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Category:Letter type:RC
MONTHYEARRC-22-0004, (Vcsns), Unit 1 - 2021 Annual Letter of Certification and Testing Results of the Public Alerting System2022-01-14014 January 2022
(Vcsns), Unit 1 - 2021 Annual Letter of Certification and Testing Results of the Public Alerting System
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 Licenses2018-12-28028 December 2018
(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 Licenses2018-12-21021 December 2018
ISFSI - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses
RC-18-0136, (Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683)2018-12-12012 December 2018
(Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683)
RC-18-0144, (Vcsns), Unit 1 - Core Operating Limits Report (COLR) for Cycle 252018-11-20020 November 2018
(Vcsns), Unit 1 - Core Operating Limits Report (COLR) for Cycle 25
RC-18-0126, (Vcsns), Unit 1 - Notification of an Intended Change a Commitment Date for Open Phase Condition (OPC) Made in RC-17-01692018-11-0909 November 2018
(Vcsns), Unit 1 - Notification of an Intended Change a Commitment Date for Open Phase Condition (OPC) Made in RC-17-0169
RC-18-0070, (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ...2018-10-0808 October 2018
(Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ...
RC-18-0067, (Vcsns), Unit 1 - License Amendment Request - LAR-16-00644 - Revise Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.22018-10-0808 October 2018
(Vcsns), Unit 1 - License Amendment Request - LAR-16-00644 - Revise Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2
RC-18-0123, NRC Request for Information Baseline Radiation Safety Inspection2018-10-0404 October 2018
NRC Request for Information Baseline Radiation Safety Inspection
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
RC-18-0112, (Vcsns), Unit 1 - Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2, D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.B.2 and 4.8.2.1.C.32018-09-27027 September 2018
(Vcsns), Unit 1 - Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2, D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.B.2 and 4.8.2.1.C.3
RC-18-0119, (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422, Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-09-19019 September 2018
(Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422, Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation
RC-18-0118, (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange2018-09-14014 September 2018
(Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange
RC-18-0116, (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information2018-09-11011 September 2018
(Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information
RC-18-0113, (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-08-31031 August 2018
(Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation
RC-18-0091, License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions2018-08-29029 August 2018
License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions
RC-18-0111, License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-08-24024 August 2018
License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation
RC-18-0100, (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information2018-08-22022 August 2018
(Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information
RC-18-0105, (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water ..2018-08-14014 August 2018
(Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water ..
RC-18-0102, Withdrawal of Request to Revise Technical Specifications to Correct an Administrative Error2018-08-10010 August 2018
Withdrawal of Request to Revise Technical Specifications to Correct an Administrative Error
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 Licenses2018-07-30030 July 2018
(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-18-0085, (Vcsns), Unit 1 - Notification of an Intended Change to a Commitment Made in RC-17-01262018-07-23023 July 2018
(Vcsns), Unit 1 - Notification of an Intended Change to a Commitment Made in RC-17-0126
RC-18-0090, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request...2018-07-12012 July 2018
(Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request...
RC-18-0089, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping2018-07-11011 July 2018
(Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping
RC-18-0084, Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Requ2018-07-0303 July 2018
Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Reques
RC-18-0082, Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping2018-07-0303 July 2018
Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping
RC-18-0079, Vigil C. Summer Nuclear Station (Vcsns), Unit 1 - Request to Revise Technical Specifications to Correct an Administrative Error2018-06-29029 June 2018
Vigil C. Summer Nuclear Station (Vcsns), Unit 1 - Request to Revise Technical Specifications to Correct an Administrative Error
RC-18-0074, Change of the Commitment Date of DRIB/105A&B Door Submittal2018-06-18018 June 2018
Change of the Commitment Date of DRIB/105A&B Door Submittal
RC-18-0060, (VCSNS) - Request to Revise Technical Specifications to Correct Administrative Error2018-05-30030 May 2018
(VCSNS) - Request to Revise Technical Specifications to Correct Administrative Error
RC-18-0064, (Vcsns), Unit 1 - Annual Commitment Change Summary Report2018-05-18018 May 2018
(Vcsns), Unit 1 - Annual Commitment Change Summary Report
RC-18-0063, Submittal of 10 CFR 72.48 Biennial Report for the Independent Spent Fuel Storage Installation2018-05-0202 May 2018
Submittal of 10 CFR 72.48 Biennial Report for the Independent Spent Fuel Storage Installation
RC-18-0056, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors2018-04-25025 April 2018
(Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors
RC-18-0059, Annual Radioactive Effluent Release Report2018-04-25025 April 2018
Annual Radioactive Effluent Release Report
RC-18-0046, License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information2018-04-19019 April 2018
License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information
RC-18-0036, (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information2018-04-0202 April 2018
(Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information
RC-18-0041, Report of Status of Decommissioning Funding2018-03-28028 March 2018
Report of Status of Decommissioning Funding
RC-17-0175, Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error2018-01-31031 January 2018
Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error
RC-18-0006, Independent Spent Fuel Storage Installation Re Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-01-25025 January 2018
Independent Spent Fuel Storage Installation Re Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses
RC-17-0169, Notification of an Intended Change of a Commitment Date for Open Phase Condition Made in RC-14-00192017-12-11011 December 2017
Notification of an Intended Change of a Commitment Date for Open Phase Condition Made in RC-14-0019
RC-17-0182, (VCSNS) - Anchor Darling Double Disc Gate Valve Information and Status2017-12-11011 December 2017
(VCSNS) - Anchor Darling Double Disc Gate Valve Information and Status
RC-17-0172, Notification of Personnel Changes2017-11-30030 November 2017
Notification of Personnel Changes
RC-17-0161, Submittal of Change of the Commitment Date of DRIB/105A&B Door2017-11-28028 November 2017
Submittal of Change of the Commitment Date of DRIB/105A&B Door
RC-17-0135, Annual Commitment Change Summary Report2017-11-0303 November 2017
Annual Commitment Change Summary Report
RC-17-0123, Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds2017-10-30030 October 2017
Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds
RC-17-0140, Transmittal of 10 CFR 50.59 Biennial Report2017-10-23023 October 2017
Transmittal of 10 CFR 50.59 Biennial Report
RC-17-0107, (Vcsns), Unit 1 - Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change2017-10-0606 October 2017
(Vcsns), Unit 1 - Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change
RC-17-0134, Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 12017-09-27027 September 2017
Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 1
RC-17-0126, Reply to a Notice of Violation, Per Inspection Report 05000395/20170022017-09-0606 September 2017
Reply to a Notice of Violation, Per Inspection Report 05000395/2017002
RC-17-0112, Special Report (Spr) 2017-007 Regarding Waste Gas Holdup System Explosive Gas Monitoring System Being Inoperable for Greater than Thirty Days2017-09-0101 September 2017
Special Report (Spr) 2017-007 Regarding Waste Gas Holdup System Explosive Gas Monitoring System Being Inoperable for Greater than Thirty Days
RC-17-0069, (Vcsns), Unit 1 - Quality Assurance Approval Certificate No. 0479, Transmittal of the Quality Assurance Program Description2017-08-30030 August 2017
(Vcsns), Unit 1 - Quality Assurance Approval Certificate No. 0479, Transmittal of the Quality Assurance Program Description
2022-01-14
[Table view]
Category:Report
MONTHYEARML23325A2022024-01-16016 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
ML19056A4132019-01-31031 January 2019
Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Cooling Water System Data
ML19056A4112019-01-31031 January 2019
Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Cooling Water Intake Structure Data
ML19056A4142019-01-31031 January 2019
Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Entrainment Performance Studies
ML19056A4102019-01-31031 January 2019
Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Source Water Physical Data
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
ML13072A0832013-01-31031 January 2013
12-4116.IPEC.V002, Revision 1, Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation: EA-12-051
2024-01-16
[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
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Application to Use Weighting Factors for External Exposure
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2022-02-18
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Jeffrey B. Archie Vice President,Nuclear Operations 803.345.4214 A scANA COMPANY February 19, 2008 RC-08-0006 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 APPLICATION TO USE WEIGHTING FACTORS FOR EXTERNAL EXPOSURE South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority, hereby requests Nuclear Regulatory Commission (NRC) approval to use weighting factors for calculating external whole body dose pursuant to footnote 2 to the "Organ Dose Weighting Factors" table in 10 CFR Part 20.1003. The application for this request is provided as Attachment I.
Specifically, SCE&G requests approval to use weighting factors specified in American National Standards Institute technical standard HPS N13.41 (HPS N13.41-1997, "Criteria for Performing Multiple Dosimetry," approved December 1996) for assessing effective dose equivalent (EDE) at VCSNS based on direct measurement of external exposures using personnel dosimeters.
As described in the application, approval would improve assessment of occupational dose to individuals from exposure to highly non-uniform radiation fields. The technical basis for this application is the consensus technical standard approved by the American National Standards Institute - Accredited HPS N13 Committee. The standard is practical and consistent with the organ or tissue weighting factors in 10 CFR Part 20.1003.
The NRC has given approval to use weighting factors for external exposure to the Florida Power and Light Company plants (St. Lucie Units 1 and 2, Turkey Point Units 3 and 4, Seabrook Station and Duane Arnold Energy Center) in a letter dated February 28, 2007 (Agencywide Documents Access and Management System [ADAMS]
Accession No. ML070530387). Additionally, the NRC has given recent approval to the Wolf Creek Generating Station in a letter dated August 23, 2007 (ADAMS Accession No. ML072220355). Also, the NRC has given similar approval to various other licensees in the past to use weighting factors for external exposures.
SCE&G I Virgil C.Summer Nuclear Station
Document Control Desk LTD 442 RC-08-0006 Page 2 of 2 VCSNS would like to begin using weighting factors for external exposures during the next refueling outage starting April 25, 2008. Therefore, SCE&G is requesting the approval of the subject application by April 15, 2008.
If you have any questions or require additional information, please contact Mr. Bruce L.
Thompson at (803) 931-5042.
Very truly yours, Oey Brch~ie GAR/JBA/dr Attachments Attachment I- Application to Use Weighting Factors for External Exposure Attachment I1: List of Commitments c: K. B. Marsh S. A. Byrne N. S. Cams J. H. Hamilton R. J. White V. M. McCree R. E.. Martin NRC Resident Inspector K. M. Sutton NSRC RTS (LTD 442)
File (810.32)
PRSF (RC-08-0006)
Document Control Desk Attachment I RC-08-0006 Page 1 of 6 ATTACHMENT I APPLICATION TO USE WEIGHTING FACTORS FOR EXTERNAL EXPOSURE
Document Control Desk Attachment I RC-08-0006 Page 2 of 6 APPLICATION TO USE WEIGHTING FACTORS FOR EXTERNAL EXPOSURE
1.0 INTRODUCTION
3 1.1 PURPOSE 3
1.2 REGULATORY EVALUATION
-3 5
2.0 TECHNICAL JUSTIFICATION 3 2.1 IMPROVED ASSESSMENT OF DOSE _3 2.2 COMPARTMENT FACTORS_4 2.3 CHEST COMPARTMENT 5 2.4 DOSIMETER SELECTION AND PLACEMENT 5 2.5 DOSE ASSIGNMENT 5 2.6 PRECEDENCE 6
3.0 CONCLUSION
6
Document Control Desk Attachment, I RC-08-0006 Page 3 of 6
1.0 INTRODUCTION
1.1 PURPOSE Pursuant to footnote 2 to the "Organ Dose Weighting Factors" table in 10 CFR Part 20.1003, VCSNS requests approval to use weighting factors for calculating external whole body dose.
Specifically, VCSNS requests approval to use weighting factors specified in American National Standards Institute technical standard HPS N13.41 (HPS N13.41-1997, "Criteria for Performing Multiple Dosimetry", approved December 1996) for assessing effective dose equivalent (EDE) based on direct measurement of external exposures using personnel dosimeters. The assigned EDE is the sum of each dosimeter measurement modified by its appropriate weighting factor.
1.2 REGULATORY EVALUATION
Dose limits in 10 CFR Part 20 are specified in the dose quantity total effective dose equivalent (TEDE). TEDE is defined in 20.1003 as the sum of the external dose quantity called deep dose equivalent (DDE),plus the internal dose quantity called committed effective dose equivalent.
Footnote 2, in the "Organ Dose Weighting Factors" table in 10 CFR 20.1003, permits the use of weighting factors for external exposure with prior NRC approval. VCSNS seeks NRC approval to use weighting factors to calculate the external exposure quantity EDE and to use EDE in place of DDE in the calculation of TEDE.
2.0 TECHNICAL JUSTIFICATION 2.1 IMPROVED ASSESSMENT OF DOSE In uniform radiation fields, the dosimeter used to measure whole body dose is worn on the chest. The dosimeter measures radiation exposure using an operational dose quantity called DDE.
When the radiation field is highly non-uniform, either the chest dosimeter is moved to the part of the whole body expected to receive the highest dose or additional dosimeters are worn so that the highest Whole body dose can be measured.
Difficulties arise because the annual occupational dose limit is based on the stochastic risk from whole body exposure, which is related to the dose quantity EDE. While the
Document Control Desk Attachment I RC-08-0006 Page 4 of 6 use of DDE as a surrogate quantity to approximate EDE works well in uniform radiation fields, in highly non-uniform radiation fields, a more accurate estimate of EDE is needed to improve the assessment of occupational dose.
2.2 COMPARTMENT FACTORS HPS N13.41 provides a method for assessing EDE based on measurements of DDE at specific areas of the body called "compartments" and applying appropriate weighting factors called "compartment factors". A compartment factor "relates the fractional risk to the organs underlying the measurement location to the total risk from uniform irradiation of the whole body."
HPS N13.41, Appendix A describes how the 10 CFR Part 20 organ or tissue weighting factors are apportioned to each "compartment" based on the associated underlying organs and tissues. The resulting compartment factors used to calculate EDE are listed below:
HPS N13.41 COMPARTMENT FACTORS Compartment Name Compartment Factor Head and Neck 0.10 Thorax, above the diaphragm 0.38 Abdomen, including the pelvis 0.50 Upper right arm 0.005 Upper left arm 0.005 Right thigh 0.005 Left thigh 0.005
Document Control Desk Attachment I RC-08-0006 Page 5 of 6 2.3 CHEST COMPARTMENT Consistent with VCSNS's current practice, normally a chest and back dosimeter are used to measure the thorax compartment and a groin dosimeter is used to measure the abdomen compartment. The thorax compartment is then assigned the higher of the chest dosimeter and back dosimeter readings. Under certain circumstances, a single dosimeter may be used to monitor the thorax and abdomen compartments which will be called the chest compartment. If this does occur, the weighting factor would be 0.88 (summed).
2.4 DOSIMETER SELECTION AND PLACEMENT NRC Inspection Procedure 71121.01, "Access Control to Radiologically Significant Areas" issue date 03/06/02, Section 03.04(c), "Dosimeter Selection and Placement Criteria," will be used to provide adequate criteria for monitoring the part of the body expected to receive the highest dose.
VCSNS will monitor the part of the whole body within each compartment (and/or combined compartment) that receives the highest dose. VCSNS Health Physics Procedure HPP-041 1, "Monitoring Exposure with Multiple Badging", provides guidance for determining dosimeter selection and placement and will be revised consistent with that found in NRC Inspection Procedure Attachment 71121.01, dated 03/06/02.
VCSNS Health Physics Procedure HPP-0517, "Multiple Whole Body and Extremity Badging Exposure Calculations", provides guidance for tracking and calculating an individual's radiation exposure and will. be revised such that the EDE (when used) will be reported in place of the DDE, as discussed in NRC Regulatory Issue Summary 2004-01.
2.5 DOSE ASSIGNMENT The DDE for each compartment will be determined from dosimeters worn at that location. When no dosimeter is worn at a particular compartment, DDE will be determined from the dosimeter positioned where the exposure is judged to be similar.
The assigned EDE will be the sum of each DDE measurement multiplied by its appropriate compartment factor.
If an eye dosimeter is not used, the assigned lens dose equivalent (LDE) will be the higher of the head or chest dosimeters. The assigned shallow dose equivalent (SDE) will be the highest of any whole body dosimeter.
Document Control Desk Attachment I RC-08-0006 Page 6 of 6 2.6 PRECEDENCE The NRC has given approval to use weighting factors for external exposure to the Florida Power and Light Company plants (St. Lucie Units 1 and 2, Turkey Point Units 3 and 4, Seabrook Station and Duane Arnold Energy Center) in a letter dated February 28, 2007 (Agencywide Documents Access and Management System [ADAMS]
Accession No. ML070530387). Additionally, the NRC has given recent approval to the Wolf Creek Generating Station in a letter dated August 23, 2007 (ADAMS Accession No. ML072220355). Also, the NRC has given similar approval to various other licensees in the past to use weighting factors for external exposures.
3.0 CONCLUSION
Accurate assessment of occupational dose from external sources of radiation in highly non-uniform radiation fields requires a method for assessing EDE. NRC approval of this application will improve the accuracy of licensee assessment of occupational dose.
VCSNS will assess EDE based on the consensus technical standard, HPS N13.41.
This standard was approved by the American National Standards Institute - Accredited HPS N13 Committee on 20 June 1996. At the time of balloting, the HPS N13 Committee membership included representatives from the Nuclear Regulatory Commission and the National Council on Radiation Protection and Measurements.
The HPS N13.41 consensus technical standard has previously been approved for use by the NRC for evaluating occupational dose to medical personnel wearing lead aprons in Regulatory Issue Summary 2002-06, "Evaluation Occupational Dose for Individuals Exposed to NRC-Licensed Material and Medical X-Rays," dated April 16, 2002.
The proposed method will monitor the part of the whole body expected to receive the highest dose using the criteria for dosimeter selection and placement found in current NRC inspection procedures.
Document Control Desk Attachment II RC-08-0006 Page 1 of i ATTACHMENT II LIST OF COMMITMENTS The following table identifies those actions committed to by VCSNS in this document.
Any other statements in this submittal are provided for information purposes and are not considered regulatory commitments. Please direct any questions regarding these commitments to Mr. Bruce L. Thompson, Manager Nuclear Licensing at VCSNS, (803) 931-5042.
REGULATORY COMMITMENT DUE DATE VCSNS will monitor the part of the whole body within Within 90 days of NRC each compartment (and/or combined compartment) that Approval.
receives the highest dose. VCSNS Health Physics Procedure HPP-041 1, "Monitoring Exposure with Multiple Badging", provides guidance for determining dosimeter selection and placement and will be revised consistent with that found in NRC Inspection Procedure 1121.01, dated 03/06/02.
VCSNS Health Physics Procedure HPP-0517, "Multiple Within 90 days of NRC Whole Body and Extremity Badging Exposure Approval.
Calculations", provides guidance for tracking and calculating an individual's radiation exposure and will be revised such that the EDE (when used) will be reported in place of the DDE, as discussed in NRC Regulatory Issue Summary 2004-01.
Based on the NRC's approval of this request, VCSNS Within 90 days of NRC will account for dose consistent with the guidance of the Approval.
standard in applicable Health Physics procedures, as follows:
The DDE for each compartment will be determined from dosimeters worn at that location. When no dosimeter is worn at a particular compartment, DDE will be determined from the dosimeter positioned where the exposure is judged to be similar. The assigned EDE will be the sum of each DDE measurement multiplied by its appropriate compartment factor.
If an eye dosimeter is not used, the assigned lens dose equivalent (LDE) will be the higher of the head or chest dosimeters. The assigned shallow dose equivalent (SDE) will be the highest of any whole body dosimeter.
