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 Issue dateTitle
ML22194A24827 June 20222 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities
ML22188A08123 June 2022ISFSI, Virgil C. Summer Nuclear Station, Unit 1 & ISFSI, North Anna Power Station, Units 1 & 2 & ISFSI, Surry Power Station, Units 1 & 2 & ISFSI - Submission of Revision 32 of the Quality Assurance Topical Report
ML22040A1468 February 2022(Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 26
ML21197A04315 July 2021VCS ISI 2021004 RFI - Combined
ML21168A33917 June 2021Virgil C. Summer Nuclear Station, North Anna Power Station, Surry Power Station -Submission of Revision 30 of the Quality Assurance Topical Report
ML21209A17230 April 20211 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities
IR 05000395/20200024 August 2020Integrated Inspection Report 05000395/2020002 and Independent Spent Fuel Storage Installation Inspection (ISFSI) Report 07201038/2020001
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.
ML19302E17024 October 2019Replacement of Quality Assurance Program Description with Topical Report DOM-QA-1
ML19255F48531 May 2019Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems
ML19255F53131 May 2019Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities
ML19255F49131 May 2019Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System
IR 05000395/201800421 February 2019Reissued - Virgil C. Summer Nuclear Station, Unit 1 - Nuclear Regulatory Commission Integrated Inspection Report 05000395/2018004
ML19044A63413 February 2019Nuclear Regulatory Commission Integrated Inspection Report 05000395/2018004
ML18225A09313 August 2018Notification of Inspection and Request for Information
ML18221A16531 May 2018Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems31 May 2018Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
ML18221A16731 May 2018Updated Final Safety Analysis Report, Chapter 5.0, Reactor Coolant System
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 5.0, Reactor Coolant System31 May 2018Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 5.0, Reactor Coolant System
ML17059C53823 February 2017Notification of Inspection and Request for Information
ML16166A23725 May 2016Updated Final Safety Analysis Report, Chapter 18
ML16166A11425 May 2016Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System25 May 2016Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System
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 18
ML16029A11229 January 2016NRC Integrated Inspection Report 05000395/2015004
RC-15-0020, Attachment 4 - First Inservice Inspection for Steam Generator a25 February 2015Attachment 4 - First Inservice Inspection for Steam Generator a
RC-15-0020, Attachment 3 - Final NDE Inspection Reports25 February 2015Attachment 3 - Final NDE Inspection Reports
ML15061A03125 February 2015Relief Request RR-4-09 Request for Weld Recategorization for VCSNS Steam Generator Nozzle to Safe End Welds
ML15061A03525 February 2015Attachment 4 - First Inservice Inspection for Steam Generator a
ML15061A03425 February 2015Attachment 3 - Final NDE Inspection Reports
RC-14-0145, Twenty-First Refueling Inservice Inspection (ISI) Reports28 August 2014Twenty-First Refueling Inservice Inspection (ISI) Reports
RC-14-0021, Relief Request RR-4-05 Alternative Weld Repair for Reactor Vessel Upper Head Penetrations24 February 2014Relief Request RR-4-05 Alternative Weld Repair for Reactor Vessel Upper Head Penetrations
ML14055A22621 February 2014Notification of Inspection and Request for Information
ML12319A2555 November 2012Relief Request RR-III-09 Supplemental Information
RC-12-0165, Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration30 October 2012Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration
RC-12-0154, Reactor Vessel Head Penetration Weld Repair Under WCAP-1598722 October 2012Reactor Vessel Head Penetration Weld Repair Under WCAP-15987
ML12289A05017 October 2012Alternative RR-III-08 for Third 10-Year Inservice Inspection Interval
RC-12-0136, Response to NRC Request for Additional Information Request for Weld Recategorization and Use of Alternative to ASME Code Inspection Interval for VCSNS Third Ten Year Inservice Inspection13 September 2012Response to NRC Request for Additional Information Request for Weld Recategorization and Use of Alternative to ASME Code Inspection Interval for VCSNS Third Ten Year Inservice Inspection
RC-12-0110, LTR-PAFM-12-86-NP, Rev. 0, Flaw Tolerance Evaluation to Support Re-categorization of V. C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements.27 June 2012LTR-PAFM-12-86-NP, Rev. 0, Flaw Tolerance Evaluation to Support Re-categorization of V. C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements.
RC-12-0097, (VCSNS) Unit 1, Request for Weld Recategorization for VCSNS Steam Generator Nozzle to Safe End Welds (Preliminary Submittal - RR-III-08)21 June 2012(VCSNS) Unit 1, Request for Weld Recategorization for VCSNS Steam Generator Nozzle to Safe End Welds (Preliminary Submittal - RR-III-08)
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
IR 05000395/200800329 July 2008IR 05000395-08-003, on 04/01/2008 - 06/30/2008, Virgil C. Summer, Identification and Resolution of Problems
RC-07-0085, Virgil Summer - Request to Use Alternatives to ASME Code Section XI Requirements for Application of Weld Overlay Repairs (RR-III-05)1 June 2007Virgil Summer - Request to Use Alternatives to ASME Code Section XI Requirements for Application of Weld Overlay Repairs (RR-III-05)
IR 05000395/200300526 January 2004IR 05000395-03-005, on 09/28-12/27/2003, Virgil C. Summer Nuclear Station. Non-Cited Violations Noted
ML20217R01019 January 1998VC Summer Nuclear Station Refueling Outage 10 ISI Rept
ML20084Q88224 October 1994Rev 1 to Sce&G VC Summer Nuclear Station ASME Section XI Inservice Exam Manual for 2nd Insp Interval
ML20029E11129 December 1993Rev 2 to Quality Sys Procedure QSP-210, ISI Nde.
ML20064H47031 October 1993Nonproprietary Rev 1 to Westinghouse Delta 75 SG Design & Fabrication Info for VC Summer Nuclear Station
ML20104B80631 August 1992Nonproprietary Westinghouse Delta 75 SG Design & Fabrication Info for VC Summer Nuclear Station
Information Notice 1991-32, Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering15 May 1991Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering
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