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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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3535 Colonnade Parkway
~ Southern Nuclear Cheryl A. Gayheart Birmingham. AL 35243 Regulatory Affairs Director 205 992 5316 tel 205 992 7601 fax cagayhea@southemco com APR 2 3 2019 Docket Nos. : 50-348 NL-19-0343 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Unit 1 and 2 Relief Request FNP-ISI-RR-03 SNC Response to NRC Request for Additional Information Ladies and Gentlemen:
By letter dated November 30, 2018 (Agency wide Documents Access and Management System Accession Number ML18334A032), Southern Nuclear Operating Company (SNC) requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI. This relief request, FNP-ISI-RR-03, proposed an alternate examination coverage of certain welds during the fourth 10-year inservice inspection program interval for Farley Nuclear Plant Units 1 and 2.
By email dated March 7, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff notified SNC that additional information is needed for the staff to complete their review.
Enclosure 1 to this letter provides the SNC response to the NRC request for additional information (RAI).
This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.
Respectfully submitted, Clieryl . yheart Regulatory Affairs Director Southern Nuclear Operating Company CAG/ndj/sm
Enclosure:
SNC Response to NRC Request for Additional Information (RAI) - Relief Request FNP-ISI-RR-03
U.S. Nuclear Regulatory Commission NL-19-0343 Page 2 cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector- Farley Nuclear Plant RTYPE: CFA04.054
Joseph M. Farley Nuclear Plant - Unit 1 and 2 Relief Request FNP-ISI-RR-03 SNC Response to NRC Request for Additional Information Enclosure SNC Response to NRC Request for Additional Information (RAI)
Relief Request FNP-ISI-RR-03
Enclosure to NL-19-0343 SNC Response to NRC Request for Additional Information (RAI)
Relief Request FNP-181-RR-03 NRC RAI1 Only the materials of construction for Category 8-F Item 85.70 welds were listed in the submittal.
(a) Please discuss the materials of construction (e.g., ASME material specifications) of the other subject welds and adjacent components (nozzles and pipes) in Tables RR-03.1 and RR-03.2 of the relief request.
(b) If Alloy 82/182 filler metal was used, discuss whether the subject welds have been mitigated to minimize the potential for primary water stress corrosion cracking.
SNC Response to RAJ 1 (a)
Table RR-03.1 Component ID Component Material Reference ALA 1-41 03-4 Valve SA-182 F316 U166878 Weld ER 308L or E308L Grinnell Spool Traveler 01B13CCA27 Pipe SA-376, TP304 or 316 Grinnell Spool Traveler 01B13CCA27 ALA 1-41 04-4 Valve SA-182 F316 U166878 Weld ER308L Grinnell Spool Traveler 01B13CCA22 Pipe SA-376 TP304 Grinnell Spool Traveler 01B13CCA22 ALA 1-41 04-5 Valve SA-182 F316 U166878 Weld ER308L Grinnell Spool Traveler 01B13CCA22 Pipe SA-376 TP304 Grinnell Spool Traveler 01B13CCA22 ALA 1-41 08-8-RB Valve SA-182 F316 U166880 Weld ER 308L Grinnell spool Traveler 01E21CCA5 Pipe SA-376, TP304 or 316 Grinnell spool Traveler 01E21CCA5 ALA 1-41 08-14BW -RB Tee SA-403 WP304 or 316 U259976 Weld ER 308L Daniels spool traveler 01 B13CCA 17E1523 Pipe SA-376 TP316 Daniels spool traveler 01 B13CCA 17E1523 ALA 1-4202-3-RB Elbow SA-403 WP304 or 316 U259449 Weld ER 308L or ER 316L FS-350N Pipe SA-376 TP304 Grinnell spool traveler 01B13CCA22 E-1
Enclosure to NL-19-0343 SNC Response to NRC Request for Additional Information (RAI)
Relief Request FNP-ISI-RR-03 (a) Continued Table RR-03.1 Continued Component 10 Component Material Reference ALA 1-4202-4-RB Valve SA-182 F316 U166878 Weld E 308L I ER 308L Grinnell spool traveler Q1813CCA22 Pipe SA-376, TP304 Grinnell spool traveler Q1813CCA22 ALA 1-4204-4 Valve SA-182 F316 U166878 Weld E 308L I ER 308L Grinnell Spool Traveler Q1E21CCA27 Pipe SA-376 TP304 or 316 Grinnell Spool Traveler Q1E21CCA27 ALA 1-4204-5-RB Valve SA-182 F316 U166878 Weld E 308L I ER 308L Grinnell Spool Traveler Q1E21CCA27 Pipe SA-376 TP304 or 316 Grinnell Spool Traveler Q1E21CCA27 ALA 1-4209-11 BW -RB Flange SA-182 Gr. F316 (1)
Weld ER308 (1)
Pipe (1)
SA-376 TP304 Note (1 )- Per Westinghouse ema1l, the p1pe and flange were fabncated at the pump manufacturer.
Table RR-03.2 Component 10 Component Material Reference APR1-4101-8 Valve SA-182 Gr F316 U214167 Weld E 308L I ER 308L Grinnell spool traveler Q2813CCA16 Pipe SA-376 TP304 or 316 Grinnell spool traveler Q2813CCA16 APR1-4102-2-RB Pipe SA-376 TP304 or 316 U214253 WO# M5750 Weld E308L I ER308L WO# M5750 Pipe SA-376 TP304 or 316 U214253 WO# M5750 APR1-4104-30 Valve SA-182 Gr F316 U206344 Weld E 308L I ER 308L Grinnell spool traveler Q2E21CCA27 Pipe SA-376 TP316 U213288 Grinnell spool traveler Q2E21CCA27 E-2
Enclosure to NL-19-0343 SNC Response to NRC Request for Additional Information (RAI)
Relief Request FNP-ISI-RR-03 (a) Continued Table RR-03.2 Continued Component ID Component Material Reference APR1-4106-8-RB Valve SA-182 Gr F316 U206343 Weld E 308L I ER 308L Grinnell spool traveler Q2813CCA6 Pipe SA-376 TP316 U213289 Grinnell spool traveler Q2813CCA6 APR1-4106-11-RB Branch Connection SA-403 WP304 or 316 Pipe Specification SS-1109-02 Weld E 308L I ER 308L Grinnell spool traveler Q2813CCA6 Pipe SA-376 TP304 or 316 U213289 Grinnell spool traveler Q2813CCA6 APR1-4108-11-RB Valve SA-182 Gr. F316 U206348 Weld 31 ER 308L Grinnell spool Traveler Q2813CCA5 Pipe SA376 TP304 Grinnell spool Traveler Q2813CCA5 APR1-4108-12-RB Valve A182 Gr. F316 U206348 Weld ER 308L Grinnell Spool Traveler E21CCA5-2-6748 Pipe SA-376 TP304 Grinnell Spool Traveler E21 CCA5-2-6748 U214156 APR1-41 08-13-RB Valve SA-182 Gr. F316 U205173 Weld ER 308L or ER 316L Grinnell Spool Traveler E21 CCA5-2-6748 Pipe SA-376 TP304 or 316 Grinnell Spool Traveler E21CCA5-2-6748 U214156 APR 1-4301-8 Valve SA-182 Gr. F316 U214167 Weld E 308L I ER 308L Grinnell Spool Traveler Q2813CCA16 Pipe SA-376 TP304 Grinnell Spool Traveler Q2813CCA16 APR1-4302-11-RB Elbow SA-403, WP304 or 316 U214050 Weld ER 308L or ER 316L FS-350N Pipe SA-376 TP304 OR TP316 U214050 E-3
Enclosure to NL-19-0343 SNC Response to NRC Request for Additional Information (RAI)
Relief Request FNP-ISI-RR-03 (a) Continued Table RR-03.2 Continued Component ID Component Material Reference APR 1-4302-12-RB Elbow SA-403, WP304 or 316 U214050 Weld ER 308L or ER 316L FS-350N Pipe SA-376 TP304 or TP316 U214050 APR1-4304-18 Valve SA-182 Gr. F316 U206344 Weld E 308LI ER 316L Grinnell Spool Traveler Q2E11CCA22 Pipe SA-376 TP316 Grinnell Spool Traveler Q2E11CCA22 APR1-4304-19-RB Valve SA-182 Gr. F316 U206344 Weld E 308L I ER 308L Grinnell Spool Traveler Q2E11CCA22 Pipe SA-376 TP316 Grinnell Spool Traveler Q2E11CCA22 APR1-4307-21 BC-RB Branch connection SA-182 F304 or 316 U214253 Weld ER 308L Grinnell Spool Traveler Q2E21 CCA21-E7808 Pipe SA-376 TP 304 OR 316 Grinnell Spool Traveler Q2E21 CCA21-E7808 APR1-4500-1 Branch connection SA-182 F316 Grinnell spool Traveler 2B13CCAE5365E Weld ER 308L or ER 316L Grinnell spool Traveler 2B13CCAE5365E Pipe SA-376 TP304 Grinnell spool Traveler 2B 13CCAE5365E APR2-4511-10 Flange SA-182 F316 Grinnell spool traveler Q2E11 CCB32-6 Weld ER308L Grinnell spool traveler Q2E11 CCB32-6 Pipe SA-376 TP304 Grinnell spool traveler Q2E11 CCB32-6 APR2-4511-11 Valve SA-182 F316 U206344 Weld ER308L Grinnell spool traveler Q2E11CCB32 Pipe SA-376 TP316 Grinnell spool traveler Q2E11CCB32 U214081 E-4
Enclosure to NL-19-0343 SNC Response to NRC Request for Additional Information (RAI)
Relief Request FNP-ISI-RR-03 Table RR-03.2 Continued Component ID Component Material Reference APR2-4511-12 Tee SA-403 WP 304 or 316 Grinnell spool Traveler 02E11 CCB32-6 Weld ER-308L Grinnell spool Traveler Q2E11 CCB32-6 Elbow SA-403 WP 304 or 316 Grinnell spool Traveler Q2E11 CCB32-6 (b) Filler metal Alloy 82/182 was not used as indicated in the above table.
RAI No.2 Discuss any factors or other measures that could ensure or monitor the structural integrity of the subject welds, given that certain volume of the subject welds could not be examined. The other measures may include the reactor coolant system leakage detection systems, routine system leakage tests in accordance with IWA/B-5000 of the ASME Code, Section XI, boric acid monitoring programs, operator walkdowns, and any augmented examinations.
SNC Response to RAI 2 The Class 1 pressure testing is performed per IWB-5000 during startup from refueling outages. In accordance with the Boric Acid Corrosion Control Program, Operations and Engineering personnel perform boric acid walkdowns inside containment early in the outage to identify potential leakage areas. Online monitoring and trending is performed on the identified and unidentified leakage in the RCS system per Technical Specification Surveillance Requirement 3.4.13.1.
The Class 2 pressure testing is performed per IWC-5000 once per period. In accordance with the Boric Acid Corrosion Control Program, Operations and Engineering personnel perform boric acid walkdowns inside containment early in the outage to identify potential leakage areas. Additionally, the MRP-192 programs inspects additional locations on Class 2 E11 system.
RAI No.3 The submittal states that no recordable indications were identified during examination of the Category R-A and Category B-F components. Please confirm whether recordable indications were identified in any of the other subject welds.
SNC Response to RAI 3 All of the datasheets were reviewed for the 4'h interval examinations listed in tables RR-03.1 and RR-03.2. No recordable indications were identified on the subject welds.
RAI No.4 The second paragraph of Applicable Code Requirements states The extent of examination requirement for Examination Category B-J, Item Numbers B9.11 and B9.21, E-5
Enclosure to NL-19-0343 SNC Response to NRC Request for Additional Information (RAI)
Relief Request FNP-ISI-RR-03 per Table IW8-2500-1, requires a surface and volumetric examination of essentially 100% of the weld length." However, 89.21 only requires a surface examination method.
Additionally, there does not seem to be any welds identified as 89.21 in the submittal.
Please confirm whether any 89.21 welds were supposed to be included in the submittal.
SNC Response to RAI 4 There were no limited exams in the Category 8-J, Item Number 89.21.
E-6