML20154Q057 | 28 September 1988 | Summary of 880901 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts Encl | Hayes J Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation |
ML20155F092 | 6 October 1988 | Informs That 880603 Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants Provided Assurance That Program in Place Deals W/Boric Acid Leakage Re Integrity of RCPB | Hayes J Office of Nuclear Reactor Regulation | Dominion Bradham O |
ML20195C697 | 28 October 1988 | Summary of 881018 Meeting W/Util Re Status of Licensing Issues for Plant.List of Attendees Encl | Hayes J Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation |
ML20196C785 | 5 December 1988 | Summary of 881129 Meeting W/Util in Atlanta,Ga Re Status of Licensing Issues for Facility.List of Attendees Encl & Related Info Encl | Hayes J Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation |
ML20245J211 | 28 February 1989 | Summary of 890207 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts Encl | Hayes J Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation |
ML20246M924 | 8 May 1989 | Summary of 890418 & 19 Meetings W/Region II & Util to Discuss Status of Licensing Issues for Plant.List of Attendees & Handouts Encl | Hayes J Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation |
ML20245A585 | 15 June 1989 | Forwards Response to 890420 Request for Addl Info Re Proposed Extension of OL to 40-yr Term Beginning W/Date of OL Rather than Cp.Effective Jul 1989,util Rates to Customers Will Reflect 40-yr Depreciation Schedule | Dominion Bradham O | Hayes J Office of Information Resources Management |
NRC Generic Letter 1991-17 | 17 October 1991 | NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants. | Partlow J Office of Nuclear Reactor Regulation | |
RC-94-0258, Forwards Rev 1 to ISI Relief Request RR-06,from ASME Section XI Requirements for Class 1 & 2 Insulated Pressure Retaining Bolted Connections Which Received VT-2 Visual Exam During Performance Sys Pressure Testing | 7 October 1994 | Forwards Rev 1 to ISI Relief Request RR-06,from ASME Section XI Requirements for Class 1 & 2 Insulated Pressure Retaining Bolted Connections Which Received VT-2 Visual Exam During Performance Sys Pressure Testing | Dominion Skolds J | Office of Information Resources Management |
RC-94-0280, Requests Relief from ASME Section XI Requirements for Class 1 & 2 Insulated Pressure Retaining Bolted Connection, Receiving VT-2 Visual Exam During Performance of Sys Pressure Testing | 26 October 1994 | Requests Relief from ASME Section XI Requirements for Class 1 & 2 Insulated Pressure Retaining Bolted Connection, Receiving VT-2 Visual Exam During Performance of Sys Pressure Testing | Dominion Skolds J | Office of Information Resources Management |
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | Grimes B K Office of Nuclear Reactor Regulation | |
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | Grimes B Office of Nuclear Reactor Regulation | |
RC-97-0150, Submits 120-day Response to GL 97-01, Degradation of CR Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations Per 10CFR50.54(f).Non-proprietary Rev 0 to TR WCAP-14955 & Proprietary Rev 0 to TR WCAP-14932,encl | 30 July 1997 | Submits 120-day Response to GL 97-01, Degradation of CR Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations Per 10CFR50.54(f).Non-proprietary Rev 0 to TR WCAP-14955 & Proprietary Rev 0 to TR WCAP-14932,encl | Dominion Gabe Taylor | Office of Information Resources Management |
ML20207J570 | 31 October 1998 | Non-proprietary Rev 1 to WCAP-14955, Probabilistic & Economic Evaluation of Rv Closure Head Penetration Integrity for VC Summer Nuclear Plant | Brad Bishop WESTINGHOUSE ELECTRIC COMPANY DIV OF CBS CORP. Bamford W Duran J | |
RC-02-0055, Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | 3 April 2002 | Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | South Carolina Electric & Gas Company Byrne S | Office of Nuclear Reactor Regulation Document Control Desk Edison G |
RC-02-0091, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity. | 17 May 2002 | Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity. | South Carolina Electric & Gas Company Byrne S | Cotton K Office of Nuclear Reactor Regulation Document Control Desk |
RC-02-0170, Operating License No. NPF-12, Basis Documentation for Application for Renewed Operating License, Virgil C. Summer Nuclear Station Mechanical Database AMR Query, Pages 1 to 237 | 1 October 2002 | Operating License No. NPF-12, Basis Documentation for Application for Renewed Operating License, Virgil C. Summer Nuclear Station Mechanical Database AMR Query, Pages 1 to 237 | South Carolina Electric & Gas Company Byrne S | Office of Nuclear Reactor Regulation Document Control Desk |
ML023250378 | 21 November 2002 | Request for Additional Information, Bulletin 2002-01 Reactor Coolant Pressure Boundary Integrity 60 Day Response | Cotton K NRC/NRR/DLPM/LPD2 | South Carolina Electric & Gas Company Byrne S |
RC-03-0016, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity | 24 January 2003 | Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity | South Carolina Electric & Gas Company Byrne S | Cotton K Office of Nuclear Reactor Regulation Document Control Desk |
IR 05000395/2005003 | 29 July 2005 | IR 05000395-05-003, on 04/01-06/30/2005, Virgil Summer, Inservice Inspection Activities, Operator Performance During Non-Routine Evolutions and Events, and Refueling and Outage Activities | NRC/RGN-II/DRP/RPB5 Landis K | South Carolina Electric & Gas Company Archie J |
IR 05000395/2006005 | 25 January 2007 | IR 05000395-06-005, on 10/01/2006 - 12/31/2006 for Virgil C. Summer; Surveillance Testing and Event Followup | Eugene Guthrie NRC/RGN-II/DRP/RPB5 | South Carolina Electric & Gas Company Archie J |
IR 05000395/2008003 | 29 July 2008 | IR 05000395-08-003, on 04/01/2008 - 06/30/2008, Virgil C. Summer, Identification and Resolution of Problems | NRC/RGN-II/DRP/RPB5 Bates M | South Carolina Electric & Gas Company Archie J |
IR 05000395/2011003 | 4 August 2011 | IR 05000395-11-003, on 04/01/2011 - 06/30/2011, Virgil C. Summer Nuclear Station, Maintenance Risk Assessments & Emergent Work Control, Refueling & Other Outage Activities; & Identification and Resolution of Problems | Gerald Mccoy Reactor Projects Region 2 Branch 6 | South Carolina Electric & Gas Company Gatlin T |
IR 05000395/2012005 | 7 February 2013 | IR 05000395-12-005; 10/01/2012 - 12/31/2012: Virgil C. Summer Nuclear Station; Radioactive Material Handling, Storage and Transportation; Identification and Resolution of Problems | Gerald Mccoy NRC/RGN-II/DRP/RPB5 | South Carolina Electric & Gas Company Gatlin T |
IR 05000395/2014003 | 13 August 2014 | IR 05000395-14-003; on 04/01/2014 - 06/30/2014: Virgil C. Summer Nuclear Station, Unit 1; Problem Identification and Resolution, and Other Activities | NRC/RGN-II/DRP/RPB5 Mark King | South Carolina Electric & Gas Company Gatlin T |
ML16029A112 | 29 January 2016 | NRC Integrated Inspection Report 05000395/2015004 | NRC/RGN-II/DRP/RPB5 Steven Rose | South Carolina Electric & Gas Company Gatlin T |
IR 05000395/2015004 | 5 February 2016 | Reissue - Virgil C. Summer Nuclear Station, Unit 1 - NRC Integrated Inspection Report 05000395/2015004 | NRC/RGN-II/DRP/RPB5 Steven Rose | South Carolina Electric & Gas Company Gatlin T |
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 18 | 25 May 2016 | Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 18 | South Carolina Electric & Gas Company | Office of Nuclear Reactor Regulation |
ML16166A237 | 25 May 2016 | Updated Final Safety Analysis Report, Chapter 18 | South Carolina Electric & Gas Company | Office of Nuclear Reactor Regulation |
ML19255F531 | 31 May 2019 | Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities | South Carolina Electric & Gas Company Dominion Energy Co | Office of Nuclear Reactor Regulation |
ML21209A172 | 30 April 2021 | 1 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities | Dominion Energy South Carolina | Office of Nuclear Reactor Regulation |
ML22194A248 | 27 June 2022 | 2 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities | Dominion Energy South Carolina | Office of Nuclear Reactor Regulation |