Letter Sequence Supplement |
---|
|
|
|
Similar Documents at Hatch |
---|
Category:Letter type:NL
MONTHYEARNL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-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-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-23-0841, 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-23-0658, 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-23-0566, 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-23-0444, 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-23-0422, 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-23-0383, 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-23-0310, 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-23-0228, 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-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 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-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error NL-22-0316, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-11-30030 November 2022 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0850, Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-11-18018 November 2022 Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0800, Supplement to Authorized Relief Request HNP-ISI-RR-05-022022-10-27027 October 2022 Supplement to Authorized Relief Request HNP-ISI-RR-05-02 NL-22-0832, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF .2022-10-27027 October 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF . 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-22-0757, Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-09-30030 September 2022 Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NL-22-0687, Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 22022-08-31031 August 2022 Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 2 NL-22-0406, Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes2022-08-19019 August 2022 Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes 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-22-0672, Registration of Spent Fuel Cask Use2022-08-17017 August 2022 Registration of Spent Fuel Cask Use NL-22-0564, and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use2022-07-21021 July 2022 and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use 2024-07-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. NL-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-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-23-0003, 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-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-22-0650, 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-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 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-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-20-1000, 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-20-0670, 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-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request NL-19-1248, Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations - TSTF-51, SNC Response to NRC Request for Additional Information2019-10-17017 October 2019 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations - TSTF-51, SNC Response to NRC Request for Additional Information NL-19-1203, Response to Request to Additional Information Regarding Application to Adopt National Fire Protection Association Standard 8052019-10-0707 October 2019 Response to Request to Additional Information Regarding Application to Adopt National Fire Protection Association Standard 805 NL-19-1028, Response to NRC Request for Additional Information Concerning License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Unit 1 Degraded Voltage Protection2019-08-28028 August 2019 Response to NRC Request for Additional Information Concerning License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Unit 1 Degraded Voltage Protection NL-19-0850, Response to Request for Addition Information Regarding Application to Adopt Title 10 of Code of Federal Regulations (CFR) 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and ...2019-07-16016 July 2019 Response to Request for Addition Information Regarding Application to Adopt Title 10 of Code of Federal Regulations (CFR) 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and ... NL-19-0698, License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function SNC Response to NRC Request for ...2019-06-12012 June 2019 License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function SNC Response to NRC Request for ... NL-19-0188, Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test SNC Response to NRC Request...2019-02-20020 February 2019 Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test SNC Response to NRC Request... 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-19-0009, Supplemental Response to Alternative Request HNP-ISI-ALT-05-042019-01-0808 January 2019 Supplemental Response to Alternative Request HNP-ISI-ALT-05-04 NL-18-1480, Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04)2018-11-29029 November 2018 Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04) NL-18-0639, Response to Request for Information Regarding Safety Relief Valve Main Valve Body Testing Extension2018-05-10010 May 2018 Response to Request for Information Regarding Safety Relief Valve Main Valve Body Testing Extension NL-18-0541, Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements2018-04-17017 April 2018 Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements ML18088A0802018-03-29029 March 2018 Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements NL-18-0211, Response to Request for Additional Information Regarding Alternative HNP-181-ALT-05-05 to Adopt Code Case N-7022018-02-20020 February 2018 Response to Request for Additional Information Regarding Alternative HNP-181-ALT-05-05 to Adopt Code Case N-702 NL-18-0085, Response to NRC RAIs Regarding Generic Letter 2016-012018-02-0505 February 2018 Response to NRC RAIs Regarding Generic Letter 2016-01 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-17-1161, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Supplemental Responses to NRC Second Set of Requests for Additional Information2017-07-12012 July 2017 License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Supplemental Responses to NRC Second Set of Requests for Additional Information NL-17-0766, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Second Set of Requests for Additional Information2017-06-0101 June 2017 License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Second Set of Requests for Additional Information NL-17-0917, Response to Request for Additional Information Regarding Relief Requests RR-16, RR-17. RR-21 and RR-222017-05-31031 May 2017 Response to Request for Additional Information Regarding Relief Requests RR-16, RR-17. RR-21 and RR-22 NL-17-0063, Response to Verbal Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-write2017-02-0606 February 2017 Response to Verbal Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-write NL-16-2494, Units 1 and 2 - Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2016-12-15015 December 2016 Units 1 and 2 - Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... NL-16-2457, Supplemental Information Regarding Proposed Safety Limit Minimum Critical Power Ratio (SLMCPR) License Amendment2016-11-18018 November 2016 Supplemental Information Regarding Proposed Safety Limit Minimum Critical Power Ratio (SLMCPR) License Amendment NL-16-2109, Response to Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500. DC Electrical Re-write2016-11-16016 November 2016 Response to Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500. DC Electrical Re-write 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 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 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 NL-16-1169, Response to Request for Additional Information on Technical Specifications - Revision Request to Implement TSTF-500, DC Electrical Re-Write.2016-08-12012 August 2016 Response to Request for Additional Information on Technical Specifications - Revision Request to Implement TSTF-500, DC Electrical Re-Write. 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-16-0660, Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specification Amendment Request2016-05-16016 May 2016 Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specification Amendment Request NL-16-0655, Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specifications Amendment Request2016-05-0909 May 2016 Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specifications Amendment Request NL-16-0292, Response to Request for Additional Information on Revision to Secondary Containment Drawdown Time Technical Specifications Amendment Request2016-03-16016 March 2016 Response to Request for Additional Information on Revision to Secondary Containment Drawdown Time Technical Specifications Amendment Request 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-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 NL-16-0172, Response to Request for Information Regarding Changes to Technical Specification Section 1.0, 3.4.9, and 5.02016-02-0909 February 2016 Response to Request for Information Regarding Changes to Technical Specification Section 1.0, 3.4.9, and 5.0 2024-07-26
[Table view] |
Text
Proprietary and/or Security-Related Information-Withhold Under 10 CFR 2.390 .. &. Southern Nuclear November 18, 2016 Charles R. Pierce Regulatory Affairs Director 40 Inverness Center Parkway Post Ofiice Box 1295 Birmingham, AL 35242 205 992 7872 tel 205 992 7601 fax crpierce@southernco.com Docket Nos.: 50-366 NL-16-2457 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant -Unit 2 Supplemental Information Regarding Proposed Safety Limit Minimum Critical Power Ratio (SLMCPR) License Amendment Ladies and Gentlemen:
By application dated August 29, 2016, Southern Nuclear Operating Company (SNC), the licensee for Edwin I. Hatch Nuclear Plant (HNP) Unit 2, submitted an amendment (ADAMS Accession No. ML 16245A257) that requested changes to Technical Specifications Section 2.1.1.2, "Reactor Core SLs." The amendment proposed revising the cycle-specific safety limit minimum critical power ratio (SLMCPR) for the upcoming Cycle 25. The U. S. Nuclear Regulatory Commission (NRG) issued a request for additional information (RAI) on November 2, 2016. The enclosures to this letter provide the additional information for the NRG staff to complete its safety evaluation of the application.
This letter contains no NRG commitments.
If you have any questions, please contact Ken
Mr. C. R. Pierce states he is the Regulatory Affairs Director for Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating*
Company and, to the best of .his knowledge and belief, the facts set forth in this letter are true.
C.R. Pierce Director Regulatory Affairs CAP/lac Sworn to and subscribed before me this -1&__ day of No 11 e.M..k Notary Public My commission expires: /D * 'l -7..o( I . . ! , 2016.
U.S. Nuclear Regulatory Commission NL-16-2457 Page 2
Enclosures:
- 1) Response to NRC RAI for Edwin I. Hatch Unit 2, Cycle 25 SLMCPR submittal
-Proprietary Information.
- 2) Response to NRC RAI for Edwin I. Hatch, Unit 2, Cycle 25 SLMCPR submittal
-Non-Proprietary Information.
- 3) Affidavit for Enclosure
- 1. cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President
& CEO Mr. D. G. Bost, Executive Vice President
& Chief Nuclear Officer Mr. D. R. Vineyard, Vice President
-Hatch Mr. M. D. Meier, Vice President
-Regulatory Affairs Mr. D. R. Madison, Vice President
-Fleet Operations Mr. B. J. Adams, Vice President
-Engineering Mr. G. L. Johnson, Regulatory Affairs Manager -Hatch RType: CHA02.004 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manager -Hatch Mr. D. H. Hardage, Senior Resident Inspector
-Hatch State of Georgia Mr. R.E. Dunn, Director -Environmental Protection Division Edwin I. Hatch Nuclear Plant -Unit 2 Supplemental Information Regarding Proposed Safety Limit Minimum Critical Power Ratio (SLMCPR) License Amendment Enclosures ENCLOSURE2 VSP-SNC-HVI-16-082 RI Revised Response to NRC RAI for Hatch 2 Cycle 25 SLMCPR Submittal Non-Proprietary Information
-Class I (Public) INFORMATION NOTICE This is a non-proprietary version of VSP-SNC-HVl 082 RI Enclosure 1, which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside an open and closed bracket as shown here [[ ]].
VSP-NPP-HVl-16-082 Rl Enclosure 2 *RAil Non-Proprietary Information
-Class I (Public) Page I of J. The SLM CPR shall have appropriate margin to reasonably protect the integrity of fuel to meet the requirements of Title 10 of the Code of Federal Regulations, Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants, Criterion 10, "Reactor Design." Table 3 of Global Nuclear Fuel-Americas, LLC report GNF-003N7688-Rl-P, "GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hatch 2 Cycle 25," (non-public, proprietary) showed TS single-loop operation SLMCPR to be 1.13, which is rounded from the [[ ]]. Please provide justification for the apparent non-conservative rounding from [[ ]] to 1.13, or demonstrate that use of this rounding convention is not significant with respect to the margin of safety. GNF Response Per the approved methodology (Reference 1 ), limiting rod patterns used in the determination of the SLMCPR are sufficiently conservative to ensure that the use of standard rounding practices, to two places past the decimal point, is not significant with respect to the margin of safety. The degree of rounding, from [[ ]] to 1.13, is therefore less than the 0.005 level of significance established as part of the approved methodology.
Furthermore, the Appendix C RAJ 17 response (page C-48) of Reference 2 discusses the 0.005 level of significance threshold in the context of the inherent variability in the Monte Carlo process. Quoted from the RAI response; "This threshold was chosen to correspond to the inherent variability in the Monte Carlo process for determining the safety limit. It is also consistent with the accepted practice of rounding and reporting SLMCPR values to two places past the decimal point. By definition, a change in a statepoint condition that goes into the evaluation of a SLMCPR is not significant unless it results in an increase in the calculated SLMCPR by +0.005." References
- 1. GE Nuclear Energy, "Methodology and Uncertainties for Safety Limit MCPR Evaluations," NEDC-32601P-A, Revision 0, August 1999. 2. GE Hitachi Nuclear Energy, "Applicability of GE Methods to Expanded Operating Domains," NEDC-33173P-A, Revision 4, November 2012.
ENCLOSURE3 VSP-SNC-HVI-16-082 RI Affidavit for Enclosure 1
Global Nuclear Fuel -Americas AFFIDAVIT I, Brian R. Moore, state as follows: (1) I am Engineering Manager, Core & Fuel Engineering, Global Nuclear Fuel -Americas, LLC (GNF-A), and have been, delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure 1 of GNF's letter, VSP-SNC-HVI-16-082 RI, V. Perry (GNF-A) to B. Carmichael (Southern Nuclear Operating Company), entitled "Revised GNF Response to NRC RAJ for Hatch 2 Cycle 25 SLMCPR Submittal," dated November 17, 2016. GNF-A proprietary information in Enclosure 1, which is entitled "Revised Response to NRC RAI for Hatch 2 Cycle 25 SLMCPR Submittal," is identified by a dotted underline inside double square brackets.
__
GNF proprietary information in some tables is identified with double square brackets before and after the object. In each case, the superscript notation (3 J refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983). (4) Some examples of categories of information which fit into the definition of proprietary information are: a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A; d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
VSP-SNC-HVl-16-082 Rl Enclosure I Affidavit Page 1 of 3 The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above. (5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence.
The information is of a sort customarily held in confidence by A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.
Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. (7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation.
Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology.
The development of this methodology, along with the testing, development and approval was achieved at a significant cost to GNF-A. The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from an extensive experience database that constitutes a major GNF-A asset. (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of making opportunities.
The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods. The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A. VSP-SNC-HVI-16-082 Rl Enclosure 1 Affidavit Page 2 of 3 The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this infonnation to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools. I declare under penalty of perjury that the foregoing is true and correct. Executed on this 17th day of November 2016. Brian R. Moore Engineering Manager, Core & Fuel Engineering Global Nuclear Fuel -Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 Brian.Moore@ge.com VSP-SNC-HVl-16-082 RI Enclosure I Affidavit Page 3 of 3