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 Issue dateTitleFromTo
NRC Generic Letter 1988-0517 March 1988NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR PlantsMiraglia F
Office of Nuclear Reactor Regulation
NRC Generic Letter 1988-077 April 1988NRC 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
ML20155D2273 June 1988Forwards 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 880930Dominion
Nauman D
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification2 August 1988NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical SpecificationsMiraglia F
Office of Nuclear Reactor Regulation
ML20154Q05728 September 1988Summary of 880901 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts EnclHayes J
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation
ML20155F0926 October 1988Informs 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 RCPBHayes J
Office of Nuclear Reactor Regulation
Dominion
Bradham O
ML20195C69728 October 1988Summary of 881018 Meeting W/Util Re Status of Licensing Issues for Plant.List of Attendees EnclHayes J
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation
ML20196C7855 December 1988Summary of 881129 Meeting W/Util in Atlanta,Ga Re Status of Licensing Issues for Facility.List of Attendees Encl & Related Info EnclHayes J
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation
ML20245J21128 February 1989Summary of 890207 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts EnclHayes J
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation
ML20246M9248 May 1989Summary of 890418 & 19 Meetings W/Region II & Util to Discuss Status of Licensing Issues for Plant.List of Attendees & Handouts EnclHayes J
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation
ML20245A58515 June 1989Forwards 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 ScheduleDominion
Bradham O
Hayes J
Office of Information Resources Management
NRC Generic Letter 1991-1717 October 1991NRC 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 Testing7 October 1994Forwards 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 TestingDominion
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 Testing26 October 1994Requests 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 TestingDominion
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 1995Degradation 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 1995Degradation 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,encl30 July 1997Submits 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,enclDominion
Gabe Taylor
Office of Information Resources Management
ML20207J57031 October 1998Non-proprietary Rev 1 to WCAP-14955, Probabilistic & Economic Evaluation of Rv Closure Head Penetration Integrity for VC Summer Nuclear PlantBrad 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 Integrity3 April 2002Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary IntegritySouth 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 2002Response 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 2371 October 2002Operating License No. NPF-12, Basis Documentation for Application for Renewed Operating License, Virgil C. Summer Nuclear Station Mechanical Database AMR Query, Pages 1 to 237South Carolina Electric & Gas Company
Byrne S
Office of Nuclear Reactor Regulation
Document Control Desk
ML02325037821 November 2002Request for Additional Information, Bulletin 2002-01 Reactor Coolant Pressure Boundary Integrity 60 Day ResponseCotton 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 Integrity24 January 2003Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary IntegritySouth Carolina Electric & Gas Company
Byrne S
Cotton K
Office of Nuclear Reactor Regulation
Document Control Desk
IR 05000395/200500329 July 2005IR 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 ActivitiesNRC/RGN-II/DRP/RPB5
Landis K
South Carolina Electric & Gas Company
Archie J
IR 05000395/200600525 January 2007IR 05000395-06-005, on 10/01/2006 - 12/31/2006 for Virgil C. Summer; Surveillance Testing and Event FollowupEugene Guthrie
NRC/RGN-II/DRP/RPB5
South Carolina Electric & Gas Company
Archie J
IR 05000395/200800329 July 2008IR 05000395-08-003, on 04/01/2008 - 06/30/2008, Virgil C. Summer, Identification and Resolution of ProblemsNRC/RGN-II/DRP/RPB5
Bates M
South Carolina Electric & Gas Company
Archie J
IR 05000395/20110034 August 2011IR 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 ProblemsGerald Mccoy
Reactor Projects Region 2 Branch 6
South Carolina Electric & Gas Company
Gatlin T
IR 05000395/20120057 February 2013IR 05000395-12-005; 10/01/2012 - 12/31/2012: Virgil C. Summer Nuclear Station; Radioactive Material Handling, Storage and Transportation; Identification and Resolution of ProblemsGerald Mccoy
NRC/RGN-II/DRP/RPB5
South Carolina Electric & Gas Company
Gatlin T
IR 05000395/201400313 August 2014IR 05000395-14-003; on 04/01/2014 - 06/30/2014: Virgil C. Summer Nuclear Station, Unit 1; Problem Identification and Resolution, and Other ActivitiesNRC/RGN-II/DRP/RPB5
Mark King
South Carolina Electric & Gas Company
Gatlin T
ML16029A11229 January 2016NRC Integrated Inspection Report 05000395/2015004NRC/RGN-II/DRP/RPB5
Steven Rose
South Carolina Electric & Gas Company
Gatlin T
IR 05000395/20150045 February 2016Reissue - Virgil C. Summer Nuclear Station, Unit 1 - NRC Integrated Inspection Report 05000395/2015004NRC/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 1825 May 2016Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 18South Carolina Electric & Gas CompanyOffice of Nuclear Reactor Regulation
ML16166A23725 May 2016Updated Final Safety Analysis Report, Chapter 18South Carolina Electric & Gas CompanyOffice of Nuclear Reactor Regulation
ML19255F53131 May 2019Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and ActivitiesSouth Carolina Electric & Gas Company
Dominion Energy Co
Office of Nuclear Reactor Regulation
ML21209A17230 April 20211 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and ActivitiesDominion Energy South CarolinaOffice of Nuclear Reactor Regulation
ML22194A24827 June 20222 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and ActivitiesDominion Energy South CarolinaOffice of Nuclear Reactor Regulation