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MONTHYEARML24281A1362024-10-0707 October 2024 NRR E-mail Capture - (External_Sender) Acceptance Review - Hatchs Revise Technical Specifications to Adopt TSTF-591 LAR (L-2024-LLA-0122) Project stage: Other 2024-10-07
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Category:Letter type:NL
MONTHYEARNL-24-0357, Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines2024-10-30030 October 2024 Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines NL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information 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-24-0290, 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-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0062, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-03-12012 March 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024 Cycle 32 Core Operating Limits Report Version 1 NL-24-0067, 10 CFR 72.48(d)(2) Biennial Report2024-02-26026 February 2024 10 CFR 72.48(d)(2) Biennial Report NL-24-0051, License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-02-20020 February 2024 License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers 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 Owners Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owners 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-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error 2024-09-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program 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-24-0026, 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-24-0051, License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-02-20020 February 2024 License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components 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-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-22-0832, 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-22-0757, 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-22-0406, 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-22-0335, Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And.2022-05-17017 May 2022 Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And. NL-21-0918, License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 52022-03-31031 March 2022 License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 5 NL-22-0010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 and Administrative.2022-03-25025 March 2022 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 and Administrative. NL-21-1037, License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2022-02-0404 February 2022 License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NL-21-0784, License Amendment Request: Revise Technical Specifications to Adopt TSTF-227, Revision to EOC-RPT Pump Actions and TSTF-297, Enhancements to Required Actions for Feedwater and Main Turbine High Water Level Trip2021-12-13013 December 2021 License Amendment Request: Revise Technical Specifications to Adopt TSTF-227, Revision to EOC-RPT Pump Actions and TSTF-297, Enhancements to Required Actions for Feedwater and Main Turbine High Water Level Trip NL-21-0722, Units 1 and 2, License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates2021-12-0606 December 2021 Units 1 and 2, License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates NL-21-0576, Units 1 and 2 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 4b2021-10-26026 October 2021 Units 1 and 2 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-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements NL-21-0852, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2021-09-21021 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 NL-21-0613, Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, .2021-06-30030 June 2021 Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, . NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications2021-06-22022 June 2021 License Amendment Request to Remove Table of Contents from Technical Specifications NL-21-0413, Supplement to Emergency License Amendment Request for Technical Specification 3.5.1 Re One-Time Extension of Completion Time for 2D RHR Pump2021-04-20020 April 2021 Supplement to Emergency License Amendment Request for Technical Specification 3.5.1 Re One-Time Extension of Completion Time for 2D RHR Pump NL-21-0411, Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump2021-04-19019 April 2021 Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump NL-21-0065, License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls2021-03-25025 March 2021 License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls NL-20-0949, License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 22020-10-30030 October 2020 License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2 NL-20-0785, Southern Nuclear Operating Co - Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-08-28028 August 2020 Southern Nuclear Operating Co - Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20224A4642020-08-11011 August 2020 Southern Nuclear Operating Co, Inc - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions NL-20-0843, License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time for Unit 1 and Swing Emergency Diesel Generators2020-07-31031 July 2020 License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time for Unit 1 and Swing Emergency Diesel Generators ML20192A1402020-06-30030 June 2020 Southern Nuclear Operating Co., Inc. - License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions NL-19-1455, Emergency License Amendment Request for Technical Specification 3.7.1 Regarding One-Time Extension of Completion Time for RHRSW Pump Inoperable2019-11-29029 November 2019 Emergency License Amendment Request for Technical Specification 3.7.1 Regarding One-Time Extension of Completion Time for RHRSW Pump Inoperable NL-19-1266, Supplement to License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Degraded Voltage Protection2019-10-17017 October 2019 Supplement to License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Degraded Voltage Protection NL-19-0355, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process2019-07-23023 July 2019 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19123A1012019-04-30030 April 2019 License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Unit 1 Degraded Voltage Protection NL-19-0250, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2019-04-23023 April 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR NL-19-0173, Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test2019-02-19019 February 2019 Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test ML18226A0942018-08-0909 August 2018 Edwin I. Hatch, Units 1 and 2; and Vogtle, Units 1 and 2 - License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-shift Staff Tables NL-18-0601, Revision to Technical Specification End State for Residual Heat Removal Drywell Spray2018-08-0606 August 2018 Revision to Technical Specification End State for Residual Heat Removal Drywell Spray NL-16-0108, Units 1 and 2, License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function2018-06-29029 June 2018 Units 1 and 2, License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function NL-17-1962, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors.2018-06-0707 June 2018 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. NL-18-0630, Supplement to License Amendment Request to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control2018-05-0101 May 2018 Supplement to License Amendment Request to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control ML18096A9562018-04-0404 April 2018 Enclosure 2: NFPA 805 LAR Transition Report for Edwin I. Hatch (Redacted) NL-18-0282, Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch2018-04-0404 April 2018 Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch NL-18-0282, Edwin I. Hatch, Units 1 and 2, License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2018-04-0404 April 2018 Edwin I. Hatch, Units 1 and 2, License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML18096A9552018-04-0404 April 2018 License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) NL-18-0074, License Amendment Request for Technical Specification 3.3.8.1 Regarding Degraded Voltage Protection2018-03-0909 March 2018 License Amendment Request for Technical Specification 3.3.8.1 Regarding Degraded Voltage Protection NL-18-0206, Supplement to Application to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-02-19019 February 2018 Supplement to Application to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control NL-17-1088, Submittal of License Amendment Request, Relocation of the Emergency Operations Facility2017-08-30030 August 2017 Submittal of License Amendment Request, Relocation of the Emergency Operations Facility NL-17-0328, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-04-20020 April 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. NL-16-1582, Request for License Amendment to Address Secondary Containment Access Openings2017-04-0707 April 2017 Request for License Amendment to Address Secondary Containment Access Openings ML16340A0052016-12-0101 December 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Rev 4, Clarify Use and Application Rules. 2024-09-11
[Table view] Category:Technical Specification
MONTHYEARNL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program 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-24-0026, 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-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-23-0069, 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-22-0406, 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-21-1037, License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2022-02-0404 February 2022 License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NL-22-0062, Supplement to License Amendment Request: Revise Technical Specifications to Adopt TSTF-227 & TSTF-2972022-02-0101 February 2022 Supplement to License Amendment Request: Revise Technical Specifications to Adopt TSTF-227 & TSTF-297 NL-21-0784, License Amendment Request: Revise Technical Specifications to Adopt TSTF-227, Revision to EOC-RPT Pump Actions and TSTF-297, Enhancements to Required Actions for Feedwater and Main Turbine High Water Level Trip2021-12-13013 December 2021 License Amendment Request: Revise Technical Specifications to Adopt TSTF-227, Revision to EOC-RPT Pump Actions and TSTF-297, Enhancements to Required Actions for Feedwater and Main Turbine High Water Level Trip NL-21-0984, Southern Nuclear Operating Company - Second Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls2021-11-10010 November 2021 Southern Nuclear Operating Company - Second Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls 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-21-0613, Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, .2021-06-30030 June 2021 Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, . NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications2021-06-22022 June 2021 License Amendment Request to Remove Table of Contents from Technical Specifications 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-21-0411, Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump2021-04-19019 April 2021 Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump NL-19-1455, Emergency License Amendment Request for Technical Specification 3.7.1 Regarding One-Time Extension of Completion Time for RHRSW Pump Inoperable2019-11-29029 November 2019 Emergency License Amendment Request for Technical Specification 3.7.1 Regarding One-Time Extension of Completion Time for RHRSW Pump Inoperable NL-19-1266, Supplement to License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Degraded Voltage Protection2019-10-17017 October 2019 Supplement to License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Degraded Voltage Protection NL-19-0355, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process2019-07-23023 July 2019 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-19-0250, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2019-04-23023 April 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR NL-19-0173, Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test2019-02-19019 February 2019 Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test NL-18-1132, Revision to Technical Specification 3.6.4.1 -Secondary Containment2018-10-17017 October 2018 Revision to Technical Specification 3.6.4.1 -Secondary Containment ML18226A0942018-08-0909 August 2018 Edwin I. Hatch, Units 1 and 2; and Vogtle, Units 1 and 2 - License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-shift Staff Tables NL-18-0601, Revision to Technical Specification End State for Residual Heat Removal Drywell Spray2018-08-0606 August 2018 Revision to Technical Specification End State for Residual Heat Removal Drywell Spray NL-17-0328, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-04-20020 April 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.2016-07-28028 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application. NL-16-0626, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-07-0101 July 2016 License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies NL-16-0827, E. I. Hatch, Units 1 and 2 - Withdrawal of TSTF-500 Request to Increase the Completion Time for the Station Service Batteries from 2 to 12 Hours2016-06-17017 June 2016 E. I. Hatch, Units 1 and 2 - Withdrawal of TSTF-500 Request to Increase the Completion Time for the Station Service Batteries from 2 to 12 Hours NL-15-2047, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 22015-11-24024 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 2 NL-13-1773, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A (NL-13-1773)2015-04-0202 April 2015 Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A (NL-13-1773) NL-13-1528, Response to Request for Information on the Plant Hatch License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well2013-07-22022 July 2013 Response to Request for Information on the Plant Hatch License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well NL-12-1078, Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well2012-07-0505 July 2012 Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well ML11320A1272011-10-24024 October 2011 Edwin I. Hatch, Units 1 and 2- Bases for Technical Specifications NL-11-0816, Supplement to Licensing Amendment Request for Adoption of TSTF - 425 - a, Rev. 3, Risk - Informed Justification for Relocation of Specific Frequency Requirements to a Licensee Controlled Program Using the Consolidated..2011-05-27027 May 2011 Supplement to Licensing Amendment Request for Adoption of TSTF - 425 - a, Rev. 3, Risk - Informed Justification for Relocation of Specific Frequency Requirements to a Licensee Controlled Program Using the Consolidated.. NL-09-1380, Revision to Technical Specifications LCO 3.1.2, Reactivity Anomalies2009-12-17017 December 2009 Revision to Technical Specifications LCO 3.1.2, Reactivity Anomalies NL-07-2111, Technical Specifications Revision Request to the Ventilation Filter Testing Program2008-07-15015 July 2008 Technical Specifications Revision Request to the Ventilation Filter Testing Program NL-08-0903, Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Turbine Building Ventilation Exhaust System Fans2008-06-25025 June 2008 Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Turbine Building Ventilation Exhaust System Fans ML0733203732007-11-26026 November 2007 Technical Specifications for Edwin I. Hatch Nuclear Plant, Units 1 and 2, Issuance of Amendments Regarding Control Rod Scram Time Testing Frequency (TAC MD5722 and MD5723) NL-07-0277, Technical Specifications Bases Changes for 20062007-02-19019 February 2007 Technical Specifications Bases Changes for 2006 ML0624902532006-08-29029 August 2006 Enclosure 5, E. I. Hatch Request to Implement an Alternative Source Term - Marked-Up TS and Bases Pages ML0535500322005-12-12012 December 2005 Handout of Draft Proposed Change #1 Technical Specifications Bases Changes from 12/12/05 Meeting on Safety Limit 2.1.1.1, Part 21 ML0535500352005-12-12012 December 2005 Handout of Draft Proposed Change #2 Technical Specifications and Bases Changes from 12/12/05 Meeting on Safety Limit 2.1.1.1, Part 21 NL-05-0252, Technical Specifications Bases Revisions for 20042005-02-24024 February 2005 Technical Specifications Bases Revisions for 2004 NL-04-1001, Edwin 1. Hatch Nuclear Plant Unit 1 and 2 - Technical Specifications Amendment Request Appendix J Leakage Rate Test for Containment Purge Valves2004-08-23023 August 2004 Edwin 1. Hatch Nuclear Plant Unit 1 and 2 - Technical Specifications Amendment Request Appendix J Leakage Rate Test for Containment Purge Valves NL-04-0981, Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases2004-06-0202 June 2004 Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases NL-04-0564, Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors2004-05-21021 May 2004 Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors NL-04-0563, Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension2004-04-26026 April 2004 Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension ML0406905022004-03-0808 March 2004 Technical Specification for Amendment 182, 3/8/04 ML0406905122004-03-0808 March 2004 Technical Specification for Amendment 239, 3/8/04 2024-09-11
[Table view] Category:Bases Change
MONTHYEARNL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program 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-21-0784, License Amendment Request: Revise Technical Specifications to Adopt TSTF-227, Revision to EOC-RPT Pump Actions and TSTF-297, Enhancements to Required Actions for Feedwater and Main Turbine High Water Level Trip2021-12-13013 December 2021 License Amendment Request: Revise Technical Specifications to Adopt TSTF-227, Revision to EOC-RPT Pump Actions and TSTF-297, Enhancements to Required Actions for Feedwater and Main Turbine High Water Level Trip 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-19-1266, Supplement to License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Degraded Voltage Protection2019-10-17017 October 2019 Supplement to License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Degraded Voltage Protection NL-19-0355, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process2019-07-23023 July 2019 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-18-1132, Revision to Technical Specification 3.6.4.1 -Secondary Containment2018-10-17017 October 2018 Revision to Technical Specification 3.6.4.1 -Secondary Containment NL-18-0601, Revision to Technical Specification End State for Residual Heat Removal Drywell Spray2018-08-0606 August 2018 Revision to Technical Specification End State for Residual Heat Removal Drywell Spray NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.2016-07-28028 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application. NL-16-0626, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-07-0101 July 2016 License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies NL-15-2047, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 22015-11-24024 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 2 NL-13-1773, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A (NL-13-1773)2015-04-0202 April 2015 Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A (NL-13-1773) NL-12-1078, Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well2012-07-0505 July 2012 Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well ML11320A1272011-10-24024 October 2011 Edwin I. Hatch, Units 1 and 2- Bases for Technical Specifications NL-11-0816, Supplement to Licensing Amendment Request for Adoption of TSTF - 425 - a, Rev. 3, Risk - Informed Justification for Relocation of Specific Frequency Requirements to a Licensee Controlled Program Using the Consolidated..2011-05-27027 May 2011 Supplement to Licensing Amendment Request for Adoption of TSTF - 425 - a, Rev. 3, Risk - Informed Justification for Relocation of Specific Frequency Requirements to a Licensee Controlled Program Using the Consolidated.. NL-09-1380, Revision to Technical Specifications LCO 3.1.2, Reactivity Anomalies2009-12-17017 December 2009 Revision to Technical Specifications LCO 3.1.2, Reactivity Anomalies NL-07-2111, Technical Specifications Revision Request to the Ventilation Filter Testing Program2008-07-15015 July 2008 Technical Specifications Revision Request to the Ventilation Filter Testing Program NL-08-0903, Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Turbine Building Ventilation Exhaust System Fans2008-06-25025 June 2008 Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Turbine Building Ventilation Exhaust System Fans NL-07-0277, Technical Specifications Bases Changes for 20062007-02-19019 February 2007 Technical Specifications Bases Changes for 2006 ML0624902532006-08-29029 August 2006 Enclosure 5, E. I. Hatch Request to Implement an Alternative Source Term - Marked-Up TS and Bases Pages ML0535500352005-12-12012 December 2005 Handout of Draft Proposed Change #2 Technical Specifications and Bases Changes from 12/12/05 Meeting on Safety Limit 2.1.1.1, Part 21 ML0535500322005-12-12012 December 2005 Handout of Draft Proposed Change #1 Technical Specifications Bases Changes from 12/12/05 Meeting on Safety Limit 2.1.1.1, Part 21 NL-05-0252, Technical Specifications Bases Revisions for 20042005-02-24024 February 2005 Technical Specifications Bases Revisions for 2004 NL-04-0981, Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases2004-06-0202 June 2004 Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases NL-04-0564, Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors2004-05-21021 May 2004 Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors NL-04-0233, Technical Specifications Bases Revisions for 20032004-02-24024 February 2004 Technical Specifications Bases Revisions for 2003 NL-03-0488, 10 CFR 50.59 Changes to the Technical Specification Bases2003-02-28028 February 2003 10 CFR 50.59 Changes to the Technical Specification Bases ML0227404922002-09-24024 September 2002 Revised Technical Specifications Pages for Post Accident Sampling System Submittal ML0220400142002-07-16016 July 2002 Revision to Request to Revise Technical Specifications: Quarterly Surveillance Extension ML0130604121995-03-0303 March 1995 Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases 2024-09-11
[Table view] |
Text
Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243
205 992 5000
September 11, 2024
Docket Nos.: 50-321 NL-23-0930 50-366 10 CFR 50.90
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001
Edwin I. Hatch Nuclear Plant - Units 1 & 2 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
Ladies and Gentlemen:
Pursuant to 10 CFR 50.90, Southern Nuclear Operating Company (SNC) requests a license amendment to the Edwin I. Hatch Nuclear Plant (HNP) Units 1 and 2 Renewed Facility Operating Licenses DPR-57 and NPF-5 respectively.
SNC requests adoption of TSTF-591, Revise Risk Informed Completion Time (RICT)
Program, which is an approved change to the Standard Technical Specifications (STS),
into the HNP Units 1 and 2 TS. TSTF-591 revises the Technical Specifications (TS)
Section 5.5 Program, Risk Informed Completion Time Program, to reference Regulatory Guide (RG) 1.200, Revision 3, instead of Revision 2, and to make other changes. A new report is added to TS Section 5.6, Reporting Requirements, to inform the NRC of newly developed methods used to calculate a RICT.
The enclosure provides a description and assessment of the proposed changes. provides the existing TS pages marked to show the proposed changes. provides revised (clean) TS pages. The proposed change does not affect the TS Bases.
SNC requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLIIP). Approval of the proposed amendment is requested within 6 months of acceptance. Once approved, the amendment shall be implemented within 90 days.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Georgia State Officials.
This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
U. S. Nuclear Regulatory Commission NL-23-0930 Page 2
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 11th day of September 2024.
Respectfully submitted,
Jamie M. Coleman Director, Regulatory Affairs Southern Nuclear Operating Company
JMC/agq/cbg
Enclosure:
Description and Assessment
Attachments: 1. Proposed Technical Specification Changes (Mark-up)
- 2. Revised Technical Specification Pages
cc: Regional Administrator, Region ll NRR Project Manager - Hatch 1 & 2 Senior Resident Inspector - Hatch 1 & 2 Director, Environmental Protection Division - State of Georgia RType: CHA02.004
Edwin I. Hatch Nuclear Plant - Units 1 & 2 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
Enclosure to NL-23-0930
Description and Assessment
Enclosure to NL-23-0930 Description and Assessment
1.0 DESCRIPTION
Southern Nuclear Operating Company (SNC) requests adoption of TSTF-591, Revise Risk Informed Completion Time (RICT) Program, which is an approved change to the Standard Technical Specifications (STS), into the HNP Units 1 and 2 TS. TSTF-591 revises the Technical Specifications (TS) Section 5.5 Program, Risk Informed Completion Time Program, to reference Regulatory Guide (RG) 1.200, Revision 3, instead of Revision 2, and to make other changes. A new report is added to TS Section 5.6, Reporting Requirements, to inform the NRC of newly developed methods used to calculate a RICT.
2.0 ASSESSMENT
2.1 Applicability of Safety Evaluation
SNC has reviewed the safety evaluation for TSTF-591 provided to the Technical Specifications Task Force in a letter dated September 21, 2023. This review included a review of the NRC staffs evaluation, as well as the information provided in TSTF-591.
SNC has concluded that the justifications presented in TSTF-591 and the safety evaluation prepared by the NRC staff are applicable to HNP Units 1 and 2 and justify this amendment for the incorporation of the changes to the HNP Units 1 and 2 TS.
2.2 Variations
SNC is not proposing any variations from the TS changes described in TSTF-591 or the applicable parts of the NRC staffs safety evaluation dated September 21, 2023.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Analysis
Southern Nuclear Operating Company (SNC) requests adoption of TSTF-591, Revise Risk Informed Completion Time (RICT) Program, which is an approved change to the Standard Technical Specifications (STS), into the HNP Units 1 and 2 TS. TSTF-591 revises the Technical Specifications (TS) Section 5.5 Program, Risk Informed Completion Time Program, to reference Regulatory Guide (RG) 1.200, Revision 3, instead of Revision 2, and to make other changes. A new report is added to TS Section 5.6, Reporting Requirements, to inform the NRC of newly developed methods used to calculate a RICT.
SNC has evaluated if a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, Issuance of amendment, as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No
E-1 Enclosure to NL-23-0930 Description and Assessment
The proposed change updates the standard for maintaining and updating PRA models used to calculate a RICT from NRC-approved Regulatory Guide 1.200, Revision 2, to NRC-approved Regulatory Guide 1.200, Revision 3. A new report is added to inform the NRC when a newly developed method is used.
The proposed change does not involve a significant increase in the probability of an accident previously evaluated because the change involves no change to the plant or its modes of operation. The proposed change does not increase the consequences of an accident because the design-basis mitigation function of the affected systems is not changed and the consequences of an accident during the extended Risk Informed Completion Time are no different from those during the existing Completion Time. The submittal of information-only reports has no effect on the initiators or consequences of any accidents previously evaluated.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No
The proposed change updates the standard for maintaining and updating PRA models used to calculate a RICT from NRC-approved Regulatory Guide 1.200, Revision 2, to NRC-approved Regulatory Guide 1.200, Revision 3. A new report is added to inform the NRC when a newly developed method is used. The proposed change does not change a design function or method of operation of the plant. The proposed change does not involve a physical alteration of the plant (no new or different kind of equipment will be installed).
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No
The proposed change updates the standard for maintaining and updating PRA models used to calculate a RICT from NRC-approved Regulatory Guide 1.200, Revision 2, to NRC-approved Regulatory Guide 1.200, Revision 3. A new report is added to inform the NRC when a newly developed method is used.
The proposed change supports the extension of Completion Times provided risk is assessed and managed in accordance wi th the NRC-approved RICT Program. The proposed change does not alter any design basis or safety limits. The proposed change affects the standard used to maintain the PRA models used in the RICT Program by changing from one NRC-approved standard to a later NRC-approved version and requiring submittal of an information-only report. The RICT Program will continue to assure that adequate margins of safety are maintained.
E-2 Enclosure to NL-23-0930 Description and Assessment
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, SNC concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.
3.2 Conclusion
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
4.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets t he eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or envir onmental assessment need be prepared in connection with the proposed amendment.
E-3 Edwin I. Hatch Nuclear Plant - Units 1 & 2 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
Attachment 1 to NL-23-0930
Proposed Technical Specification Changes (Markup)
Programs and Manuals 5.5
5.5 Programs and Manuals
5.5.16 Risk Informed Completion Time Program (continued)
- c. When a RICT is being used, any change to the plant config uration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on theRICT.
- 1. For planned changes, the revised RI CT must be determined prior to implementation of the change in configuration.
- 2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.
- 3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.
- d. For emergent conditions, if the extent of condition evaluation for inoper able structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure ( CCF) by either:
- 1. Numerically accounting for increased possibility of CCF in the RICT calculation;or
- 2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating even ts that challenge the function(s) performed by the ino perable SSCs.
- e. The risk assessment approaches and methods shall be acceptable to the NRC. The plant PRA shall be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant, as specified in Regulatory Guide 1.200, Revision 2. Methods to assess the risk from extending the Completion Times must be PRA methods used to support this license amendment, or other methods approved by the NRC for generic use; and any change in the PRA methods to assess risk that are outside these approval boundar ies require prior NRC approval.
- e. A RICT calculation must include the following hazard groups: Internal Events PRA model, Internal Flooding PRA model, Internal Fire Events PRA model, and seismic hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
HATCH UNIT 1 5.0-19a Amendment No. 319 Programs and Manuals 5.5
- f. The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
- g. A report shall be submitted in accordance with Specification 5.6.8 before a newly developed method is used to calculate a RICT.
HATCH UNIT 1 5.0-19a Amendment No. 319 Reporting Requirements 5.6
5.6 Reporting Requirements
5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPER ATURE LIMITS REPORT (PTLR) (continued)
ii. BWROG-TP-11-023-A, Revision 0 (0900876.401, Revision 0-A),
Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations, dated May 2013.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supp lement thereto.
5.6.8 Risk Informed Completion Time (RICT) Program Upgrade Report
A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
- a. The PRA models upgraded to include newly developed methods;
- b. A description of the acceptability of the newly de veloped methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, "Newly Developed Method Requirements and Peer Review;"
- c. Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were dispositioned; and
- d. All changes to key assumptions related to newly developed methods or their implementation.
HATCH UNIT 1 5.0-23 Amendment No. 287 Programs and Manuals 5.5
5.5 Programs and Manuals
5.5.16 Risk Informed Completion Time Program (continued)
- c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.
- 1. For planned changes, the revised RI CT must be determined prior to implementation of the change in configuration.
- 2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e.,
not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.
- 3. Revising the RICT is not required if the plant configuration cha nge would lower plant risk and would result in a longer RICT.
- d. For emergent conditions, if the extent of condition evaluatio n for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
- 1. Numerically accounting for the increased possibility of CCF in the RICT calculation; or
- 2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support re dundant or diverse SSCs that perform the function(s) of the inoperab le SSCs, and, if practicable, reduce the frequency of initiating even ts that challenge the function(s) performed by the inoperable SSCs.
- e. The risk assessment approaches and methods shall be acceptable to the NRC. The plant PRA shall be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant, as specified in Regulatory Guide 1.200, Revision 2. Methods to assess the risk from extending the Completion Times must be PRA methods used to support this license amendment, or other methods approved by the NRC for generic use; and any change in the PRA methods to assess risk that are outside these approval boundarie s require prior NRC approval.
- e. A RICT calculation must include the following hazard groups: Internal Events PRA model, Internal Flooding PRA model, Internal Fire Events PRA model, and seismic hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
HATCH UNIT 2 5.0-19a Amendment No. 264 Programs and Manuals 5.5
- f. The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
- g. A report shall be submitted in accordance with Specification 5.6.8 before a newly developed method is used to calculate a RICT.
HATCH UNIT 2 5.0-19a Amendment No. 264 Reporting Requirements 5.6
5.6 Reporting Requirements
5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPER ATURE LIMITS REPORT (PTLR) (continued)
ii. BWROG-TP-11-023-A, Revision 0 (0900876.401, Revision 0-A),
Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations, dated May 2013.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supp lement thereto.
5.6.8 Risk Informed Completion Time (RICT) Program Upgrade Report
A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
- a. The PRA models upgraded to include newly developed methods;
- b. A description of the acceptability of the newly de veloped methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, "Newly Developed Method Requirements and Peer Review;"
- c. Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were dispositioned; and
- d. All changes to key assumptions related to newly developed methods or their implementation.
HATCH UNIT 2 5.0-23 Amendment No. 232 Edwin I. Hatch Nuclear Plant - Units 1 & 2 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
Attachment 2 to NL-23-0930
Revised Technical Specification Pages
Programs and Manuals 5.5
5.5 Programs and Manuals
5.5.16 Risk Informed Completion Time Program (continued)
- c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06- 09-A, Appendix A, must be considered for the effect on the RICT.
- 1. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.
- 2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.
- 3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.
- d. For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
- 1. Numerically accounting for increased possibility of CCF in the RICT calculation; or
- 2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.
- e. A RICT calculation must include the following hazard groups: Internal Events PRA model, Internal Flooding PRA model, Internal Fire Events PRA model, and seismic hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
- f. The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
- g. A report shall be submitted in accordance with Specification 5.6.8 before a newly developed method is used to calculate a RICT.
HATCH UNIT 1 5.0- 19a Amendment No.
Reporting Requirements 5.6
5.6 Reporting Requirements
5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued)
ii. BWROG-TP-11-023-A, Revision 0 (0900876.401, Revision 0-A),
Lin ear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations, dated May 2013.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
5.6.8 Risk Informed Completion Time (RICT) Program Upgrade Report
A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
- a. The PRA models upgraded to include newly developed methods;
- b. A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, "Newly Developed Method Requirements and Peer Review;"
- c. Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were d ispositioned; and
- d. All changes to key assumptions related to newly developed methods or their implementation.
HATCH UNIT 1 5.0-23 Amendment No.
Programs and Manuals 5.5
5.5 Programs and Manuals
5.5.16 Risk Informed Completion Time Program (continued)
- c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06- 09-A, Appendix A, must be considered for the effect on the RICT.
- 1. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.
- 2. For emergent conditions, the revised R ICT must be determined within the time limits of the Required Action Completion Time (i.e.,
not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.
- 3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.
- d. For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
- 1. Numerically accounting for the increased possibility of CCF in the RICT calculation; or
- 2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.
- e. A RICT calculation must include the following hazard groups: Internal Events PRA model, Internal Flooding PRA model, Internal Fire Events PRA model, and seismic hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
- f. The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
- g. A report shall be submitted in accordance with Specification 5.6.8 before a newly developed method is used to calculate a RICT.
HATCH UNIT 2 5.0- 19a Amendment No.
Reporting Requirements 5.6
5.6 Reporting Requirements
5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued)
ii. BWROG-TP 023-A, Revision 0 (0900876.401, Revision 0-A),
Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations, dated May 2013.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
5.6.8 Risk Informed Completion Time (RICT) Program Upgrade Report
A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
- a. The PRA models upgraded to include newly developed methods;
- b. A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, "Newly Developed Method Requirements and Peer Review;"
- c. Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were d ispositioned; and
- d. All changes to key assumptions related to newly dev eloped methods or their implementation.
HATCH UNIT 2 5.0-23 Amendment No.