RC-18-0006, Independent Spent Fuel Storage Installation Re Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses
RC-18-0098, (Vcsns), Units 1, 2 and 3 - Modification of Requested Latest Completion Date in Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses
RC-09-0134, Response to Request for Additional Information for Generic Letter 2004-02
RC-09-0135, 10 CFR 50.59 Biennial Report Covering the Time Frame from October 1, 2007 to September 30, 2009
RC-09-0108, Response to Request for Additional Information on Extension of Enforcement Discretion and License Amendment for the Fire Protection Program
RC-09-0084, Request for Extension of Enforcement Discretion and Revised Submittal Schedule for 10 CFR 50.48(c) License Amendment Request (LAR 08-03929)
RC-09-0068, License Amendment Request - LAR 09-00562, for Use of Optimized Zirlo Fuel Rod Cladding
RC-09-0050, Submittal of 2008 Emergency Core Cooling System (ECCS) Evaluation Model Revisions Report
RC-09-0060, Response to Request for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
RC-09-0032, Report of Status of Decommissioning Funding
RC-09-0033, Virgil C Summer Nuclear Station - Guarantee of Payment of Deferred Premium Annual 10CFR140.21(e) Report
RC-09-0004, License Amendment Request - LAR 04-02911 License Amendment and Related Technical Specification Changes to Implement Full-scope Alternative Source Term in Accordance with 10 CFR 50.67
RC-09-0012, License Amendment Request LAR 08-01332, for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR 26
RC-08-0129, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
L-07-002, Sump Structural Analysis for Response to NRC GL 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
RC-08-0106, Supplemental Revision to License Amendment Request LAR 03-01931-20
RC-08-0083, Mitigation of Alloy 600/82/182 Pressurizer Butt Welds in 2008 (CR-07-00439) - Confirmatory Action Letter Completion
RC-08-0046, Guarantee of Payment of Deferred Premiums Annual 10CFR140.21(e) Report
RC-08-0043, V. C. Summer, Unit 1 - Transmittal of the 2007 Annual Operating Report
RC-08-0031, Supplemental Response to NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
RC-08-0006, Application to Use Weighting Factors for External Exposure
RC-08-0019, Request for Use of Higher Assigned Protection Factors with Use of French-Designed Air-Line Respirator Equipment
RC-08-0009, Supplemental Information Relative to Request to Use Alternatives to ASME Code Section Xl Requirements for Application of Weld Overlay Repairs (RR-III-05)
RC-08-0007, License Amendment Request - LAR 03-01931-20, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
RC-07-0169, Virgil Summer - 10 CFR 50.59 Biennial Report Covering the Period from October 1, 2005 Until October 1, 2007
RC-07-0143, Response to NRC Questions Regarding Response to Generic Letter 96-06
RC-07-0164, Withdrawal of License Amendment Request - LAR 05-3262 Changes to Emergency Diesel Generator Technical Specification
RC-07-0156, Response to NRC Request for Additional Information Regarding Lead Test Assemblies
RC-07-0118, Mitigation of Alloy 600/82/182 Pressurizer Butt Welds in 2008 (CR-07-00439)
RC-07-0085, Virgil Summer - Request to Use Alternatives to ASME Code Section XI Requirements for Application of Weld Overlay Repairs (RR-III-05)
RC-07-0081, ECCS Evaluation Model Revisions Annual Report
RC-07-0084, (Vcsns), Request for Burnup Extension of Exemption Request
RC-07-0082, Assessment of Feasibility for Leak Detection Enhancement (CR-07-00439)
RC-07-0074, V. C. Summer - Ninety-Day Response to GL 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
RC-07-0063, Amended Report of Status of Decommissioning Funding
RC-07-0047, Guarantee of Payment of Deferred Premiums Annual 10CFR140.21(e) Report
RC-07-0043, V.C. Summer Report of Status of Decommissioning Funding (RR-1950)
RC-07-0025, License Amendment Request - LAR 05-3594 Steam Generator Tube Integrity
RC-07-0028, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds (C-04-1719) - Supplement
RC-07-0021, Inspection and Mitigation Plan/Schedule of Alloy 82/182 Pressurizer Butt Welds (C-04-1719)
RC-06-0222, Response to Request for Additional Information Regarding NRC Bulletin 2004-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-Water Reactors
RC-06-0216, License Condition 2.C(5), 14-Day Report on Exceeding Surveillance Frequency
RC-06-0205, ECCS Evaluation Model Revisions Report
RC-06-0199, License Amendment Request - LAR 05-3262, Changes to Emergency Diesel Generator Specification
RC-06-0202, V. C. Summer - ECCS Evaluation Model Revisions Report, Addresses the Effect of Using a Finer Break Spectrum
RC-06-0204, Response to NRC Questions Regarding Response to Generic Letter 96-06
RC-06-0186, Letter of Intent to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition
RC-06-0182, Response to NRC Generic Letter 96-06: Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions - Change to Commitment Implementation Schedule
RC-06-0173, V. C. Summer - LAR 05-2926, Implementation of WCAP-14333-P-A, Rev. 1, Probabilistic Risk Analysis of RPS and ESFAS Test Times and Completion Times - Summarized List of Commitments
RC-05-0180, V. C. Summer License Amendment Request - LAR 05-3666, Alternate AC Power Supply Revision to Submitted Technical Specification Pages and Response to Verbal Request for Additional Information
RC-06-0117, Relief, Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04)
RC-06-0106, Day Response to NRC Generic Letter 2006-03: Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations
RC-06-0111, Reply to Notice of Violation: EA-06-046 NRC Inspection Report 2006-011
RC-06-0067, LAR 05-2926 Implementation of WCAP-14333-P-A, Rev. 1, Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times Response to Request for Additional Information
RC-06-0084, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity
RC-06-0094, April 2006 Monthly Operating Report for Virgil C. Summer Nuclear Station
RC-06-0073, March 2006 Monthly Operating Report for V.C. Summer Nuclear Station
RC-06-0058, Guarantee of Payment of Deferred Premiums Annual 10CFR140.21(e) Report
RC-06-0051, Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours
RC-06-0038, 30-Day Response to NRC Generic Letter 2006-01 Steam Generator Tube Integrity and Associated Technical Specifications
RC-06-0012, Results of Cycle 14 Lead Test Assembly Program Participation
RC-06-0030, Supplemental Response to NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
RC-06-0027, Initial Operator License Written Examination Post-Examination Comments
RC-18-0157, (Vcsns), Units 1, 2 and 3 Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses
RC-18-0149, ISFSI - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses
RC-05-0034, Response to Preliminary White Finding, NRC Inspection Report 2005006, Apparent Violation AV 05000395/2005006-02
RC-05-0204, Response to NRC Questions Regarding Response to Generic Letter 96-06
RC-05-0181, Elimination of Requirements to Provide the Monthly Operating Report and the Occupational Radiation Exposure Report Using the Consolidated Line Item Improvement Process
RC-05-0157, License Amendment Request - LAR 05-3664, Emergency Feedwater System Isolation Valves
RC-05-0193, Response to NRC Generic Letter 2003-01 on Control Room Habitability
RC-05-0192, Update to Emergency Response Data System Data Point Library
RC-05-0168, Response to Request for Additional Information Regarding Inspection Report Unresolved Issue URI 2004009-02
RC-05-0163, September 2005 Monthly Operating Report for Virgil C Summer Nuclear Station
RC-05-0145, August 2005 Monthly Operating Report for Virgil C. Summer Nuclear Station
RC-05-0138, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
RC-05-0140, Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI Relief Request RR-II-9 and RR-11-10 (C-02-3202)
RC-05-0135, Submittal of Information Requested by NRC for Integrity Evaluation for Future Operation Reactor Vessel Nozzle to Pipe Weld Regions (C-00-1392)
RC-05-0126, Containment Tendon Surveillance Report Update
RC-05-0117, Virgil C. Sumner, Response to NRC Bulletin 2004-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-Water Reactors (C-04-1719),
RC-05-0116, Special Report (Spr) 2005-03
RC-05-0097, Core Operating Limits Report - Reference for Best Estimate Loss of Coolant Accident
RC-05-0090, License Amendment Request Re Reactor Coolant System - Heatup/Cooldown Curves
RC-05-0095, LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area
RC-05-0091, Withdrawal of License Amendment Request - LAR 02-2820 Emergency Core Cooling Systems - Exclusion of Safety Injection Pumps from the Requirement of Vent ECCS Pumps
RC-05-0094, Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI Relief Request RR-11-9 and RR-11-10 (C-02-3202)
RC-05-0076, Operating License, Special Report (Spr 2005-001)
RC-05-0057, V.C. Summer Nuclear Station, Responds to Request for Additional Information Re NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
RC-05-0056, March 2005 Monthly Operating Report for Virgil C. Summer Nuclear Station
RC-05-0053, Guarantee of Payment of Deferred Premium Annual 10CFR140.21(e) Report
RC-05-0041, License Amendment Request (LAR 03-1931-24) Adoption of TS Task Force (TSTF) Traveler-287, Revision 5, Ventilation System Envelope Allowed Outage Time
RC-05-0037, 90-Day Response to NRC GL-04-002: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
RC-05-0008, Response to Preliminary White Finding NRC IR 05000395-05-006
RC-05-0022, January 2005 Monthly Operating Report for the Virgil C. Summer Nuclear Station Unit 1
RC-05-0003, Response to NRC Generic Letter 2003-01 Control Room Habitability - Change to Activity Schedule
ND-18-0008, (VCSNS) Units 2 and 3 - Reporting of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Section Viii Departures
ND-18-0004, (VCSNS) Units 2 and 3, ITAAC Completion and Operational Program Implementation Schedule Updates (Required by 10 CFR 52.99(a) and License Conditions 2.D.(11) and 2.D.(12)(e))
ND-18-0002, Submittal of Six (6) Month Status Report Regarding Implementation of the Overall Integrated Plan for Mitigation Strategies for Beyond Design Basis External Events
ND-18-0001, (VCSNS) Units 2 and 3, Reporting of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Section VI 11 Departures
ND-17-0503, V. C. Summer, Units 2 and 3 - Request for Withdrawal of COLs
ND-12-0606, Report of Changes to Quality Assurance Program Description
RC-04-0185, Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-water Reactors
RC-04-0184, Request for Additional Information - Request for Exemption for Cladding Material Specified in 10CFR50.44 and 10CFR50 Appendix K
RC-04-0175, Confirmation of Implementation of April 29, 2003, Orders to V. C. Summer Nuclear Station (EA-03-086)
RC-04-0178, 60-day Response to NRC Generic Letter 2004-01 Requirements for Steam Generator Tube Inspections
RC-04-0170, Reactor Vessel Radiation Surveillance Program
RC-04-0164, NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information
RC-04-0167, NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information Date Extension.
RC-04-0162, Supplemental Response to April 29, 2003, Order Requiring Compliance with Revised Design Basis Threat for Operating Power Reactors (EA-03-086)
RC-04-0148, Request to Use Alternatives to ASME Code Requirements in Plant Third Inservice Inspection Interval (RR-111-01, RR-111-02)
RC-04-0147, Request for Exemption for Cladding Material Specified in 10CFR50.44, 10CFR50.46 and 10CFR50 Appendix K
05000395/LER-2009-003, Regarding Potential Loss of Residual Heat Removal System Safety Function in Mode 4 Due to an Unanalyzed Condition
05000395/LER-2009-002, Unit ,1 Regarding Reactor Trip from Fault of Main Generator Output Breaker
05000395/LER-2009-001, Regarding Inadequate Procedure Results in EDG Not Obtaining Maximum Load Required by Technical Specification
NRC-2008-0332, Comment (16) of Jeffrey B. Archie, on Behalf of South Carolina Electric and Gas Company, Endorsing NEIs Comments Re ANPR 50, Performance-Based Emergency Core Cooling System Acceptance Criteria
05000395/LER-2008-004, V. C. Summer Technical Specification Violation Due to Alternate AC Unavailability
05000395/LER-2008-003, Regarding Inadvertent Actuation of the Emergency Diesel Generator in the Emergency Start Mode Due to Bus Undervoltage
05000395/LER-2008-002, Re Control Room Normal and Emergency Air Handling Systems Inoperable Due to Pressure Boundary Breach
05000395/LER-2008-001, Regarding Manual Reactor Trip Due to Low Steam Generator Level Caused by Feedwater Flow Control Valve Malfunction
05000395/LER-2007-002, Re Failure to Follow Administrative Controls Results in LCO 3.6.4 Violation
05000395/LER-2007-003, Regarding Clogged Reactor Building Cooling Unit Drain Line Results in Violation of LCO 3.4.6.1
05000395/LER-2007-001, Regarding Manual Reactor Shutdown Due to Steam Leak at Feedwater Booster Pump Recirculation Header
05000395/LER-2006-004, Re Turbine Trip Due to High Steam Generator Level P-14
05000395/LER-2006-003, From Virgil C. Summer Re Emergency Diesel Generator Start Due to Undervoltage on 1DB Emergency Bus
05000395/LER-2006-002, Re Securing an Associated Radiation Monitor While the Reactor Building Alternate Purge System Was in Service
05000395/LER-2006-001, Securing Emergency Recirculation of Control Room Ventilation While Associated Radiation Monitor Was Out of Service
05000395/LER-1999-014-03, Re Kaowool Fire Barriers Outside 10 CFR 50 Appendix R Design Basis
05000395/LER-2005-002, Regarding Mode 3 Entry with an Inoperable Emergency Feedwater Pump
RC-05-0143, License Amendment Request - LAR 05-2926 Implementation of WCAP-14333-P-A, Rev. 1, Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times
05000395/LER-2005-003, Regarding Plant Trip and Associated Fire in B Condensate Pump Motor
05000395/LER-2005-001, Re Emergency Diesel Generator Start and Load Due to a Loss of Vital Bus
05000395/LER-2004-003, Regarding Emergency Diesel Generator Start and Load Due to Inadvertent Actuation of 1 DA Undervoltage Test Switch