Similar Documents at Hatch |
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Category:Letter type:NL
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-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-22-0832, 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-22-0800, 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-22-0801, 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 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0499, Registration of Spent Fuel Cask Use2022-06-27027 June 2022 Registration of Spent Fuel Cask Use NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0365, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R302022-05-31031 May 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R30 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-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0315, Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days2022-05-0404 May 2022 Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days NL-22-0325, Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-05-0303 May 2022 Withdrawal of 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-22-0283, 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.2022-04-29029 April 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-22-0271, Changes to the Physical Security Plan2022-04-19019 April 2022 Changes to the Physical Security Plan NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 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-22-0220, Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 20222022-03-28028 March 2022 Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 2022 NL-22-0221, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2022-03-28028 March 2022 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) 2024-01-30
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNL-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 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) 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 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. NL-16-1564, Revised Technical Specifications Pages for Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-Write.2016-09-20020 September 2016 Revised Technical Specifications Pages for Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-Write. NL-16-1328, License Amendment Request Concerning Safety Limit Minimum Critical Power Ratio2016-08-29029 August 2016 License Amendment Request Concerning Safety Limit Minimum Critical Power Ratio ML16245A2582016-08-29029 August 2016 License Amendment Request Concerning Safety Limit Minimum Critical Power Ratio NL-16-1390, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Correction to Attachment 32016-08-24024 August 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, Correction to Attachment 3 2023-12-06
[Table view] Category:Technical Specification
MONTHYEARNL-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 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-04-1001, 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 ML0406905122004-03-0808 March 2004 Technical Specification for Amendment 239, 3/8/04 ML0406905022004-03-0808 March 2004 Technical Specification for Amendment 182, 3/8/04 NL-04-0233, Technical Specifications Bases Revisions for 20032004-02-24024 February 2004 Technical Specifications Bases Revisions for 2003 NL-03-2517, Application for Technical Specification Improvement to Revise TS 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process2004-02-0202 February 2004 Application for Technical Specification Improvement to Revise TS 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process 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 2023-12-06
[Table view] Category:Amendment
MONTHYEARNL-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-21-0984, 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-19-0250, 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-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-16-0827, 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-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 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-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-04-0563, 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 NL-03-2517, Application for Technical Specification Improvement to Revise TS 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process2004-02-0202 February 2004 Application for Technical Specification Improvement to Revise TS 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process ML0306301082003-02-24024 February 2003 Tech Spec Pages for Amendment Nos. 236 & 178, Respectively, Revising the Technical Specification Surveillance Requirement SR 3.6.4.12 ML0234502762002-12-0202 December 2002 Technical Specifications Revision to Secondary Containment Access Door Surveillance ML0229802952002-10-23023 October 2002 Request to Revise Technical Specifications: Correction to Quarterly Surveillance Extension Technical Specifications Page ML0219601412002-07-0303 July 2002 Revision to Request to Revise Technical Specifications: Quarterly Surveillance Extension, Enclosure 7, Technical Specifications Page Change Instructions, Unit 2 ML0210603492002-04-11011 April 2002 TS Pages to Amendment 230 ML0210603572002-04-11011 April 2002 TS Pages to Amendment 171 ML0207204142002-03-0808 March 2002 Technical Specification Pages for Amendments 228 & 170 for Edwin I. Hatch, Units 1 & 2 ML0205700232002-02-20020 February 2002 Technical Specification Pages Amendment 226 Revising to Allow a one-timer Defferal of the Type a Containment Integrated Leak Rate Test 2023-12-06
[Table view] |
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3535 Colonnade Parkway Cheryl A. Gayheart Birmingham, AL 35243 Regulatory Affairs Director 205 992 5316 cagayhea@southernco.com February 4, 2022 NL-21-1037 Docket Nos. 50-321 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling" Pursuant to 10 CFR 50.90, Southern Nuclear Operating Company (SNC) hereby requests a license amendment to 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-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specification (TS) exception to entering Mode 4 if both required Residual Heat Removal (RHR) shutdown cooling subsystems are inoperable.
The enclosure provides a description and assessment of the proposed changes. Attachment 1 provides the existing TS pages marked to show the proposed changes. Attachment 2 provides clean typed TS pages. Attachment 3 provides the existing TS Bases pages marked to show the revised text associated with the proposed TS changes and is provided for information only.
SNC requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLIIP). Approval of the proposed amendment is requested within six months of completion of the NRCs acceptance review. Once approved, the amendment shall be implemented within 90 days.
In accordance with 10 CFR 50.91, a copy of this application is being provided to the designated Georgia Official.
This letter contains no regulatory commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
U.S. Nuclear Regulatory Commission NL-21-1037 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 4th day of February 2022.
Respectfully submitted, Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company CAG/tle
Enclosure:
Description and Assessment Attachments: 1. Proposed Technical Specifications Changes (Mark-Up)
- 2. Revised Technical Specification Pages
- 3. Proposed Technical Specifications Bases Changes (Mark-Up) - For Information Only cc: Regional Administrator, Region II NRR Project Manager - Hatch Senior Resident Inspector - Hatch Director, Environmental Protection Division - State of Georgia RType: CHA02.004
ENCLOSURE Edwin I. Hatch Nuclear Plant - Units 1 and 2 Application to Revise Technical Specifications to Adopt TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling" Description and Assessment
Description and Assessment
1.0 DESCRIPTION
Southern Nuclear Operating Company (SNC) hereby requests a license amendment to 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-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specification (TS) exception to entering Mode 4 if both required Residual Heat Removal (RHR) shutdown cooling subsystems are inoperable.
Associated TS Bases are revised to reflect these TS changes.
2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation SNC has reviewed the safety evaluation for TSTF-580 provided to the Technical Specifications Task Force in a letter dated July 11, 2021. This review included a review of the NRC staffs evaluation, as well as the information provided in TSTF-580. SNC has concluded that the justifications presented in TSTF-580 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 TS.
Adoption of TSTF-566-A, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems,"
was approved by the NRC for HNP Units 1 and 2 on November 13, 2019 (ML19267A023).
2.2 Optional Changes and Variations SNC is not proposing any variations from the TS changes described in TSTF-580 or the applicable parts of the NRC staffs safety evaluation dated July 11, 2021.
HNP TS utilize different numbering than the Standard Technical Specifications on which TSTF-580 was based. Specifically, HNP equivalent TS are numbered as TS 3.4.7 instead of the Standard Technical Specification numbering of TS 3.4.8. This difference is administrative and does not affect the applicability of TSTF-580 to the HNP TS.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Analysis Southern Nuclear Operating Company (SNC) requests adoption of TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specifications (TS) exception to entering Mode 4 if both required Residual Heat Removal (RHR) shutdown cooling subsystems are inoperable.
SNC has evaluated if a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
E-1
Description and Assessment
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable. The RHR System in the shutdown cooling mode performs the important safety function of removing decay heat from the reactor coolant system during shutdown. The RHR System in the shutdown cooling mode is not an initiator of any accident previously evaluated or assumed to mitigate any accident previously evaluated. The design and function of the RHR System are not affected by the proposed change.
The proposed change would also exempt entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable and other operating modes of the RHR System are inoperable, such as Low Pressure Core Injection (LPCI) and RHR suppression pool cooling, and both subsystems of the support system for the RHR System heat exchangers, the RHR Service Water (RHRSW) System, are inoperable. The TS for those RHR operating modes and the RHRSW System require entering Mode 4 when both required subsystems are inoperable. Those operating modes and systems are not initiators to any accident previously evaluated but are used to mitigate the consequences of an accident previously evaluated. However, the consequences of an accident previously evaluated resulting from remaining in Mode 3 versus Mode 4 when RHR shutdown cooling subsystems are inoperable are not significantly increased because there would be no dependable method to remove post-accident decay heat in Mode 4 if both required RHR shutdown cooling subsystems are inoperable.
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 provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable. The proposed change does not affect the design function or operation of the RHR System or the RHRSW System. No new equipment is being installed as a result of the proposed change. The proposed change affects the actions taken when both required RHR shutdown cooling subsystems are inoperable, so no new failure mechanisms are created.
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 provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable. The proposed change does not change any E-2
Description and Assessment specific values or controlling parameters that define margin in the design or licensing basis. No safety limits are affected by the proposed change. The proposed change applies when both required RHR shutdown cooling subsystems are inoperable, so no design or safety limits associated with the operation of the RHR System are affected.
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 EVALUATION 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 the 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 environmental assessment need be prepared in connection with the proposed amendment.
E-3
Edwin I. Hatch Nuclear Plant - Units 1 and 2 Application to Revise Technical Specifications to Adopt TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling" Attachment 1 Proposed Technical Specification Changes (Mark-Up)
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES-------------------------------------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for performance of Surveillances.
APPLICABILITY: MODE 3 with reactor steam dome pressure less than the RHR low pressure permissive pressure.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems method of decay heat inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> subsystem. thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion RHR shutdown cooling Time of Condition A not subsystem(s) to met. OPERABLE status.
(continued)
HATCH UNIT 1 3.4-13 Amendment No. 300
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Two RHR shutdown C.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems method of decay heat inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> subsystem. thereafter D. Required Action and -----------------NOTE------------------
associated Completion LCO 3.0.3 and all other LCO Time of Condition C not Required Actions requiring a met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status.
EC. No RHR shutdown cooling EC.1 Initiate action to restore Immediately subsystem in operation. one RHR shutdown cooling subsystem or AND one recirculation pump to operation.
No recirculation pump in operation. AND EC.2 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND EC.3 Monitor reactor coolant Once per hour temperature and pressure.
HATCH UNIT 1 3.4-14 Amendment No. 300
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES-------------------------------------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for performance of Surveillances.
APPLICABILITY: MODE 3 with reactor steam dome pressure less than the RHR low pressure permissive pressure.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems method of decay heat inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> subsystem. thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion RHR shutdown cooling Time of Condition A not subsystem(s) to met. OPERABLE status.
(continued)
HATCH UNIT 2 3.4-13 Amendment No. 245
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Two RHR shutdown C.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems method of decay heat inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> subsystem. thereafter D. Required Action and -----------------NOTE------------------
associated Completion LCO 3.0.3 and all other LCO Time of Condition C not Required Actions requiring a met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status.
EC. No RHR shutdown cooling EC.1 Initiate action to restore Immediately subsystem in operation. one RHR shutdown cooling subsystem or AND one recirculation pump to operation.
No recirculation pump in operation. AND EC.2 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND EC.3 Monitor reactor coolant Once per hour temperature and pressure.
HATCH UNIT 2 3.4-14 Amendment No. 245
Edwin I. Hatch Nuclear Plant - Units 1 and 2 Application to Revise Technical Specifications to Adopt TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling" Attachment 2 Revised Technical Specification Pages
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES-------------------------------------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for performance of Surveillances.
APPLICABILITY: MODE 3 with reactor steam dome pressure less than the RHR low pressure permissive pressure.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystem method of decay heat inoperable. removal is available. AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to met. OPERABLE status.
(continued)
HATCH UNIT 1 3.4-13 Amendment No.
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Two RHR shutdown C.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems method of decay heat inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> subsystem. thereafter D. Required Action and -----------------NOTE------------------
associated Completion LCO 3.0.3 and all other LCO Time of Condition C not Required Actions requiring a met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status.
E. No RHR shutdown cooling E.1 Initiate action to restore Immediately subsystem in operation. one RHR shutdown cooling subsystem or AND one recirculation pump to operation.
No recirculation pump in operation. AND E.2 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND E.3 Monitor reactor coolant Once per hour temperature and pressure.
HATCH UNIT 1 3.4-14 Amendment No.
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES-------------------------------------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for performance of Surveillances.
APPLICABILITY: MODE 3 with reactor steam dome pressure less than the RHR low pressure permissive pressure.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystem method of decay heat inoperable. removal is available. AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to met. OPERABLE status.
(continued)
HATCH UNIT 2 3.4-13 Amendment No.
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Two RHR shutdown C.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems method of decay heat inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> subsystem. thereafter D. Required Action and -----------------NOTE------------------
associated Completion LCO 3.0.3 and all other LCO Time of Condition C not Required Actions requiring a met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status.
E. No RHR shutdown cooling E.1 Initiate action to restore Immediately subsystem in operation. one RHR shutdown cooling subsystem or AND one recirculation pump to operation.
No recirculation pump in operation. AND E.2 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND E.3 Monitor reactor coolant Once per hour temperature and pressure.
HATCH UNIT 2 3.4-14 Amendment No.
Edwin I. Hatch Nuclear Plant - Units 1 and 2 Application to Revise Technical Specifications to Adopt TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling" Attachment 3 Proposed Technical Specification Bases Changes (Mark-Up)
For Information Only
RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES (continued)
ACTIONS A Note has been provided to modify the ACTIONS related to RHR shutdown cooling subsystems. Section 1.3, Completion Times, specifies once a Condition has been entered, subsequent divisions, subsystems, components or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition. Section 1.3 also specifies Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition.
However, the Required Actions for inoperable shutdown cooling subsystems provide appropriate compensatory measures for separate inoperable shutdown cooling subsystems. As such, a Note has been provided that allows separate Condition entry for each inoperable RHR shutdown cooling subsystem.
A.1 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the overall reliability is reduced because a single failure in the OPERABLE subsystem could result in reduced RHR shutdown cooling capability.
Therefore, an alternate method of decay heat removal must be provided.
With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided for the initial RHR shutdown cooling subsystem inoperability.
This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of these alternate method(s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.
The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Condensate/Main Steam Systems, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.
(continued)
HATCH UNIT 1 B 3.4-31 REVISION 106
RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES (continued)
ACTIONS B.1 If required alternate method(s) of decay heat removal cannot be verified within one hour, immediate action must be taken to restore the inoperable RHR shutdown cooling subsystem(s) to operable status. The Required Action will restore redundant decay heat removal paths. The immediate Completion Time reflects the importance of maintaining the availability of two paths for heat removal.
C.1 With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided for the initial RHR shutdown cooling subsystem inoperability.
This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of these alternate method(s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.
The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.
D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status.
The immediate Completion Time reflects the importance of restoring a method of heat removal.
Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available. When at least one RHR subsystem HATCH UNIT 1 B 3.4-32 REVISION 106
RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES (continued) is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.
EC.1, EC.2, and EC.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or recirculation pump must be restored without delay.
Until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This will provide assurance of continued temperature monitoring capability.
During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.
SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant.
The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
(continued)
HATCH UNIT 1 B 3.4-33 REVISION 106
RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES (continued)
ACTIONS A Note has been provided to modify the ACTIONS related to RHR shutdown cooling subsystems. Section 1.3, Completion Times, specifies once a Condition has been entered, subsequent divisions, subsystems, components or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition. Section 1.3 also specifies Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition.
However, the Required Actions for inoperable shutdown cooling subsystems provide appropriate compensatory measures for separate inoperable shutdown cooling subsystems. As such, a Note has been provided that allows separate Condition entry for each inoperable RHR shutdown cooling subsystem.
A.1 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the overall reliability is reduced, however, because a single failure in the OPERABLE subsystem could result in reduced RHR shutdown cooling capability. Therefore, an alternate method of decay heat removal must be provided.
With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided for the initial RHR shutdown cooling subsystem inoperability.
This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of these alternate method(s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.
The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Condensate/Main Steam Systems, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.
(continued)
HATCH UNIT 2 B 3.4-32 REVISION 118
RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES ACTIONS B.1 If the required alternate method(s) of decay heat removal cannot be verified within one hour, immediate action must be taken to restore the inoperable RHR shutdown cooling subsystem(s) to operable status. The Required Action will restore redundant decay heat removal paths. The immediate Completion Time reflects the importance of maintaining the availability of two paths for heat removal.
C.1 With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided for the initial RHR shutdown cooling subsystem inoperability.
This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of these alternate method(s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.
The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.
D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status.
The immediate Completion Time reflects the importance of restoring a method of heat removal.
Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown (continued)
HATCH UNIT 2 B 3.4-33 REVISION 118
RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES ACTIONS cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available. When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.
EC.1, EC.2, and EC.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or recirculation pump must be restored without delay.
Until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This will provide assurance of continued temperature monitoring capability.
During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.
SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant.
The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
(continued)
HATCH UNIT 2 B 3.4-34 REVISION 118