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Category:Letter
MONTHYEARIR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public IR 05000395/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000395/2024402 IR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24190A4012024-08-19019 August 2024 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Dominion Energy Letter Dated May 30, 2024 IR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000395/20240112024-06-26026 June 2024 – Comprehensive Engineering Team Inspection Report 05000395/2024011 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d ML24108A1432024-04-17017 April 2024 (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24087A2262024-03-26026 March 2024 License Amendment Request - Inverter Allowed Outage Time Extension Response to Request for Additional Information ML24088A2062024-03-26026 March 2024 Annual Operating Report ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. ML24067A0232024-03-0707 March 2024 (Vcsns), Unit 1 - Readiness for 95001 Supplemental Inspection; EA-23-093 IR 05000395/20230062024-02-28028 February 2024 Annual Assessment Letter for Virgil C. Summer Nuclear Station - Report 05000395/2023006 IR 05000395/20244032024-02-27027 February 2024 Security Baseline Inspection Report 05000395/2024403 ML24057A1132024-02-22022 February 2024 Special Report 2024-001 Waste Gas System Inoperability ML24051A0112024-02-20020 February 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Proposed Project Location or May Be Affected by Proposed Project for V.C. Summer SLR ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24032A3062024-02-15015 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24040A1802024-02-12012 February 2024 Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000395/20244012024-02-0808 February 2024 Security Baseline Inspection Report 05000395/2024401 ML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter–Nrc Inspection Report 05000395/2023091 2024-09-26
[Table view] Category:Report
MONTHYEARML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report ML23024A1542023-01-23023 January 2023 Proposed Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Potential Subsequent License Renewal Activity ML22286A1392022-10-13013 October 2022 Special Report 2022-005, Inoperable Radiation Monitoring Instrumentation Channel ML22279A9892022-09-23023 September 2022 Restoration Project - Final Status Survey Release Record North Protected Area Yard Survey Unit 12201C - Revision 2 ML22069B1172022-03-10010 March 2022 Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination) ML22049B0242022-02-18018 February 2022 2021 Q4 Summary Page IR 05000395/20210052021-08-24024 August 2021 Updated Inspection Plan for Virgil C.Summer Nuclear Station, Unit 1 (Report 05000395/2021005) ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML20296A7082020-10-22022 October 2020 (VCSNS) Unit 1 - Alternative Requests RR-4-25 for Elimination of Reactor Pressure Vessel Threads in Flange Examination for the Remainder of the Fourth 10-Year ISI Interval ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20212L5762020-07-30030 July 2020 Annual Commitment Change Summary Report ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML19204A1172019-07-17017 July 2019 Vigil C. Summer, Unit 1, Proposed Alternative Request RR-4-20 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML19122A5172019-05-0202 May 2019 Annual Commitment Change Summary Report ML19056A4122019-01-31031 January 2019 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Source Water Baseline Biological Characterization Data ML19056A4112019-01-31031 January 2019 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Cooling Water Intake Structure Data ML19056A4132019-01-31031 January 2019 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Cooling Water System Data ML19056A4102019-01-31031 January 2019 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Source Water Physical Data ML19056A4142019-01-31031 January 2019 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Entrainment Performance Studies RC-18-0117, (Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk Assessment2018-09-28028 September 2018 (Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk Assessment ML18179A4162018-06-28028 June 2018 ECCS Evaluation Model Revisions Report RC-18-0064, (Vcsns), Unit 1 - Annual Commitment Change Summary Report2018-05-18018 May 2018 (Vcsns), Unit 1 - Annual Commitment Change Summary Report ML17206A4592017-09-26026 September 2017 Staff Assessment of Response to Information Request Pursuant to 10 CFR 50.54(F) - Recommendation 9.3 of the Near-Term Task Force, Communications Assessment RC-17-0089, Focused Evaluation for External Flooding2017-06-30030 June 2017 Focused Evaluation for External Flooding RC-17-0057, Emergency Core Cooling System Evaluation Model Revisions Annual Report2017-05-15015 May 2017 Emergency Core Cooling System Evaluation Model Revisions Annual Report ML19056A4152017-02-28028 February 2017 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Appendix B, Entrainment Study, 2016 and Revised 2017 RC-16-0170, Mitigating Strategies Assessment (MSA) Report Submittal2016-12-22022 December 2016 Mitigating Strategies Assessment (MSA) Report Submittal RC-16-0143, (VCSNS) Unit 1 - Report of Full Compliance and Final Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design...2016-10-31031 October 2016 (VCSNS) Unit 1 - Report of Full Compliance and Final Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design... RC-16-0081, Submittal of 2015 Annual Commitment Change Summary Report2016-06-22022 June 2016 Submittal of 2015 Annual Commitment Change Summary Report RC-16-0086, Special Report 2016-003 Regarding Fire Barrier Not Restored to Operability Status within 7 Days of Inoperability2016-06-0909 June 2016 Special Report 2016-003 Regarding Fire Barrier Not Restored to Operability Status within 7 Days of Inoperability RC-16-0008, Transmittal of Expedited Seismic Evaluation Process Report, Revision 12016-01-28028 January 2016 Transmittal of Expedited Seismic Evaluation Process Report, Revision 1 ML15296A3772015-11-0303 November 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request- Flood Causing Mechanism Reevaluation RC-15-0153, Submittal of 10 CFR 50.59 Biennial Report2015-10-0707 October 2015 Submittal of 10 CFR 50.59 Biennial Report ML15194A0552015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 Fukushima Dai-Ichi RC-15-0020, Attachment 2 - Ihi Southwest Inner Diameter Examination Data, Part 2 of 22015-02-25025 February 2015 Attachment 2 - Ihi Southwest Inner Diameter Examination Data, Part 2 of 2 ML15061A0332015-02-25025 February 2015 Attachment 2 - Ihi Southwest Inner Diameter Examination Data, Part 2 of 2 ML14314A0332014-11-0505 November 2014 Submittal Special Report (Spr) 2014-006 ML14261A2762014-09-18018 September 2014 Draft September 23, 2014, Category 1 Public Meeting with V. C. Summer - Draft License Amendment Related to Approval of the Technical Support Center ML14141A4612014-06-0606 June 2014 Staff 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 RC-14-0048, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2014-03-26026 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident ML14051A3632014-03-0505 March 2014 Closure Letter Concerning 2012 Annual Emergency Core Cooling System Evaluation Model Revisions Report (TAC No. Mf 2722) ML19056A4082014-02-28028 February 2014 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Thermal Mixing Zone Evaluation, Addendum: Additional Modeling Cases for Revised Reservoir Ambient and Discharge Temperatures ML14034A3392014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14037A2282014-02-21021 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Virgil C. Summer Nuclear Station, Unit 1, TAC MF2338 ML14010A4152014-01-30030 January 2014 Staff 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 ML13309B0532013-11-0404 November 2013 ECCS Evaluation Model Revisions 30-Day Report RC-13-0130, WCAP-17758-NP, Rev. 0, Technical Basis for Westinghouse Embedded Flaw Repair for V.C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles and Attachment Welds.2013-08-31031 August 2013 WCAP-17758-NP, Rev. 0, Technical Basis for Westinghouse Embedded Flaw Repair for V.C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles and Attachment Welds. RC-13-0038, Flooding Hazard Reevaluation Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task.2013-03-12012 March 2013 Flooding Hazard Reevaluation Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task. RC-13-0037, Permanent ILRT Interval Extension Risk Impact Assessment2013-03-0101 March 2013 Permanent ILRT Interval Extension Risk Impact Assessment 2024-05-31
[Table view] Category:Miscellaneous
MONTHYEARML22286A1392022-10-13013 October 2022 Special Report 2022-005, Inoperable Radiation Monitoring Instrumentation Channel ML22049B0242022-02-18018 February 2022 2021 Q4 Summary Page IR 05000395/20210052021-08-24024 August 2021 Updated Inspection Plan for Virgil C.Summer Nuclear Station, Unit 1 (Report 05000395/2021005) ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20212L5762020-07-30030 July 2020 Annual Commitment Change Summary Report ML19122A5172019-05-0202 May 2019 Annual Commitment Change Summary Report ML18179A4162018-06-28028 June 2018 ECCS Evaluation Model Revisions Report RC-18-0064, (Vcsns), Unit 1 - Annual Commitment Change Summary Report2018-05-18018 May 2018 (Vcsns), Unit 1 - Annual Commitment Change Summary Report ML17206A4592017-09-26026 September 2017 Staff Assessment of Response to Information Request Pursuant to 10 CFR 50.54(F) - Recommendation 9.3 of the Near-Term Task Force, Communications Assessment RC-17-0057, Emergency Core Cooling System Evaluation Model Revisions Annual Report2017-05-15015 May 2017 Emergency Core Cooling System Evaluation Model Revisions Annual Report RC-16-0170, Mitigating Strategies Assessment (MSA) Report Submittal2016-12-22022 December 2016 Mitigating Strategies Assessment (MSA) Report Submittal RC-16-0081, Submittal of 2015 Annual Commitment Change Summary Report2016-06-22022 June 2016 Submittal of 2015 Annual Commitment Change Summary Report RC-16-0086, Special Report 2016-003 Regarding Fire Barrier Not Restored to Operability Status within 7 Days of Inoperability2016-06-0909 June 2016 Special Report 2016-003 Regarding Fire Barrier Not Restored to Operability Status within 7 Days of Inoperability RC-16-0008, Transmittal of Expedited Seismic Evaluation Process Report, Revision 12016-01-28028 January 2016 Transmittal of Expedited Seismic Evaluation Process Report, Revision 1 ML15296A3772015-11-0303 November 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request- Flood Causing Mechanism Reevaluation RC-15-0153, Submittal of 10 CFR 50.59 Biennial Report2015-10-0707 October 2015 Submittal of 10 CFR 50.59 Biennial Report ML15194A0552015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 Fukushima Dai-Ichi RC-15-0020, Attachment 2 - Ihi Southwest Inner Diameter Examination Data, Part 2 of 22015-02-25025 February 2015 Attachment 2 - Ihi Southwest Inner Diameter Examination Data, Part 2 of 2 ML15061A0332015-02-25025 February 2015 Attachment 2 - Ihi Southwest Inner Diameter Examination Data, Part 2 of 2 ML14314A0332014-11-0505 November 2014 Submittal Special Report (Spr) 2014-006 ML14261A2762014-09-18018 September 2014 Draft September 23, 2014, Category 1 Public Meeting with V. C. Summer - Draft License Amendment Related to Approval of the Technical Support Center ML14141A4612014-06-0606 June 2014 Staff 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 ML14051A3632014-03-0505 March 2014 Closure Letter Concerning 2012 Annual Emergency Core Cooling System Evaluation Model Revisions Report (TAC No. Mf 2722) ML14010A4152014-01-30030 January 2014 Staff 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 ML13309B0532013-11-0404 November 2013 ECCS Evaluation Model Revisions 30-Day Report RC-12-0104, Submittal of ECCS Evaluation Model Revisions 30-Day Report2012-10-16016 October 2012 Submittal of ECCS Evaluation Model Revisions 30-Day Report RC-15-0020, Attachment 5 - Westinghouse LTR-PAFM-12-86 Flaw Tolerance Evaluation to Support Re-Categorization of V.C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements2012-07-31031 July 2012 Attachment 5 - Westinghouse LTR-PAFM-12-86 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-11-0178, Submittal of Twenty-Second Report to 10 CFR 50.59(d)(2) Changes2011-11-0404 November 2011 Submittal of Twenty-Second Report to 10 CFR 50.59(d)(2) Changes RC-11-0119, 30-Day Special Report (Rt 2800) Groundwater Protection Initiative (GPI) - Voluntary Special Report for On-Site Liquid Effluent Line Leak2011-08-0303 August 2011 30-Day Special Report (Rt 2800) Groundwater Protection Initiative (GPI) - Voluntary Special Report for On-Site Liquid Effluent Line Leak ML1019304172010-05-0606 May 2010 Tritium Database Report ML0921001332009-07-24024 July 2009 Submittal of Special Report (Spr) 09-0001 RC-09-0050, Submittal of 2008 Emergency Core Cooling System (ECCS) Evaluation Model Revisions Report2009-05-14014 May 2009 Submittal of 2008 Emergency Core Cooling System (ECCS) Evaluation Model Revisions Report ML0810701772008-04-11011 April 2008 Submittal of Special Report 2008-001, Pursuant to Requirements of Technical Specification 3.3.3.10.a RC-08-0019, Request for Use of Higher Assigned Protection Factors with Use of French-Designed Air-Line Respirator Equipment2008-02-19019 February 2008 Request for Use of Higher Assigned Protection Factors with Use of French-Designed Air-Line Respirator Equipment RC-08-0006, Application to Use Weighting Factors for External Exposure2008-02-19019 February 2008 Application to Use Weighting Factors for External Exposure RC-07-0169, Virgil Summer - 10 CFR 50.59 Biennial Report Covering the Period from October 1, 2005 Until October 1, 20072007-11-0606 November 2007 Virgil Summer - 10 CFR 50.59 Biennial Report Covering the Period from October 1, 2005 Until October 1, 2007 RC-07-0081, ECCS Evaluation Model Revisions Annual Report2007-06-0101 June 2007 ECCS Evaluation Model Revisions Annual Report RC-06-0216, License Condition 2.C(5), 14-Day Report on Exceeding Surveillance Frequency2006-12-13013 December 2006 License Condition 2.C(5), 14-Day Report on Exceeding Surveillance Frequency RC-06-0205, ECCS Evaluation Model Revisions Report2006-12-0404 December 2006 ECCS Evaluation Model Revisions Report RC-06-0202, V. C. Summer - ECCS Evaluation Model Revisions Report, Addresses the Effect of Using a Finer Break Spectrum2006-11-15015 November 2006 V. C. Summer - ECCS Evaluation Model Revisions Report, Addresses the Effect of Using a Finer Break Spectrum RC-06-0196, Special Report (Spr) 2006-0052006-10-27027 October 2006 Special Report (Spr) 2006-005 RC-05-0076, Operating License, Special Report (Spr 2005-001)2005-05-19019 May 2005 Operating License, Special Report (Spr 2005-001) ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0406307712004-02-25025 February 2004 Transmittal of Semi-Annual Fitness-for-Duty Report for Period Ending December 31, 2003 2022-02-18
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Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 A SCANA COMPANY May 14, 2009 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 ECCS EVALUATION MODEL REVISIONS REPORT South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority hereby submits the 2008 Emergency Core Cooling System (ECCS) Evaluation Model Revisions Annual Report for the Virgil C.Summer Nuclear Station (VCSNS). This report is being submitted pursuant to 10 CFR 50.46, which requires licensees to notify the NRC on at least an annual basis of corrections to or changes in the ECCS Evaluation Models.Summary sheets describing changes and enhancements to the ECCS Evaluation Models for 2008 are included in Attachment I. Peak Clad Temperature (PCT) sheets are included in Attachment I1.If you have any questions, please call Mr. Bruce L. Thompson at (803) 931-5042.GAR/JBA/dr Attachments c: K. B. Marsh S. A. Byrne N. S. Carns J. H. Hamilton R. J. White K. J. Browne L. A. Reyes R. E. Martin NRC Resident Inspector K. M. Sutton NSRC RTS (LTD 321, RR 8375)File (818.02-17)
PRSF (RC-09-0050)
SCE&G I Virgil C. Summer Nuclear Station
- P. 0. Box 88 .Jenkinsville, South Carolina 29065 -T (803) 345.5209 www.scona.com Document Control Desk Attachment I LTD 321 RC-09-0050 Page 1 of 5 Attachment I Changes and Enhancements to the ECCS Evaluation Models for 2008 Document Control Desk Attachment I LTD 321 RC-09-0050 Page 2 of 5 ERRORS IN REACTOR VESSEL LOWER PLENUM SURFACE AREA CALCULATIONS (Non-Discretionary Change)Background Two errors were discovered in the calculations of reactor vessel lower plenum surface area. The corrected values have been evaluated for impact on current licensing-basis analysis results and will be incorporated on a forward-fit basis. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP- 13451.Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The differences in vessel lower plenum surface area are relatively minor and would be expected to produce a negligible effect on small break LOCA analysis results, leading to an estimated PCT impact of 0°F for 10 CFR 50.46 reporting purposes.DISCREPANCY IN METAL MASSES USED FROM DRAWINGS (Non-Discretionary Change)Background Discrepancies were discovered in the use of metal masses from drawings.
The updated reactor vessel metal masses and fluid volumes have been evaluated for impact on current licensing-basis analysis results and will be incorporated on a forward-fit basis. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-13451.Affected Evaluation Model 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The differences in the reactor vessel metal mass and fluid volume are relatively minor and would be expected to produce a negligible effect on small break LOCA analysis results, leading to an estimated PCT impact of 0 0 F for 10 CFR 50.46 reporting purposes.
Document Control Desk Attachment I LTD 321 RC-09-0050 Page 3 of 5 GENERAL CODE MAINTENANCE (Discretionary Change)Background Various changes have been made to enhance the usability of the codes and to help preclude errors in analyses.
This includes items such as modifying input variable definitions, units, and defaults; improving the input diagnostic checks; enhancing the code output; optimizing active coding; and, eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451.
Affected Evaluation Model 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The nature of these changes leads to an estimated PCT impact of 0°F.,GENERAL CODE MAINTENANCE (Discretionary Change)Background A number of coding changes were made as part of normal code maintenance.
Examples include additional information in code outputs, improved automation and diagnostics in the codes, increased code dimensions, and general code cleanup. All of these changes are considered to be Discretionary Changes in accordance with Section 4.1.1 of WCAP- 13451.Affected Evaluation Model 1996 Westinghouse Best Estimate Large Break LOCA Evaluation Model Estimated Effect The nature of these changes leads to an estimated PCT impact of 0°F for 10 CFR 50.46 reporting purposes.
Document Control Desk Attachment I LTD 321 RC-09-0050 Page 4 of 5 HOTSPOT BURST TEMPERATURE LOGIC ERRORS (Non-Discretionary Change)Background The HOTSPOT code has been updated to incorporate the following corrections to the burst temperature logic: (1) change the rod internal pressure used to calculate the cladding engineering hoop stress from the value in the previous time step to the value in the current time step; (2)revise the average cladding heat-up rate calculation to reset selected variables to zero at the beginning of each trial and use the instantaneous heat-up rate when fewer than five values are available; and, (3) reflect the assumed saturation of ramp rate effects above 28°C/s for Zircaloy-4 cladding from Equation 7-66 of Reference
- 1. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP- 13451.Affected Evaluation Model 1996 Westinghouse Best Estimate Large Break LOCA Evaluation Model Estimated Effect Sample calculations for each change showed no effect on peak cladding temperature, leading to an estimated impact of 0°F for 10 CFR 50.46 reporting purposes.Reference 1. WCAP-12945-P-A, Volume 1 (Revision
- 2) and Volumes 2-5 (Revision 1),"Code Qualification Document for Best Estimate LOCA Analysis," S. M. Bajorek et al., March 1998.
Document Control Desk Attachment I LTD 321 RC-09-0050 Page 5 of 5 MODELING OF ANNULAR PELLETS (Non-Discretionary Change)Background It was identified that annular pellets were not addressed in the VCSNS small break loss-of-coolant accident (SBLOCA) analysis of record (AOR). A plant specific evaluation was completed to estimate the effect of modeling annular pellets in the VCSNS SBLOCA analysis.This change represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.Affected Evaluation Model 1985 Appendix K Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect A plant specific evaluation of annular pellets on the limiting peak cladding temperature (PCT)and limiting transient oxidation break sizes was performed.
The evaluation determined that annular pellets have a negligible effect on the VCSNS SBLOCA analysis results, leading to an estimated PCT impact of 0 0 F for 10 CFR 50.46 reporting purposes.PCT ASSESSMENT OF TRANSVERSE MOMENTUM CELLS FOR ZERO CROSS-FLOW BOUNDARY CONDITION ERROR IN THE VCSNS BEST-ESTIMATE LARGE BREAK LOCA ANALYSIS (Non-Discretionary Change)Background An error was identified in the calculation of the transverse momentum cells for zero cross-flow boundary condition during the course of performing a Best-Estimate Large Break LOCA (BE LBLOCA) evaluation to assess the impact of a conversion of the barrel-baffle region to an upflow configuration.
A plant specific evaluation was performed using the WCOBRA/TRAC code to estimate the effect of the error discovered in the VCSNS BE LBLOCA analysis.Affected Evaluation Model 1996 Westinghouse Best Estimate Large Break LOCA Evaluation Model Estimated Effect The VCSNS Reference Transient was re-run using WCOBRA/TRAC to establish an estimated effect on the PCT. This evaluation resulted in a I°F increase in PCT during the Blowdown period, a 9°F reduction in PCT during the Reflood 1 period, and a 14'F reduction in PCT during the Reflood 2 period. Based on these results, it is concluded that VCSNS continues to maintain a margin of safety to the limits prescribed by 10 CFR 50.46.
Document Control Desk Attachment II LTD 321 RC-09-0050 Page 1 of 7 Attachment II PCT Rackup Sheets Document Control Desk Attachment II LTD 321 RC-09-0050 Page 2 of 7 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name: V. C. Summer Utility Name: South Carolina Electric & Gas Revision Date: 1/27/09 Composite Analysis Information EM: CQD (1996) Analysis Date: 2/3/03 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.7 Fuel: Vantage + SGTP (%): 10 Notes: Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt Clad Temp ('F) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1988 1 PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS
- 1. Backfit Through 2001 Reporting Year 0 2 2. Revised Blowdown Heatup Uncertainty Distribution 5 3 B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Fan Cooler Performance Increase 2 2 C. 2008 ECCS MODEL ASSESSMENTS
- 1. Transverse Momentum Cells for Zero Cross-flow Boundary Condition
-14 4 Error D. OTHER 1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 1981
References:
- 1. WCAP- 16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C.Summer Nuclear Station," June 2003.2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.4. LTR-LIS-08-578, Revision 2, "Large Break LOCA Evaluation for V. C. Summer (CGE) Upflow Conversion and Assessment of Transverse Momentum Cells for Zero Cross-flow Boundary Condition Error," January 2009.Notes: None Document Control Desk Attachment II LTD 321 RC-09-0050 Page 3 of 7 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name: V. C. Summer Utility Name: South Carolina Electric & Gas Revision Date: 1/27/09 Blowdown Analysis Information EM: CQD (1996) Analysis Date: 2/3/03 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.7 Fuel: Vantage + SGTP (%): 10 Notes: Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt Clad Temp ('F) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1860 1 PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS
- 1. Backfit Through 2001 Reporting Year 0 2 2. Revised Blowdown Heatup Uncertainty Distribution 49 3 B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Fan Cooler Performance Increase 0 2 C. 2008 ECCS MODEL ASSESSMENTS
- 1. Transverse Momentum Cells for Zero Cross-flow Boundary Condition 1 4 Error D. OTHER 1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1910
References:
- 1. WCAP-16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C.Summer Nuclear Station," June 2003.2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.4. LTR-LIS-08-578, Revision 2, "Large Break LOCA Evaluation for V. C. Summer (CGE) Upflow Conversion and Assessment of Transverse Momentum Cells for Zero Cross-flow Boundary Condition Error," January 2009.Notes: None Document Control Desk Attachment II LTD 321 RC-09-0050 Page 4 of 7 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name: V. C. Summer Utility Name: South Carolina Electric & Gas Revision Date: 1/27/09 Reflood 1 Analysis Information EM: CQD (1996) Analysis Date: 2/3/03 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.7 Fuel: Vantage + SGTP (%): 10 Notes: Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt Clad Temp ('F) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1808 1 PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS
- 1. Backfit Through 2001 Reporting Year 0 2 2. Revised Blowdown Heatup Uncertainty Distribution 5 3 B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Fan Cooler Performance Increase 1 2 C. 2008 ECCS MODEL ASSESSMENTS
- 1. Transverse Momentum Cells for Zero Cross-flow Boundary Condition
-9 4 Error D. OTHER 1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 1805
References:
- 1. WCAP- 16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C.Summer Nuclear Station," June 2003.2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.4. LTR-LIS-08-578, Revision 2, "Large Break LOCA Evaluation for V. C. Summer (CGE) Upflow Conversion and Assessment of Transverse Momentum Cells for Zero Cross-flow Boundary Condition Error," January 2009.Notes: None Document Control Desk Attachment II LTD 321 RC-09-0050 Page 5 of 7 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name: Utility Name: V. C. Summer South Carolina Electric & Gas Revision Date: 1/27/09 Analysis Information EM: CQD (1996) Analysis Date: 2/1/03 Limiting B]FQ: 2.5 FdH: 1.7 Fuel: Vantage + SGTP (%): 10 Notes: Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt Reflood 2 reak Size: Guillotine Clad Temp ('F)LICENSING BASIS Analysis-Of-Record PCT 1988 PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS
- 1. Backfit Through 2001 Reporting Year 0 2. Revised Blowdown Heatup Uncertainty Distribution 5 B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Fan Cooler Performance Increase 2 C. 2008 ECCS MODEL ASSESSMENTS
- 1. Transverse Momentum Cells for Zero Cross-flow Boundary Condition
-14 Error Ref.Notes 1 2 3 2 4 D. OTHER 1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1981
References:
- 1. WCAP- 16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C.Summer Nuclear Station," June 2003.2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.4. LTR-LIS-08-578, Revision 2, "Large Break LOCA Evaluation for V. C. Summer (CGE) Upflow Conversion and Assessment of Transverse Momentum Cells for Zero Cross-flow Boundary Condition Error," January 2009.Notes: None Document Control Desk Attachment II LTD 321 RC-09-0050 Page 6 of 7 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: V. C. Summer Utility Name: South Carolina Electric & Gas Revision Date: 1/27/09 Analysis Information EM: NOTRUMP Analysis Date: 9/12/06 Limiting Break Size: 3 Inch FQ: 2.4 FdH: 1.62 Fuel: Vantage + SGTP (%): 10 Notes: Clad Temp ('F) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1775 9 (a)PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS
- 1. None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. None 0 C. 2008 ECCS MODEL ASSESSMENTS
- 1. None 0 D. OTHER 1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1775
References:
I. CGE-94-205, "South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Notification and Reporting Information," February 8, 1994.2. CGE-94-228, "South Carolina Electric and Gas Company, Virgil C. Summer Station, SBLOCTA Axial Nodalization," October 27, 1994.3. CGE-95-201, "South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Notification and Reporting Information," February 3, 1995.4. CGE-96-202, "South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Annual Notification and Reporting," February 9, 1996.5. CGE-96-213, "South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Small Break LOCA Notification and Reporting," July 8, 1996.6. CGE-00-044, "South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, 10 CFR 50.46 Appendix K (BART / BASH / NOTRUMP) Evaluation Model, Mid-Year Notification and Reporting for 2000," June 30, 2000.7. CGE-03-80, "10 CFR 50.46 Mid-Year Notification and Reporting for 2003," January 2004.8. LTR-LIS-06-344, "Transmittal of Updated V. C. Summer SBLOCA PCT Rackup Sheets," November 2006.9. LTR-LIS-06-662, Transmittal of V. C. Summer SBLOCTA PCT Rackup Sheets for HHSI Throttle Valve Replacement," November 2006.
Document Control Desk Attachment II LTD 321 RC-09-0050 Page 7 of 7 Notes: (a) The Rebaseline Analysis includes the impacts of the following model assessments:
1 -LUCIFER Error Corrections (Ref. 1)2-Effect of SI in Broken Loop (Ref. 1)3-Effect of Improved Condensation Model (Ref. 1)4-Axial Nodalization, RIP Model Revision and SBLOCTA Error Corrections Analysis (Ref. 2)5-Boiling Heat Transfer Error (Ref. 3)6-Steam Line Isolation Logic Error (Ref. 3)7-NOTRUMP Specific Enthalpy Error (Ref. 4)8-SALIBRARY Double Precision Error (Ref. 4)9-SBLOCTA Fuel Rod Initialization Error (Ref. 5)10-NOTRUMP Mixture Level Tracking / Region Depletion Errors (Ref. 6)1 I-NOTRUMP Bubble Rise / Drift Flux Model Inconsistency Corrections (Ref. 7)12-Refined Break Spectrum (Ref. 8)13-High Head Safety Injection (HHSI) Flow Increase (Ref. 9)