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 Issue dateTitle
ML20139A0879 June 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident
IR 05000395/201600111 May 2016NRC Integrated Inspection Report 05000395/2016001 and Notice of Enforcement Discretion, January 1, 2016, Through March 31, 2016
ML15173A43920 May 2015VC Summer 2015-301 Initial Exam Final SRO Written Exam
ML15105A34623 March 2015NSAL-15-2 - Impact of a Break in the Reactor Coolant Pump No. 1 Seal Leak-off Line Piping on Seal Leakage During a Loss of Seal Cooling Event
IR 05000395/201400722 December 2014IR 05000395/2014007; on 10/6/2014 - 11/7/2014 Virgil C. Summer Nuclear Station, Unit 1; Component Design Bases Inspection
ML14141A4616 June 2014Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
ML14010A41530 January 2014Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
RC-13-0177, South Carolina Electric & Gas Response to NRC Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic25 November 2013South Carolina Electric & Gas Response to NRC Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic
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.
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.
ML13017A47526 November 2012Final Seismic Walkdown Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
RC-12-0189, Engineering Services Technical Report TR02060-00120 November 2012Engineering Services Technical Report TR02060-001
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
IR 05000395/201100530 January 2012IR 05000395-11-005, on 10/01/2011 - 12/31/2011: Virgil C. Summer Nuclear Station; Routine Integrated Inspection Report
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 Problems
ML11186A90430 June 2011Notification of Potential Part 21 Appendix R Analyses Fails to Recognize Hot-Short Failure Resulting in the Loss of an Essential Electrical Bus
ML11182A91729 June 2011Part 21 Notification, Appendix R Analyses Fails to Recognize Hot-Short Failure Resulting in the Loss of an Essential Electrical Bus
IR 05000395/201000813 August 2010IR 05000395-10-008 on 06/14/10 - 06/18/10 and 06/28/10 - 07/01/10 for Virgil C. Summer Nuclear Station; Fire Protection
ML10236034726 February 2010E-Mail from Thomas to Rosebrook Et Al., Subject: Ioeb Screening Summary for Friday, February 26, 2010
ML0922909469 July 2009Initial Exam 2009-301 Final SRO Written Exam (as Given) with References and Answer Key
ML20216J41924 September 1999Part 21 Rept Re 990806 Abb K-Line Breaker Defect After Repair.Vendor Notified of Shunt Trip Wiring Problem & Agreed to Modify Procedure for Refurbishment of Breakers
ML20206H2975 May 1999Part 21 Rept Re Common Mode Failure for magne-blast Breakers.Vc Summer Nuclear Station Utilizes These Breakers in Many Applications,Including 7.2-kV EDG Electrical Buses
IR 05000395/199900226 April 1999Insp Rept 50-395/99-02 on 990214-0327.Non-cited Violation Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support
05000395/LER-1998-009, Forwards LER 98-009-01 for VC Summer Nuclear Station.Rept Describes Unanalyzed Condition for non-safety Related Component for Which All Failure Mechanisms Had Not Been Evaluated28 January 1999Forwards LER 98-009-01 for VC Summer Nuclear Station.Rept Describes Unanalyzed Condition for non-safety Related Component for Which All Failure Mechanisms Had Not Been Evaluated
IR 05000395/199800624 September 1998Insp Rept 50-395/98-06 on 980628-0725.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support
05000395/LER-1998-004, Forwards LER 98-004-01 Re Unanalyzed Condition for Equipment Qualification Beyond Ten Minutes Following High Energy Line Break Outside Containment,Per 10CFR50.73(a)(2)(ii).Suppl Provides Addl Corrective Actions5 August 1998Forwards LER 98-004-01 Re Unanalyzed Condition for Equipment Qualification Beyond Ten Minutes Following High Energy Line Break Outside Containment,Per 10CFR50.73(a)(2)(ii).Suppl Provides Addl Corrective Actions
IR 05000395/199800329 May 1998Insp Rept 50-395/98-03 on 980330-0417.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support
IR 05000395/199701323 December 1997Insp Rept 50-395/97-13 on 971019-1129.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support
IR 05000395/199701217 November 1997Insp Rept 50-395/97-12 on 970907-1018.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
ML20140D4522 June 1997Insp Rept 50-395/97-03 on 970323-0503.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support
05000395/LER-1996-004, Responds to Telcon W/G Lippard Re LER 96-004 on Leakage Past Motor Driven EFW Flow Control Valves Discovered During Recently Completed Refueling Outage at Station25 July 1996Responds to Telcon W/G Lippard Re LER 96-004 on Leakage Past Motor Driven EFW Flow Control Valves Discovered During Recently Completed Refueling Outage at Station
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping13 June 1991Thermal Stratification in Feedwater System Piping
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break30 June 1989Degradation of Containment Isolation Capability by a High-Energy Line Break
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11
ML20236V39827 November 1987Discusses Review of Rev 20 to Plant Radiation Emergency Plan,Per Util 871030 Submittal.Certain Changes Inconsistent w/NUREG-0654,App 1 & Info Notice 83-28,Attachment 1
NRC Generic Letter 1987-129 July 1987NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled
ML20214S8883 June 1987Safety Evaluation Rept Granting Relief from Hydrostatic Testing After Repair to ASME Code Section Xi,Class 1,reactor Coolant Pump Seal Injection Line
ML20214Q81329 May 1987Requests Relief from ASME Code/Section XI Hydrostatic Testing Requirements for Reactor Coolant Pump Seal Injection Sys.Relief Needed to Support Weld Repair to Seal Injection Pipe at Pump Thermal Barrier Flange.Details Encl.Fee Paid
Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System2 February 1987Miswiring in a Westinghouse Rod Control System
Information Notice 1986-53, Improper Installation of Heat Shrinkable Tubing26 June 1986Improper Installation of Heat Shrinkable Tubing
NRC Generic Letter 1983-4319 December 1983NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications
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