Letter Sequence Response to RAI |
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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:Response to Request for Additional Information (RAI)
MONTHYEARML22353A5462022-12-19019 December 2022
(Vcsns), Unit 1 - Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request
ML22300A2202022-10-27027 October 2022
(VCSNS) Unit 1, Alternative Request Rr-4-26 Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination) RAI
ML22020A2262022-01-20020 January 2022
Response to Request for Additional Information to License Amendment Request LAR-20-203 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency
ML21180A4052021-06-29029 June 2021
(Vcsns), Unit 1 - Supplement to Request for Additional Information Regarding RF-25 Stem Generator Tube Inspection Report
ML21168A2612021-06-17017 June 2021
(Vcsns), Unit 1 - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors - Final Supplemental Response
ML21154A1802021-06-0303 June 2021
Response to NRC Request for Additional Information Regarding RGF-25 Steam Generator Tube Inspection Report
ML21007A3232021-01-0707 January 2021
License Amendment Request LAR-20-142 Request for Technical Specification Change Technical Specification 3.6.4, Containment Isolation Valves Response to Request for Additional Information (RAI)
ML21007A3402021-01-0707 January 2021
(Vcsns), Unit 1 - License Amendment Request LAR-20-176 Update of Analytical Method to the Core Operating Limits Report with the Full Spectrum Loss of Coolant Accident Approach - Response to Request for Additional Info
ML20349A3262020-12-14014 December 2020
(Vcsns), Unit 1 - Response to NRC Request for Additional Information Regarding RF-24 Steam Generator Tube Inspection Report
ML19282E2612019-10-0909 October 2019
Response to Follow-Up Question to PRA RAI 03, License Amendment Request - LAR-16-01490 NFPA 805 Program Revisions
ML19224B1152019-08-12012 August 2019
Response to NRC Follow-Up Question PRA RAI 03, License Amendment Request - LAR-16-01490 NFPA 805 Program Revisions
ML19119A3652019-04-29029 April 2019
(Vcsns), Unit 1 - License Amendment Request - LAR-16-01490, NFPA 805 Program Revisions: Response to Request for Additional Information
ML19071A3572019-03-11011 March 2019
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 - Request for Additional Information
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-18-0100, (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-18-0090, (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-18-0084, 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-18-0046, 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-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-17-0093, License Amendment Request - LAR-15-01424 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times, Response To.2017-07-0606 July 2017
License Amendment Request - LAR-15-01424 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times, Response To.
RC-17-0088, Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times - Response to Request for Additional Information2017-06-22022 June 2017
Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times - Response to Request for Additional Information
RC-17-0032, Spent Fuel Evaluation Supplemental Report, Response to NRC 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 Accident2017-03-30030 March 2017
Spent Fuel Evaluation Supplemental Report, Response to NRC 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
ML17087A1512017-03-28028 March 2017
Response to Request for Additional Information on VC Summer Sfpli
RC-17-0019, Response to Request for Additional Information Regarding License Amendment Request LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 12017-02-0606 February 2017
Response to Request for Additional Information Regarding License Amendment Request LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 1
RC-16-0147, VC Summer Nuclear Station, Unit 1, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Pursuant to Title 10 9f the Code of Federal Regulations 05.54(f)2016-11-0303 November 2016
VC Summer Nuclear Station, Unit 1, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Pursuant to Title 10 9f the Code of Federal Regulations 05.54(f)
ML16235A2422016-08-18018 August 2016
Response to Request for Information for Triennial Fire Protection Baseline Inspection
RC-16-0091, Response to Request for Additional Information on Relief Request RR-III-12 Proposed Alternative Inspection Requirements for Piping Welds2016-06-0202 June 2016
Response to Request for Additional Information on Relief Request RR-III-12 Proposed Alternative Inspection Requirements for Piping Welds
RC-16-0077, Relief Request RR-III-12, Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information2016-05-0606 May 2016
Relief Request RR-III-12, Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information
RC-16-0046, Response to Request for Additional Information on Relief Request RR-III-2, Proposed Alternative Inspection Requirements for Piping Welds2016-03-18018 March 2016
Response to Request for Additional Information on Relief Request RR-III-2, Proposed Alternative Inspection Requirements for Piping Welds
RC-16-0036, License Amendment Request - LAR-15-01424 - Implementation of WCAP-15376-P-A, Revision 1, Response to Request for Supplemental Information2016-03-0707 March 2016
License Amendment Request - LAR-15-01424 - Implementation of WCAP-15376-P-A, Revision 1, Response to Request for Supplemental Information
RC-16-0031, License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response2016-03-0404 March 2016
License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response
RC-16-0039, Exigent License Amendment Request - LAR (16-00848), Technical Specification Change Request for Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B - Response to Request for Additional..2016-03-0303 March 2016
Exigent License Amendment Request - LAR (16-00848), Technical Specification Change Request for Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B - Response to Request for Additional..
RC-16-0001, V.C. Summer, Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information2016-01-22022 January 2016
V.C. Summer, Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information
RC-16-0006, Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis2016-01-14014 January 2016
Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis
RC-15-0186, Response to Request for Information (NRC Inspection Report No. 05000395/2015404)2015-11-11011 November 2015
Response to Request for Information (NRC Inspection Report No. 05000395/2015404)
IR 05000395/20154042015-11-11011 November 2015
V.C. Summer, Unit 1 - Response to Request for Information (NRC Inspection Report No. 05000395/2015404)
RC-15-0160, Response to Request for Information (NRC Inspection Report No. 05000395/2015404)2015-09-25025 September 2015
Response to Request for Information (NRC Inspection Report No. 05000395/2015404)
ML15310A0762015-09-21021 September 2015
Response to Request for Information to Support the Cyber Security Inspection
RC-15-0142, License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information2015-09-10010 September 2015
License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information
RC-15-0116, Response to NRC Request for Information Baseline Radiation Safety Inspection2015-07-13013 July 2015
Response to NRC Request for Information Baseline Radiation Safety Inspection
2022-12-19
[Table view] |
Text
George A. Lippard Vice President, Nuclear Operations 803. 345. 4810 4f2 SCE&G@ A SCANA COMPANY June 2, 2016 RC-16-0091 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir I Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 RELIEF REQUEST RR-111-12 PROPOSED ALTERNATIVE INSPECTION REQUIREMENTS FOR PIPING WELDS - RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
References:
- 1. SCE&G Letter from T. D. Gatlin to NRC Document Control Desk, "Relief Request RR-111-12 Proposed Alternative Inspection Requirements for Piping Welds," dated November 10, 2015 (ML15316A556)
- 2. NRC Letter to G. A. Lippard (SCE&G), "Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information (CAC No.
MF7098)," dated April 8, 2016(ML16097A081)
- 3. SCE&G Letter from G. A. Lippard to NRC Document Control Desk, "Relief Request RR-111-12 Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information," dated May 6, 2016(ML16132A248)
South Carolina Electric & Gas Company (SCE&G), acting for itself and as an agent for South Carolina Public Service Authority pursuant to 10CFR50.55a(g)(5)(iii), requested relief from the volumetric requirement of ASME Code Section XI per Reference 1. NRC review of this relief request determined that additional information was required and a request for additional information (RAI) was issued by Reference 2. SCE&G responded to the RAI with Reference 3.
An error was identified in the response to RAI response 1 within Reference 3. The attachment replaces RAI response 1 in. its entirety.
V. C. Summer Nuclear Station* P. 0. Box 88
Document Control Desk RC-16-0091 CR-15-04026 Page 2 of 2 This letter contains no commitments. If you have any questions or require additional information, please contact Bruce Thompson at (803) 931-5042.
Very truly yours, NRA/GAL/rp Attachments:
I. VCSNS Response to Request for Additional Information c: K. B. Marsh S. A. Williams S. A. Byrne NRC Resident Inspector J.B. Archie K. M. Sutton N.S.Carns NSRC J. H. Hamilton RTS (CR-15-04026 & CR-16-02544)
J. W. Williams File (810.19)
W. M. Cherry PRSF (RC-16-0091)
C. Haney
Document Control Desk Attachment I RC-16-0091 CR-15-04026 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50-395 OPERATING LICENSE NO. NPF .. 12 Attachment I VCSNS Response to Request for Additional Information The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the South Carolina.
Electric & Gas Company (SCE&G) alternative request dated November 10, 2015 (Agencywide Documents Access and Management System Accession No. ML15316A556), for the Virgil C. Summer Nuclear Station, Unit 1. The NRC staff has determined that the following request for additional information (RAI) is required to complete its review. '
RAI No.1:
Please discuss the ASME Code Section XI, Appendix I requirement from which procedure SCANA-UT-98-2 is based. If supplements apply, please discuss which supplements were used.
VCSNS Response:
ASME Section XI, Appendix I SCANA-UT-98-2, Revision 3 was utilized for Manual Ultrasonic Examination of Austenitic Piping Welds, and is therefore under the requirements 1998-2000 Section XI, Appendix I Article 1-2220 that states the following:
Ultrasonic examination procedures, equipment, and personnel used to detect and size flaws in piping welds shall be qualified by performance demonstration in accordance with Appendix V/11 and no other 1-2000 requirements apply.
From Procedure SCANA-UT-98-2, Revision 3, Section 1.0 Scope:
- 1. 1 This procedure describes the manual ultrasonic examination requirements for wrought austenitic full penetration piping welds and the adjacent base materials including ultrasonic examination for intergranular stress corrosion cracking (IGSCC) in these materials.
Document Control Desk Attachment I RC-16-0091 CR-15-04026 Page 2 of 2 1.2 This procedure details an ASME Section XI, IWA-2240 examination; PDl-UT-2, Rev C, Addenda 1, 2 & 3 has been demonstrated in accordance with the requirements of ASME Section XI, Appendix VIII, 1995 Edition with addenda through 1996, as modified in the Performance Demonstration Initiative (PD/)
program description. This demonstration was also conducted in accordance with the requirements of the Federal Register, Part II, Nuclear Regulatory Commission, 10CFR Part 50, Industry Codes and Standards, Amended Requirements, final Rule, Dated 22 September, 1999.
1.3 The scope requirements of PDl-UT-2, Revision C Addenda 1, 2 & 3, shall apply to this procedure.
- 1.4 This procedure has been written to adopt performance demonstration initiative procedure (PD/) PDl-UT-2, Revision C Addenda 1, 2 & 3, PD/ Generic Procedure for Ultrasonic Examination of Austenitic Pipe Welds.
From Procedure SCANA-UT-98-2, Revision 3, Section 2.0 Applicable Documents, Codes and Standards:
- 2. 1. 1 ASME Boiler and Pressure Vessel Section XI, 1998 Edition, through 2000 Addenda.
2.1.2 ASME Boiler and Pressure Vessel Section XI, Appendix VIII, 1998 Edition, through. 2000 Addenda.
From Procedure SCANA-UT-98-2, Revision 3, Section 4.0 Procedural Qualification:
4.1 PDl-UT-2 Rev C Addenda 1, 2 & 3, has been demonstrated to meet the 10CFR50.55a Appendix VIII alternate requirements to ASME Section XI, Appendix VIII, 1998 Edition including 2000 Addenda.
- 4. 2 PD/ Procedures meet the requirements of 10 CFR Part 50. 55a, United States Nuclear Regulatory Commission, Industry Codes and Standards, Amended Requirements, Final Rule (RIN3150-AE26). Further qualification of this procedure is not required.
Supplements Used:
ASME Boiler and Pressure Vessel Section XI, Appendix VIII, Supplement 2 - Qualification Requirements for Wrought Austenitic Piping Welds, 1998 Edition through 2000 Addenda
George A. Lippard Vice President, Nuclear Operations 803. 345. 4810 4f2 SCE&G@ A SCANA COMPANY June 2, 2016 RC-16-0091 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir I Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 RELIEF REQUEST RR-111-12 PROPOSED ALTERNATIVE INSPECTION REQUIREMENTS FOR PIPING WELDS - RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
References:
- 1. SCE&G Letter from T. D. Gatlin to NRC Document Control Desk, "Relief Request RR-111-12 Proposed Alternative Inspection Requirements for Piping Welds," dated November 10, 2015 (ML15316A556)
- 2. NRC Letter to G. A. Lippard (SCE&G), "Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information (CAC No.
MF7098)," dated April 8, 2016(ML16097A081)
- 3. SCE&G Letter from G. A. Lippard to NRC Document Control Desk, "Relief Request RR-111-12 Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information," dated May 6, 2016(ML16132A248)
South Carolina Electric & Gas Company (SCE&G), acting for itself and as an agent for South Carolina Public Service Authority pursuant to 10CFR50.55a(g)(5)(iii), requested relief from the volumetric requirement of ASME Code Section XI per Reference 1. NRC review of this relief request determined that additional information was required and a request for additional information (RAI) was issued by Reference 2. SCE&G responded to the RAI with Reference 3.
An error was identified in the response to RAI response 1 within Reference 3. The attachment replaces RAI response 1 in. its entirety.
V. C. Summer Nuclear Station* P. 0. Box 88
Document Control Desk RC-16-0091 CR-15-04026 Page 2 of 2 This letter contains no commitments. If you have any questions or require additional information, please contact Bruce Thompson at (803) 931-5042.
Very truly yours, NRA/GAL/rp Attachments:
I. VCSNS Response to Request for Additional Information c: K. B. Marsh S. A. Williams S. A. Byrne NRC Resident Inspector J.B. Archie K. M. Sutton N.S.Carns NSRC J. H. Hamilton RTS (CR-15-04026 & CR-16-02544)
J. W. Williams File (810.19)
W. M. Cherry PRSF (RC-16-0091)
C. Haney
Document Control Desk Attachment I RC-16-0091 CR-15-04026 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50-395 OPERATING LICENSE NO. NPF .. 12 Attachment I VCSNS Response to Request for Additional Information The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the South Carolina.
Electric & Gas Company (SCE&G) alternative request dated November 10, 2015 (Agencywide Documents Access and Management System Accession No. ML15316A556), for the Virgil C. Summer Nuclear Station, Unit 1. The NRC staff has determined that the following request for additional information (RAI) is required to complete its review. '
RAI No.1:
Please discuss the ASME Code Section XI, Appendix I requirement from which procedure SCANA-UT-98-2 is based. If supplements apply, please discuss which supplements were used.
VCSNS Response:
ASME Section XI, Appendix I SCANA-UT-98-2, Revision 3 was utilized for Manual Ultrasonic Examination of Austenitic Piping Welds, and is therefore under the requirements 1998-2000 Section XI, Appendix I Article 1-2220 that states the following:
Ultrasonic examination procedures, equipment, and personnel used to detect and size flaws in piping welds shall be qualified by performance demonstration in accordance with Appendix V/11 and no other 1-2000 requirements apply.
From Procedure SCANA-UT-98-2, Revision 3, Section 1.0 Scope:
- 1. 1 This procedure describes the manual ultrasonic examination requirements for wrought austenitic full penetration piping welds and the adjacent base materials including ultrasonic examination for intergranular stress corrosion cracking (IGSCC) in these materials.
Document Control Desk Attachment I RC-16-0091 CR-15-04026 Page 2 of 2 1.2 This procedure details an ASME Section XI, IWA-2240 examination; PDl-UT-2, Rev C, Addenda 1, 2 & 3 has been demonstrated in accordance with the requirements of ASME Section XI, Appendix VIII, 1995 Edition with addenda through 1996, as modified in the Performance Demonstration Initiative (PD/)
program description. This demonstration was also conducted in accordance with the requirements of the Federal Register, Part II, Nuclear Regulatory Commission, 10CFR Part 50, Industry Codes and Standards, Amended Requirements, final Rule, Dated 22 September, 1999.
1.3 The scope requirements of PDl-UT-2, Revision C Addenda 1, 2 & 3, shall apply to this procedure.
- 1.4 This procedure has been written to adopt performance demonstration initiative procedure (PD/) PDl-UT-2, Revision C Addenda 1, 2 & 3, PD/ Generic Procedure for Ultrasonic Examination of Austenitic Pipe Welds.
From Procedure SCANA-UT-98-2, Revision 3, Section 2.0 Applicable Documents, Codes and Standards:
- 2. 1. 1 ASME Boiler and Pressure Vessel Section XI, 1998 Edition, through 2000 Addenda.
2.1.2 ASME Boiler and Pressure Vessel Section XI, Appendix VIII, 1998 Edition, through. 2000 Addenda.
From Procedure SCANA-UT-98-2, Revision 3, Section 4.0 Procedural Qualification:
4.1 PDl-UT-2 Rev C Addenda 1, 2 & 3, has been demonstrated to meet the 10CFR50.55a Appendix VIII alternate requirements to ASME Section XI, Appendix VIII, 1998 Edition including 2000 Addenda.
- 4. 2 PD/ Procedures meet the requirements of 10 CFR Part 50. 55a, United States Nuclear Regulatory Commission, Industry Codes and Standards, Amended Requirements, Final Rule (RIN3150-AE26). Further qualification of this procedure is not required.
Supplements Used:
ASME Boiler and Pressure Vessel Section XI, Appendix VIII, Supplement 2 - Qualification Requirements for Wrought Austenitic Piping Welds, 1998 Edition through 2000 Addenda
