Letter Sequence Response to RAI |
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Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report SubmittalML23223A139 |
Person / Time |
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Site: |
Hatch, Vogtle, Farley, 07200042, 07200036, 07201039, 07100333, 07100521, 07100726 |
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Issue date: |
08/11/2023 |
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From: |
Joyce R Southern Nuclear Operating Co |
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To: |
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
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References |
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NL-23-0658 |
Download: ML23223A139 (1) |
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Category:Letter type:NL
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0620, ISFSI, and Edwin I. Hatch Nuclear Plant ISFSI, Registration of Spent Fuel Cask Use2023-08-0303 August 2023 ISFSI, and Edwin I. Hatch Nuclear Plant ISFSI, Registration of Spent Fuel Cask Use NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 2024-01-30
[Table view] Category:Quality Assurance Program
MONTHYEARNL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ND-22-0968, Enclosure - Nuclear Development Quality Assurance Manual (Ndqam), Version 23.02023-01-0505 January 2023 Enclosure - Nuclear Development Quality Assurance Manual (Ndqam), Version 23.0 ND-21-1116, Nuclear Development Quality Assurance Manual Version 22.02022-02-0404 February 2022 Nuclear Development Quality Assurance Manual Version 22.0 ML21313A3312021-10-28028 October 2021 0 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance NL-21-0526, Quality Assurance Topical Report - Reduction in Commitment (Pandemic Related) - Supplement2021-05-26026 May 2021 Quality Assurance Topical Report - Reduction in Commitment (Pandemic Related) - Supplement NL-21-0051, Quality Assurance Topical Report, Reduction in Commitment (Pandemic Related)2021-05-0707 May 2021 Quality Assurance Topical Report, Reduction in Commitment (Pandemic Related) ND-20-1415, Nuclear Development Quality Assurance Manual Version 21.02020-12-11011 December 2020 Nuclear Development Quality Assurance Manual Version 21.0 ND-20-0005, Enclosure - Nuclear Development Quality Assurance Manual Version 20.02019-11-0505 November 2019 Enclosure - Nuclear Development Quality Assurance Manual Version 20.0 ND-20-0256, Southern Nuclear Operating Co, Inc., Nuclear Development Quality Assurance Manual2019-11-0505 November 2019 Southern Nuclear Operating Co, Inc., Nuclear Development Quality Assurance Manual NL-19-0710, Quality Assurance Topical Report Submittal2019-06-24024 June 2019 Quality Assurance Topical Report Submittal NL-18-0854, Quality Assurance Topical Report Submittal2018-06-26026 June 2018 Quality Assurance Topical Report Submittal ND-18-0295, Nuclear Development Quality Assurance Manual Version 18.02018-03-20020 March 2018 Nuclear Development Quality Assurance Manual Version 18.0 ML16211A1322016-08-11011 August 2016 Quality Assurance Plan for the Level 3 PRA Project, Rev.0 NL-14-1996, Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.12014-12-30030 December 2014 Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1 NL-13-2418, Edwin I. Hatch Nuclear Plant; Vogtle Electric Generating Plant - Quality Assurance Topical Report2013-11-21021 November 2013 Edwin I. Hatch Nuclear Plant; Vogtle Electric Generating Plant - Quality Assurance Topical Report NL-11-1435, Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, Quality Assurance Topical Report2011-08-0303 August 2011 Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, Quality Assurance Topical Report NL-07-1099, Quality Assurance Topical Report - Clarification of RAI Response2007-05-23023 May 2007 Quality Assurance Topical Report - Clarification of RAI Response ML0712702842007-04-30030 April 2007 Southern Nuclear Operating Company - Quality Assurance Topical Report, ANSI N18.7-1976 Conformance Matrix, Enclosure 5 ML0712702832007-04-30030 April 2007 Southern Nuclear Operating Company - Quality Assurance Topical Report Revision 2b, Enclosure 1 2023-08-11
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0003, Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 12023-01-20020 January 2023 Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1 NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-22-0801, Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of .2022-10-14014 October 2022 Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of . NL-22-0609, Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2022-09-13013 September 2022 Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-22-0650, Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-08-19019 August 2022 Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0590, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten2022-08-18018 August 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten NL-22-0549, Responses to NRC Request for Additional Information for Refueling Outage 1R23 Steam Generator Tube Inspection Report2022-07-19019 July 2022 Responses to NRC Request for Additional Information for Refueling Outage 1R23 Steam Generator Tube Inspection Report ND-22-0328, Enclosuvogtle Electric Generating Plant, Units 3 & 4 - Fukushima Response NEI 12-01 On-Shift Staffing Analysis Phase 2 Report, Revision 3.0, Standard Emergency Plan Annex, Revision 6.02022-06-29029 June 2022 Enclosuvogtle Electric Generating Plant, Units 3 & 4 - Fukushima Response NEI 12-01 On-Shift Staffing Analysis Phase 2 Report, Revision 3.0, Standard Emergency Plan Annex, Revision 6.0 NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-22-0055, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2022-02-28028 February 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System NL-21-1015, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2022-01-13013 January 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System NL-21-1060, Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Allow Elimination of the Encapsulation Vessels Around the First Containment Spray (CS) and Residual Heat Removal .2021-12-13013 December 2021 Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Allow Elimination of the Encapsulation Vessels Around the First Containment Spray (CS) and Residual Heat Removal . NL-21-0862, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable - RAI Responses2021-09-23023 September 2021 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable - RAI Responses ND-21-0618, Response to Request for Additional Information Regarding Request for Alternative: Alternative Requirements for ASME Section Ill Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16)2021-07-0202 July 2021 Response to Request for Additional Information Regarding Request for Alternative: Alternative Requirements for ASME Section Ill Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16) NL-21-0423, Emergency License Amendment Request for Technical Specification 3.5.1 Re One-Time Extension of Completion Time for 2D RHR Pump - PRA RAI Response2021-04-22022 April 2021 Emergency License Amendment Request for Technical Specification 3.5.1 Re One-Time Extension of Completion Time for 2D RHR Pump - PRA RAI Response NL-21-0415, Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump - RAI Response2021-04-20020 April 2021 Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump - RAI Response NL-21-0020, Final Supplemental Response to NRC Generic Letter 2004-022021-03-23023 March 2021 Final Supplemental Response to NRC Generic Letter 2004-02 NL-21-0208, Response to Request for Additional Information Related to Refueling Outage 1R22 Steam Generator Tube Inspection Report2021-03-0202 March 2021 Response to Request for Additional Information Related to Refueling Outage 1R22 Steam Generator Tube Inspection Report NL-21-0019, Response to Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-03-0202 March 2021 Response to Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NL-20-1417, Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-1912020-12-17017 December 2020 Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-191 NL-20-1312, Response to Request for Additional Information Related to Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.02020-11-23023 November 2020 Response to Request for Additional Information Related to Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.0 NL-20-1273, Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for2020-11-20020 November 2020 Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for ND-20-1005, Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1)2020-09-18018 September 2020 Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1) NL-20-1000, Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time2020-08-23023 August 2020 Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time NL-20-0816, Response to Request for Clarification Regarding the Refueling Outage 1R29 Steam Generator Tube Inspection Report2020-07-17017 July 2020 Response to Request for Clarification Regarding the Refueling Outage 1R29 Steam Generator Tube Inspection Report NL-20-0670, Response to Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2020-06-0202 June 2020 Response to Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NL-20-0636, Third Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-05-29029 May 2020 Third Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request NL-20-0550, Responses to NRC Requests for Additional Information License Amendment Request to Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint2020-05-20020 May 2020 Responses to NRC Requests for Additional Information License Amendment Request to Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint NL-20-0538, Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-05-0808 May 2020 Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate NL-20-0458, Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-04-22022 April 2020 Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate NL-20-0403, Response to Request for Additional Information Regarding License Amendment Request to Update the Spent Fuel Pool Criticality Safety Analysis and Revise Technical Specification (TS) 3.7.15 Spent Fuel Assembly Storage2020-04-13013 April 2020 Response to Request for Additional Information Regarding License Amendment Request to Update the Spent Fuel Pool Criticality Safety Analysis and Revise Technical Specification (TS) 3.7.15 Spent Fuel Assembly Storage 2024-01-30
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Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 tel August 11, 2023 Docket Nos.: 50-321 50-348 50-424 NL-23-0658 50-366 50-364 50-425 71-521 71-333 71-726 72-036 72-042 72-1039 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 Response to Request for Additional Information Regarding Southern Nuclear Operating Companys Quality Assurance Topical Report Submittal Ladies and Gentlemen:
By letter dated June 15, 2023, Southern Nuclear Operating Company (SNC) submitted Version 26.0 of the SNC Quality Assurance Topical Report (QATR) for the Edwin I. Hatch Nuclear Plant, the Joseph M. Farley Nuclear Plant, and the Vogtle Electric Generating Plant (Enclosure 1) to the NRC. By email dated July 17, 2023 [ML23198A155], the NRC staff transmitted a request for additional information (RAI) regarding SNCs QATR submittal. The Enclosure to this letter repeats the RAI and provides SNCs response to the RAI.
This letter contains no regulatory commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
Respectfully submitted, Ryan M. Joyce Licensing Manager RMJ/agq/cbg
Enclosure:
SNC Response to Request for Additional Information
U. S. Nuclear Regulatory Commission NL-23-0658 Page 2 cc: Regional Administrator, Region ll NRR Project Manager - Farley, Hatch, Vogtle 1 & 2 Senior Resident Inspector - Farley, Hatch, Vogtle 1 & 2 RType: CGA02.001
Edwin I. Hatch Nuclear Plant - Units 1 and 2 Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 Response to Request for Additional Information Regarding Southern Nuclear Operating Companys Quality Assurance Topical Report Submittal Enclosure to NL-23-0658 SNC Response to Request for Additional Information
Enclosure to NL-23-0658 SNC Response to Request for Additional Information NRC REQUEST FOR ADDITIONAL INFORMATION (RAI)
By letter dated June 15, 2023 (Agencywide Documents and Access Management System Accession No. ML23166A104), Southern Nuclear Operating Company (SNC, the licensee) submitted Version 26 of SNC Quality Assurance Topical Report (QATR) for the Edwin I. Hatch Nuclear Plant (Hatch), Units 1 and 2, the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, and the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the changes and finds that additional information is needed to provide assurance that the changes meet the no reduction in commitment of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(a)(3)(ii),
i.e., (ii) The use of a quality assurance alternative or exception approved by an NRC safety evaluation, provided that the bases of the NRC approval are applicable to the licensees facility.
Regulatory Basis The regulation 10 CFR 50.54(a)(3) states:
Each licensee described in paragraph (a)(1) of this section may make a change to a previously accepted quality assurance program description included or referenced in the Safety Analysis Report without prior NRC approval, provided the change does not reduce the commitments in the program description as accepted by the NRC. Changes to the quality assurance program description that do not reduce the commitments must be submitted to the NRC in accordance with the requirements of Sec. 50.71(e). In addition to quality assurance program changes involving administrative improvements and clarifications, spelling corrections, punctuation, or editorial items, the following changes are not considered to be reductions in commitment:
(i) The use of a QA standard approved by the NRC which is more recent than the QA standard in the licensees current QA program at the time of the change; (ii) The use of a quality assurance alternative or exception approved by an NRC safety evaluation, provided that the bases of the NRC approval are applicable to the licensees facility; (iii) The use of generic organizational position titles that clearly denote the position function, supplemented as necessary by descriptive text, rather than specific titles; (iv) The use of generic organizational charts to indicate functional relationships, authorities, and responsibilities, or, alternately, the use of descriptive text; (v) The elimination of quality assurance program information that duplicates language in quality assurance regulatory guides and quality assurance standards to which the licensee is committed; and (vi) Organizational revisions that ensure that persons and organizations performing quality assurance functions continue to have the requisite authority and organizational freedom, including sufficient independence from cost and schedule when opposed to safety considerations.
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Enclosure to NL-23-0658 SNC Response to Request for Additional Information Request for Additional Information The NRC staff identified one area where a request for additional information (RAI) is needed. In , SNC QATR Versions 24.0, 25.0, and 26.0, Summary of Changes, of the SNC letter dated June 15, 2023, Item 6 references an Exelon Safety Evaluation (SE) documented under ADAMS Accession No. ML20287A130, dated November 5, 2020. The Exelon SE addresses the following activities related to annual evaluation and an analysis:
Exelons request includes a revision to the QATR to require an evaluation once per calendar year to determine the need for additional audit activities. Exelon will assess the results of this evaluation, and, when necessary, a review of the identified areas of performance weakness will be planned at the earliest possible opportunity. Exelon also stated that: Each functional audit area will receive an additional performance analysis (evaluation) within 2 years of the last performed audit based on internal and external data; functional area changes in responsibility, resources, or management; and consideration of the impacts, as applicable, to determine if additional audit activities are necessary prior to the 36-month scheduled performance. The NRC staff determined that the additional evaluation requirement will ensure that for Exelons facilities the extension of internal audit intervals beyond 2 years will be based on the results of an annual evaluation of the applicable functional area and objective evidence that the functional area activities are being satisfactorily accomplished.
The summary of changes in the SNC letter dated June 15, 2023, is silent on how SNC meets the conditions described in the Exelon submittal dated December 5, 2019 (ML19339E544), as supplemented by letter dated February 24, 2020 (ML20055G249), and the NRC staff SE dated November 5, 2020. Please discuss how SNC has / or will incorporate the activities above to meet the intent of the Exelon SE.
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Enclosure to NL-23-0658 SNC Response to Request for Additional Information SNC RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (RAI)
The QATR was revised from version 23 to version 24 when adopting the extended audit frequencies described in the NRC safety evaluation report (SER) to Exelon dated November 5, 2020 (ML20287A130). The evaluation of the change to adopt the extended audit frequencies credited §50.54(a)(3)(ii) The use of a quality assurance alternative or exception approved by an NRC safety evaluation, provided that the bases of the NRC approval are applicable to the licensee's facility;.
The bases cited by the NRC in the Exelon SER are as follows:
10 CFR 50.34(b)(6)(ii) - equivalent bases apply to SNC 10 CFR 50.54(a) - equivalent bases apply to SNC 10 CFR 50 Appendix B, Criterion XVII Audits - equivalent bases apply to SNC 10 CFR 72 Subpart G Quality Assurance - equivalent bases apply to SNC NQA-1-1994 Quality Assurance Program for Nuclear Facilities - equivalent bases apply to SNC Exelon committed to performing an annual evaluation of each audit area that is being extended beyond a 24-month audit frequency; a similar process was integrated into the NOS implementing procedure for audit planning and scheduling.
All of the bases cited in the Exelon SER apply to SNC. Per 50.54(a)(3)(ii), this change did not represent a reduction in commitment.
SNCs QATR (current version 26) contains a discussion in Section 18.1 as to what conditions would cause an audit schedule change:
Audit schedule changes reflecting more frequent audits are required by one or more of the following conditions:
When significant changes are made in functional areas of the QAP, such as significant reorganization or procedure revisions.
When there is evidence that the performance or reliability of safety-related items is in jeopardy due to deficiencies or nonconformances in the QAP.
When a systematic, independent assessment of QAP effectiveness is necessary.
When it is necessary to verify implementation of required corrective actions.
These requirements have been present in the SNC QATR since version 1 following initial NRC approval, including in version 24 when SNC adopted Exelons SER for extended frequencies of some audit areas. Section 18.1 of the QATR meets the intent of NQA-1-1994 Supplement 18S-1 Supplementary Requirements for Audits, Section 2, Scheduling:
The audit schedule shall be reviewed periodically and revised as necessary to assure that coverage is maintained current. Regularly scheduled audits shall be supplemented by additional audits of specific subjects when necessary to provide adequate coverage.
The requirements above from Section 18.1 of the QATR are implemented in the NOS procedure for audit planning and scheduling. This implementing procedure was updated as part of the Page 3 of 4
Enclosure to NL-23-0658 SNC Response to Request for Additional Information adoption of Exelons extended audit frequencies. The procedure requirements include (in addition to the requirements of QATR Section 18.1 cited above):
NOS Management will ensure periodic (e.g., annually, anniversary reviews) evaluations are performed to determine the need for more frequent audit intervals:
For all audit areas with 24- and 36-month audit frequencies, a 12-month Anniversary Audit Evaluation SHALL be conducted.
The independent spent fuel storage installation audit frequency was also revised to 36 months in QATR version 25 and the NOS implementing procedure for audit planning and scheduling following a similar application of the Exelon SER as described above.
Note that SNC had a pre-existing audit area annual review process prior to the adoption of the Exelon extended audit frequencies explicitly following a process described in the NOS implementing procedure for audit planning and scheduling, utilizing criteria specified in the QATR. As discussed above, SNC revised the previous annual audit review process using the Exelon procedure as a model, while making some changes to better fit the SNC QA program established in the QATR; one aspect of this change was performing a comprehensive evaluation every 12 months rather than the Exelon model that performed different evaluations of varying complexity at 12 and 24 months. SNC titled the revised annual evaluation Anniversary reviews in order to distinguish from the previous effort, and to reflect that these were to be performed 12 months after the last audit, and 12 months after the last anniversary review, until the next audit is performed (assuming a 36-month audit frequency).
In conclusion, since its initial issuance, the SNC QATR has listed criteria to be considered for more frequent audits which has been present since the initial SNC QATR, and the NOS implementing procedure for audit planning and scheduling has described an annual audit review process. The NOS implementing procedure for audit planning and scheduling establishes the details and requirements of the anniversary audits, which are as stringent or more stringent than those described in the Exelon SER. Thus, SNCs change to a 36-month audit frequency for certain audit topics did not represent a reduction in commitment.
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