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MONTHYEARML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR Project stage: RAI 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 Project stage: Request 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 Project stage: Response to RAI 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 Project stage: Response to RAI ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) Project stage: Approval 2023-08-23
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Category:Letter type:NL
MONTHYEARNL-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-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation 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-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0716, 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-23-0713, 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-23-0704, 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-23-0542, 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-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 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-23-0555, 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-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal 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-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, 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-23-0372, 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-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) 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-23-0008, 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-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0884, Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-1012022-11-17017 November 2022 Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-101 NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0756, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02022-09-30030 September 2022 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0608, Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers2022-08-17017 August 2022 Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers NL-22-0552, Inservice Inspection Program Owner'S Activity Report for Outage 2R282022-07-28028 July 2022 Inservice Inspection Program Owner'S Activity Report for Outage 2R28 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value 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-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical2022-05-10010 May 2022 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 2024-01-11
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNL-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-23-0337, 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-23-0080, 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-23-0008, 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-22-0361, 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-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-21-0020, Final Supplemental Response to NRC Generic Letter 2004-022021-03-23023 March 2021 Final Supplemental Response to NRC Generic Letter 2004-02 NL-21-0019, 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-20-1273, 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 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-20-0636, 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 NL-19-0676, Proposed Alternative FNP-ISI-ALT-05-04, Response to NRC Request for Additional Information2019-06-11011 June 2019 Proposed Alternative FNP-ISI-ALT-05-04, Response to NRC Request for Additional Information NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)2019-05-0303 May 2019 Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI) NL-19-0343, Relief Request FNP-ISI-RR-03: SNC Response to NRC Request for Additional Information2019-04-23023 April 2019 Relief Request FNP-ISI-RR-03: SNC Response to NRC Request for Additional Information NL-19-0307, Response to NRC Request for Additional Information on Relief Request FNP-ISI-RR-022019-03-27027 March 2019 Response to NRC Request for Additional Information on Relief Request FNP-ISI-RR-02 NL-18-1514, Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift.2019-01-31031 January 2019 Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift. NL-17-2135, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program, Response to NRC Request for Additional Information2018-02-0909 February 2018 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program, Response to NRC Request for Additional Information NL-17-2015, Response to NRC RAIs Regarding Decommissioning Funding Status Reports2018-01-22022 January 2018 Response to NRC RAIs Regarding Decommissioning Funding Status Reports NL-17-1443, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Final Response to NRC Requests for Additional Information2017-10-12012 October 2017 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Final Response to NRC Requests for Additional Information NL-17-1367, Response to the Second Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-09-0707 September 2017 Response to the Second Request for Additional Information Regarding Alternative Source Term License Amendment Request NL-17-0480, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information2017-06-22022 June 2017 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information NL-17-1067, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-06-0808 June 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request NL-17-0643, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-05-23023 May 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request NL-17-0774, Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating2017-05-15015 May 2017 Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating NL-17-0613, Response to Request for Additional Information Regarding Alternative Request FNP-ISI-ALT-20, Version 1.0, Regarding System Leakage Test2017-04-13013 April 2017 Response to Request for Additional Information Regarding Alternative Request FNP-ISI-ALT-20, Version 1.0, Regarding System Leakage Test NL-17-0512, Response to Request for Additional Information Regarding Alternative Request RR-PR-03 Version 1.0 for the Lnservice Testing Program Fifth 1 0-Year Interval2017-03-28028 March 2017 Response to Request for Additional Information Regarding Alternative Request RR-PR-03 Version 1.0 for the Lnservice Testing Program Fifth 1 0-Year Interval NL-16-2513, Response to Follow-up Request for Information Regarding Reactor Pressure Vessel Threads-in-Flange Examination Requirement2016-11-23023 November 2016 Response to Follow-up Request for Information Regarding Reactor Pressure Vessel Threads-in-Flange Examination Requirement NL-16-1830, Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C2016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C NL-16-1830, Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C2016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C ML16314A5052016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C ML16214A0252016-07-25025 July 2016 Units 1 and 2 - Response to Request for Additional Information for TSTF-312 NL-16-0784, Units 1 and 2 - Response to Request for Additional Information for TSTF-312. Enclosure 2 Excerpts from Calculation SM-96-1064-0012016-07-25025 July 2016 Units 1 and 2 - Response to Request for Additional Information for TSTF-312. Enclosure 2 Excerpts from Calculation SM-96-1064-001 NL-16-0870, Units 1 and 2 Supplement to Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR2016-06-30030 June 2016 Units 1 and 2 Supplement to Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR NL-16-0628, Southern Nuclear Operating Company Response to Third Request for Additional Information Regarding Standard Emergency Plan: Cover Letter, Attachment 1 and Enclosures 1 - 102016-06-0909 June 2016 Southern Nuclear Operating Company Response to Third Request for Additional Information Regarding Standard Emergency Plan: Cover Letter, Attachment 1 and Enclosures 1 - 10 NL-16-0739, Corrected Response to Second Request for Additional Information Regarding Standard Emergency Plan2016-05-26026 May 2016 Corrected Response to Second Request for Additional Information Regarding Standard Emergency Plan NL-16-0572, Response to Request for Additional Information Regarding TSTF-432-A, Revision 12016-04-13013 April 2016 Response to Request for Additional Information Regarding TSTF-432-A, Revision 1 NL-16-0415, Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR2016-04-11011 April 2016 Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR NL-16-0098, Response to Request for Additional Information for Adoption of Technical Specifications Task Force Traveler 3122016-03-0303 March 2016 Response to Request for Additional Information for Adoption of Technical Specifications Task Force Traveler 312 NL-16-0169, Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Encl2016-02-17017 February 2016 Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Enclos ML16060A3282016-02-17017 February 2016 Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Enclos NL-15-2222, Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR2016-01-28028 January 2016 Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR NL-16-0086, Units 1 and 2 - Response to Third Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 22016-01-28028 January 2016 Units 1 and 2 - Response to Third Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 2 NL-15-2062, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 22015-11-25025 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 2 2023-08-23
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Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 August 23, 2023 NL-23-0713 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Units 1 and 2 Docket Nos. 50-348 and 50-364
Subject:
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 On August 22, 2023, pursuant to the provisions of 10 CFR 50.90 and 10 CFR 50.91(a)(5),
Southern Nuclear Operating Company (SNC) submitted an emergency license amendment request (LAR) (ADAMS Accession No. ML23234A151) for Joseph M. Farley Nuclear Plant (FNP),
Units 1 and 2 renewed facility operating licenses NPF-2 and NPF-8, respectively. The requested amendment would temporarily revise the operating license, Appendix A Limiting Condition for Operation (LCO) 3.6.5, Containment Air Temperature, limit on containment average air temperature from 120F to 122F effective until 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on September 9, 2023.
On August 22, 2023, the Nuclear Regulatory Commission (NRC) Staff issued a final Request for Additional Information (RAI) seeking clarifications related to the requested LAR. The Enclosure provides the responses to RAI numbers SNSB - RAI 1 through SNSB - RAI 4. RAI number ELTB
- RAI 5 will be provided in a subsequent transmittal.
This letter contains no regulatory commitments. This letter has been reviewed and determined not to contain security-related information.
In accordance with 10 CFR 50.91, SNC is notifying the State of Alabama by transmitting a copy of this letter and its enclosure to the designated State Official.
If you have any questions, please contact Ryan Joyce at 205-992-6468.
U. S. Nuclear Regulatory Commission NL-23-0713 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 23rd day of August 2023.
Respectfully submitted, Ryan Joyce Manager, Regulatory Affairs Southern Nuclear Operating Company
Enclosure:
SNC Response to NRC RAIs SNSB - RAI 1 through SNSB - RAI 4
Attachment:
FNP Unit 1 and Unit 2 Service Water Temperature Graph cc: Regional Administrator, Region ll NRR Project Manager - Farley 1 & 2 Senior Resident Inspector - Farley 1 & 2 Alabama - State Health Officer for the Department of Public Health RType: CFA04.054
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 Enclosure SNC Response to NRC RAIs SNSB - RAI 1 through SNSB - RAI 4
Enclosure to NL-23-0713 Response to Request for Additional Information On August 22, 2023, pursuant to the provisions of 10 CFR 50.90 and 10 CFR 50.91(a)(5),
Southern Nuclear Operating Company (SNC) submitted an emergency license amendment request (LAR) for Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 renewed facility operating licenses NPF-2 and NPF-8, respectively. The requested amendment would temporarily revise the operating license, Appendix A Limiting Condition for Operation (LCO) 3.6.5, Containment Air Temperature, limit on containment average air temperature from 120F to 122F effective until 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on September 9, 2023.
On August 22, 2023, the Nuclear Regulatory Commission (NRC) Staff issued a final Request for Additional Information (RAI) via email seeking clarifications related to the requested LAR.
Responses to RAIs SNSB - RAI 1 through SNSB - RAI 4 are provided below. RAI number ELTB - RAI 5 will be provided in a subsequent transmittal.
SNSB - RAI 1:
In section 3.0, sub-section Instrument Uncertainty of the enclosure to the LAR, the licensee states that the instrument uncertainty calculation demonstrates sufficient margin to the safety analysis initial condition of 127 °F. Based on the proposed updated Containment Air Temperature limit update to 122 °F, please describe how do the existing containment maximum temperatures analyses for the LOCA and MSLB, which currently assume an initial bulk containment temperature of 127°F, remain bounding?
SNC Response The total Channel Statistical Allowance (CSA) or the total channel uncertainty for the Containment Average Air Temperature instrumentation is calculated to be +/-2.5°F when statistically combining 4 channels. The proposed Technical Specifications LCO limit of 122°F protects the Safety Analysis Limit (SAL) of 127°F and given the CSA of +/- 2.5°F yields a margin of 2.5°F.
The methodology used is the Square Root of the Sum of the Squares (SRSS) of independent components which is widely utilized in the industry. The use of probabilistic and statistical techniques to determine safety related and non-safety related set points has been endorsed by various industry standards. In particular, the methodology used in channel uncertainty for the Containment Average Air Temperature instrumentation calculation is consistent with the methodology in WCAP 13751, Westinghouse Setpoint Methodology For Protection Systems Farley Nuclear Plant Units 1 and 2 (which the NRC found acceptable for use in deriving Reactor Trip and Engineered Safety Feature Actuation System setpoints [ML013130715]).
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Enclosure to NL-23-0713 Response to Request for Additional Information SNSB - RAI 2:
In section 3.0, sub-section Sufficient Safety Margins are Maintained of the enclosure to the LAR, the licensee states that the LOCA analysis assumes an accumulator liquid temperature of 120 °F and a Refueling Water Storage Tank (RWST) initial temperature of 110 °F. The licensee further states that the 2°F increase to the accumulator liquid can be more than offset by assuming the RWST initial temperature of 100°F. Please provide details on the administrative controls that will be put in place to ensure the RWST initial temperature limit is not exceeded.
SNC Response Operations logs RWST temperature once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at midnight each day. Unit 1 Admin Tracking Item (ATI) 2608 and Unit 2 Admin Tracking Item (ATI) 2142 requires control room operators to verify RWST temperature remains less than 100 F.
SNSB - RAI 3:
Table 6.2-3 of the FSAR for Farley Units 1 and 2 states the Service Water (SW) temperature at 95°F as the initial condition for the analysis. In section 3, sub-section Service Water and Ultimate Heat Sink Evaluation of the LAR, the licensee states that the small increase in containment temperature at the start of the event represents an insignificant effect compared to the magnitude of decay heat from both units. However, there is no discussion present on how the SW temperature change due to higher outside temperatures will impact the Containment Air Temperature limit value. Please provide historical data for the SW temperature and any potential adverse impact on the Containment Air Temperature limit due to higher outside temperatures.
SNC Response Refer to the Attachment for recent Unit 1 and Unit 2 Service Water Temperature graphs.
While the ultimate heat sink (UHS) (i.e., the source for SW) temperature might be expected to rise in conjunction with the projected increased ambient temperatures, FNP does not anticipate the ultimate heat sink to exceed its Technical Specification limit of 95F (Surveillance Requirement 3.7.9.2), which is consistent with analysis assumptions. As such, there will be no adverse impact as a result of an increase in SW temperatures within the TS limits on the evaluations provided in the requested amendment.
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Enclosure to NL-23-0713 Response to Request for Additional Information SNSB - RAI 4:
Please verify that the requirement of assurance of equipment operability and containment integrity, as required by GL 96-06, will be met during operating with higher Containment Air Temperature limit.
SNC Response:
SNC response to GL 96-06 continues to be based on the current calculation of record and remains unaffected. The current Farley analyses determine that the water hammer pressure spikes at the containment air coolers are not significant enough to cause damage, demonstrating that Farley is not susceptible to the Generic Letter 96-06 concerns. A containment air temperature increase from 120°F to 122°F has a negligible impact on the current analysis. The waterhammer analysis identified that the region of the service water piping that is most susceptible to water hammer is the containment cooler return piping with lowest possible system backpressure. However, this analysis showed that no waterhammer will occur within this piping. Following a LOCA coincident with a LOSP, both the containment cooler fans and service water pumps are de-energized resulting in reduced air and service water flows through the coolers. Therefore, the heat transfer from the containment atmosphere will be less than the full capacity of the containment coolers.
In the time interval of interest (25 seconds or less) following initiation of this event, the service water downstream of the containment coolers has been calculated to reach a maximum of 119°F.
Even assuming that the service water downstream of the containment coolers picks up an additional 2°F the maximum temperature will still be less than the 164°F temperature required to form a vapor cavity.
Service water temperature, along with its associated vapor pressure, will rise rapidly following containment cooler fan restart. However, the increase in the service waters vapor pressure, caused by the service waters temperature rise, will not reach the increased pressure in the containment cooler discharge piping. Therefore, two phase flow conditions still will not occur.
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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 Attachment FNP Unit 1 and Unit 2 Service Water Temperature Graph
Attachment to NL-23-0713 Unit 1 and Unit 2 Service Water Temperatures Unit 1 Service Water A-1
Attachment to NL-23-0713 Unit 1 and Unit 2 Service Water Temperatures Unit 2 Service Water A-2