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Category:Letter
MONTHYEARIR 05000321/20230042024-01-31031 January 2024 Integrated Inspection Report 05000321/2023004 and 05000366/2023004 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. ML24012A0652024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000321/20233012024-01-17017 January 2024 NRC Operator License Examination Report 05000321/2023301 and 05000366/2023301 ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) 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 IR 05000321/20234022023-11-29029 November 2023 Security Baseline Inspection Report 05000321/2023402, 05000366/2023402, and 07200036/2023401 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 IR 05000321/20230112023-11-17017 November 2023 Biennial Problem Identification and Resolution Inspection Report 050003212023011 and 050003662023011 ML23324A4472023-11-14014 November 2023 302 Exam Approval Letter IR 05000321/20230032023-11-0202 November 2023 Integrated Inspection Report 05000321/2023003, and 05000366/2023003 IR 05000321/20234032023-10-26026 October 2023 Cyber Security Inspection Report 05000321/2023403 and 05000366/2023403 IR 05000321/20234012023-10-17017 October 2023 Security Baseline Inspection Report 05000321 2023401 and 05000366 2023401 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report IR 05000321/20230052023-08-27027 August 2023 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 & 2 - Report 05000321/2023005 and 05000366/2023005 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 IR 05000321/20230022023-08-0808 August 2023 Integrated Inspection Report 07200036/2023001, 05000321/2023002, and 05000366/2023002 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 ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23201A0292023-07-20020 July 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML23178A0012023-06-27027 June 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000321 2023403 and 05000366 2023403 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 IR 05000321/20230102023-06-0909 June 2023 Focused Engineering Inspection Report 05000321 2023010 and 05000366 2023010 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. ML23136B2942023-05-19019 May 2023 Summary of May 02, 2023, Observation Public Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a LAR for the Reactor Pressure Vessel Head Closure Bolts for Edwin I. Hatch Nuclear Plant, Units 1 and 2 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 ML23123A2222023-05-0101 May 2023 Notification of Licensed Operator Initial Examination 05000321/2023301, and 05000366/2023301 IR 05000321/20230012023-04-26026 April 2023 Integrated Inspection Report 05000321/2023001 and 05000366/2023001 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-23-0014, 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-23-0208, 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-23-0228, 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 ML23065A1092023-03-0808 March 2023 Correction of Relief Request HNP-ISI-RR-05-02 Allowing to Continue Operation with a Flaw Indication on One Reactor Pressure Vessel Closure Bolt Until December 31, 2025 ML23053A2182023-03-0303 March 2023 Correction of Amendment Nos. 321 and 266 Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program IR 05000321/20220062023-03-0101 March 2023 Annual Assessment Letter Edwin I. Hatch Nuclear Plant, Units 1 and 2 - NRC Inspection Report 05000321/2022006 and 05000366/2022006 NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 2024-01-31
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23053A2182023-03-0303 March 2023 Correction of Amendment Nos. 321 and 266 Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 ML23018A0042023-01-24024 January 2023 Correction of Amendment Nos. 319 and 264 Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF ML22297A1462022-12-22022 December 2022 Issuance of Amendments Nos. 319 and 264, Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITS ML22325A3472022-11-23023 November 2022 Correction of Amendment Nos. 318 and 263 Issuance of Amendment Nos. 318 and 263, Regarding LAR to Revise TSTF-227 and TSTF-297 ML22293A0302022-11-0707 November 2022 Amendments 318 & 263 Issuance, Regarding LAR to Adopt TSTF-227, Revision to EOC-RPT Pump Actions, and TSTF-297, ATWS-RPT (EPID L-2021-LLA- 0227) ML22192A1172022-09-0202 September 2022 Issuance of Amendments Nos. 317 & 262, Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates ML22192A1992022-08-19019 August 2022 Issuance of Amendments Nos. 316 and 261, Regarding Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22101A0942022-05-20020 May 2022 Issuance of Amendments Nos. 315 and 260, Regarding Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21264A6442021-09-24024 September 2021 Issuance of Amendment to Revise Technical Specification 3.7.2, Plant Service Water (Psw) System and Ultimate Heat Sink (UHS) (EPID L-2021-LLA-0164) (Emergency Circumstances) ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21159A1782021-06-15015 June 2021 Correction of Amendment Nos. 277 and 221 Application to Relocate the Pressure-Temperature Limit Curves Following TSTF-419 NL-21-0379, Southern Nuclear Operating Company - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions2021-04-27027 April 2021 Southern Nuclear Operating Company - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21109A3592021-04-22022 April 2021 Issuance of Amendment No. 254, Regarding Revision to Technical Specifications for One-Time Extension of Completion Times Related to Residual Heat Removal System (Emergency Circumstances) ML21095A0872021-04-19019 April 2021 Non-Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values ML21028A3882021-02-0101 February 2021 Revised Correction of Amendment Nos. 308 and 253 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements ML21014A3752021-01-26026 January 2021 Correction of Amendment Nos. 308 and 253 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements ML20294A0762020-12-0707 December 2020 Issuance of Amendments Nos. 308 and 253, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements ML20254A0572020-09-18018 September 2020 Issuance of Amendments Nos. 307 and 252, Regarding License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC (Alternating Current) Sources - Operating, ML20202A0052020-09-15015 September 2020 Issuance of Amendments Nos. 306 and 251, Regarding the Application to Revise Technical Specifications to Adopt TSTF-568, Revise Appliciability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20077J7042020-06-26026 June 2020 Issuance of Amendment Nos. 305 and 250, Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML20167A0132020-06-17017 June 2020 Correction of Amendments Nos. 304 & 249 License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 EPID L-2018-LLA-0107 ML20066F5922020-06-11011 June 2020 Issuance of Amendments Nos. 304 and 249, Regarding License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19239A2442019-11-19019 November 2019 Issuance of Amendments Regarding Revision to Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations ML19267A0232019-11-13013 November 2019 Issuance of Amendments the Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable (Residual Heat Removal) RHR Shutdown Cooling Subsystems, Using Consolidated Line Item Improvement Process ML19212A0542019-09-20020 September 2019 Issuance of Amendments 299 and 244 Regarding Revision to Technical Specifications to Adopt Tstf-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19198A1042019-09-0404 September 2019 Issuance of Amendments Regarding Revision to Technical Specification 3.6.4.1 - Secondary Containment ML19177A1662019-07-0808 July 2019 Edwin Hatch Unit Nos. 1 and 2, Issuance of Amendments Regarding License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function ML19091A2912019-04-30030 April 2019 Issuance of Amendments 296 and 241 to Revise Technical Specifications 3.6.2.5, Condition C, Residual Heat Removal Drywell Spray End State ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML19053A0932019-02-22022 February 2019 Issuance of Amendments to Revise Technical Specification 3.8.1, AC Sources - Operating (EPID L-2019-LLA-0026) (Emergency Circumstances) ML19010A0092019-01-28028 January 2019 Issuance of Amendments to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation ML18302A2562018-11-0202 November 2018 Correction of Amendment No. 227 Adoption of TSTF-65-A, Revision 1 ML18222A2962018-08-29029 August 2018 Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) ML18123A3682018-05-31031 May 2018 Issuance of Amendments to Adopt TSTF-542, RPV Water Inventory Control (CAC Nos. MF9662 and MF9663; EPID L-2017-LLA-0215) ML17355A4402018-01-22022 January 2018 Issuance of Amendments to Revise TS 3.6.4.1, Secondary Containment (CAC Nos. MF9590 and MF9591; EPID L-2017-LLA-0216) ML17271A3072017-11-30030 November 2017 Issuance of Amendments to Revise Actions of TS 5.5.12, Primary Containment Leakage Rate Testing Program ML17208A2312017-08-29029 August 2017 Issuance of Amendments Regarding the Adoption of TSTF 500, DC Electrical Rewrite - Update to TSTF 360 ML17152A2182017-06-30030 June 2017 Southern Nuclear Fleet - Issuance of Amendments Regarding the Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing (CAC Nos. MF8176 - MF8181) ML17137A0412017-06-27027 June 2017 Issuance of Amendments Regarding the Adoption of TSTF-529, Revision 4, Clarify Use and Application Rules (CAC Nos. MF8897, MF8898, MF8900-MF8902, and MF8921) ML17023A2372017-03-16016 March 2017 Issuance of Amendments Regarding the Adoption of NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors(Cac Nos. MF7460-MF7465) ML16141A1472017-03-14014 March 2017 Issuance of Amendments to Incorporate Southern Nuclear Company Fleet Emergency Plan ML16291A0302017-01-13013 January 2017 Issuance of Amendments the Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions (CAC Nos. MF7466, MF7467, MF7468, MF7469, MF7470, & MF7471) 2023-03-03
[Table view] Category:Safety Evaluation
MONTHYEARML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 ML22297A1462022-12-22022 December 2022 Issuance of Amendments Nos. 319 and 264, Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITS ML22293A0302022-11-0707 November 2022 Amendments 318 & 263 Issuance, Regarding LAR to Adopt TSTF-227, Revision to EOC-RPT Pump Actions, and TSTF-297, ATWS-RPT (EPID L-2021-LLA- 0227) ML22192A1172022-09-0202 September 2022 Issuance of Amendments Nos. 317 & 262, Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates ML22192A1992022-08-19019 August 2022 Issuance of Amendments Nos. 316 and 261, Regarding Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22101A0942022-05-20020 May 2022 Issuance of Amendments Nos. 315 and 260, Regarding Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21264A6442021-09-24024 September 2021 Issuance of Amendment to Revise Technical Specification 3.7.2, Plant Service Water (Psw) System and Ultimate Heat Sink (UHS) (EPID L-2021-LLA-0164) (Emergency Circumstances) ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality ML21109A3592021-04-22022 April 2021 Issuance of Amendment No. 254, Regarding Revision to Technical Specifications for One-Time Extension of Completion Times Related to Residual Heat Removal System (Emergency Circumstances) ML20294A0762020-12-0707 December 2020 Issuance of Amendments Nos. 308 and 253, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements ML20254A0752020-09-18018 September 2020 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 307 to Facility Operating License No. DPR-57 and Amendment No. 252 to Facility Operating License No. NPF-5 ML20202A0052020-09-15015 September 2020 Issuance of Amendments Nos. 306 and 251, Regarding the Application to Revise Technical Specifications to Adopt TSTF-568, Revise Appliciability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20077J7042020-06-26026 June 2020 Issuance of Amendment Nos. 305 and 250, Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML20066F5922020-06-11011 June 2020 Issuance of Amendments Nos. 304 and 249, Regarding License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML20143A2332020-06-0303 June 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal (EPID L-2020-LLR-0074 (COVID-19)) ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19239A2442019-11-19019 November 2019 Issuance of Amendments Regarding Revision to Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations ML19267A0232019-11-13013 November 2019 Issuance of Amendments the Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable (Residual Heat Removal) RHR Shutdown Cooling Subsystems, Using Consolidated Line Item Improvement Process ML19212A0542019-09-20020 September 2019 Issuance of Amendments 299 and 244 Regarding Revision to Technical Specifications to Adopt Tstf-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19198A1042019-09-0404 September 2019 Issuance of Amendments Regarding Revision to Technical Specification 3.6.4.1 - Secondary Containment ML19177A1662019-07-0808 July 2019 Edwin Hatch Unit Nos. 1 and 2, Issuance of Amendments Regarding License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function ML19091A2912019-04-30030 April 2019 Issuance of Amendments 296 and 241 to Revise Technical Specifications 3.6.2.5, Condition C, Residual Heat Removal Drywell Spray End State ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML19044A5552019-04-0303 April 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19064A0872019-03-0808 March 2019 Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-08 ML19053A0932019-02-22022 February 2019 Issuance of Amendments to Revise Technical Specification 3.8.1, AC Sources - Operating (EPID L-2019-LLA-0026) (Emergency Circumstances) ML19035A5502019-02-0606 February 2019 Relief Request HNP ISI RR 05-02 Regarding Reactor Pressure Vessel Head Stud Inservice Inspection Requirements ML19010A0092019-01-28028 January 2019 Issuance of Amendments to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation ML19011A0102019-01-22022 January 2019 Proposed Alternative HNP-ISI-ALT-05-04 for the Implementation of BWRVIP Guidelines ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure ML18289A6192018-10-18018 October 2018 Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-07 ML18222A2962018-08-29029 August 2018 Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) ML18163A1602018-06-15015 June 2018 Proposed Alternative RR-V-11, Extension of Main Steam Safety Relief Valve Test Interval ML18123A3682018-05-31031 May 2018 Issuance of Amendments to Adopt TSTF-542, RPV Water Inventory Control (CAC Nos. MF9662 and MF9663; EPID L-2017-LLA-0215) ML18102B0162018-04-16016 April 2018 Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-05 (CAC Nos. MF9812 and MF9813; EPID L-2017-LLR-0053) ML18022A1072018-01-25025 January 2018 Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059) ML17355A4402018-01-22022 January 2018 Issuance of Amendments to Revise TS 3.6.4.1, Secondary Containment (CAC Nos. MF9590 and MF9591; EPID L-2017-LLA-0216) ML17271A3072017-11-30030 November 2017 Issuance of Amendments to Revise Actions of TS 5.5.12, Primary Containment Leakage Rate Testing Program ML17279A0452017-10-26026 October 2017 Relief Requests ISI-RR-13, -14, -18, -19, -23, and -24 for Relief from Inservice Inspection Requirements ML17268A0442017-10-20020 October 2017 Relief Requests ISI RR 16, ISI-RR-17, ISI-44-21, and ISI-RR-22 for Relief from Inservice Inspection Requirements ML17208A2312017-08-29029 August 2017 Issuance of Amendments Regarding the Adoption of TSTF 500, DC Electrical Rewrite - Update to TSTF 360 2023-08-02
[Table view] |
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May 28, 2004 Mr. H. L. Sumner, Jr.
Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 RE: ISSUANCE OF AMENDMENTS REVISING THE TECHNICAL SPECIFICATIONS FOR THE PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM (TAC NOS.
MC1432 AND MC1433)
Dear Mr. Sumner:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 241 to Renewed Facility Operating License DPR-57 and Amendment No. 184 to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Units 1 and 2. The amendments consist of changes to the Technical Specifications in response to your application dated December 1, 2003, as supplemented on March 10 and March 30, 2004.
The amendments revise the technical specification regarding the primary leakage rate testing program.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Christopher Gratton, Senior Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366
Enclosures:
- 1. Amendment No. 241 to DPR-57
- 2. Amendment No. 184 to NPF-5
- 3. Safety Evaluation cc w/encls: See next page
ML041530387 Enclosure 2: ML041540112 *See ML041320563 OFFICE PDII-1/PM PDII-1/LA (A) DSSA/SPSB DIPM/IROBA OGC PDII-1/SC (A)
NAME CGratton DClarke RLDennig* TBoyce SLewis SCoffin DATE 5/19/04 5/19/04 5/10/04 5/21/04 5/26/04 5/27/04 FOR DISTRIBUTION EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 RE: ISSUANCE OF AMENDMENTS REVISING THE TECHNICAL SPECIFICATIONS FOR THE PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM (TAC NOS. MC1432 AND MC1433)
Dated: May 28, 2004 DISTRIBUTION:
PUBLIC PDII-1 R/F RidsNrrDlpmLpdii (EHackett)
RidsNrrDlpmLpdii-1 (SCoffin)
RidsNrrPMCGratton DClarke RidsOgcRp RidsAcrsAcnwMailCenter GHill (4 Copies)
TBoyce RidsRgn2MailCenter (VMcCree)
RidsNrrDlpmDpr RDennig EThrom BBonser, RII WBeckner
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 241 Renewed License No. DPR-57
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility)
Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated December 1, 2003, as supplemented on March 10 and 30, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-57 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 241, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephanie M. Coffin, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: May 28, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 241 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 5.0-16 5.0-16
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 184 Renewed License No. NPF-5
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility)
Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated December 1, 2003, as supplemented on March 10 and 30, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-5 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 184, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephanie M. Coffin, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: May 28, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 184 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 5.0-16 5.0-16
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 241 TO RENEWED FACILITY OPERATING LICENSE DPR-57 AND AMENDMENT NO. 184 TO RENEWED FACILITY OPERATING LICENSE NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC., ET AL.
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-321 AND 50-366
1.0 INTRODUCTION
By letter dated December 1, 2003 (Reference 1), Southern Nuclear Operating Company (SNC, the licensee), proposed a change to the Edwin I. Hatch (Hatch) Nuclear Plant, Units 1 and 2, Technical Specifications (TSs), Appendix A to operating licenses DPR-57 and NPF-5, respectively. The licensee proposes to change the peak calculated post-accident primary containment internal pressure values, Pa, in TS Section 5.5.12, Primary Containment Leakage Rate Testing Program, for Units 1 and Unit 2. The proposed change supports a 10 psi increase in the nominal reactor steam dome operating pressure at each unit. In response to the Nuclear Regulatory Commission (NRC) staffs request for additional information (RAI), the licensee provided supplemental information to support the proposed change by letters dated March 10, 2004 (Reference 2) and March 30, 2004 (Reference 3). The supplemental letters provided clarifying information that did not change the scope of the December 1, 2003, application nor the initial proposed no significant hazards consideration determination.
The purpose of the pressure increase in the nominal reactor steam dome pressure is to allow for additional flow control margin for the high pressure turbine. This flow margin is needed to operate the plants at 100 percent of the recently increased (Reference 4) rated thermal power level of 2804 MW(t).
2.0 REGULATORY EVALUATION
Hatchs primary containment leakage rate testing program (PCLRTP), TS Section 5.5.12, Primary Containment Leakage Rate Testing Program, satisfies the requirement that the primary containment meets the leakage rate test requirements of Appendix J to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 (Reference 5). Hatch uses Option B which identifies the performance-based requirements and criteria for preoperational and subsequent periodic leakage rate testing. This program was designed to ensure that (a) leakage through the primary containment or systems and components penetrating the primary containment does not exceed the allowable leakage rates specified in the TSs and (b) integrity of the containment structure is maintained during its service life.
The PCLRTP satisfies the requirements in General Design Criterion (GDC) 52, Capability for Containment Leakage Rate Testing, GDC 53, Provisions for Containment Testing and Inspection, and GDC 54, Systems Penetrating Containment, and has been previously accepted by the NRC staff. The PCLRTP is consistent with ANSI/ANS-56.8-199 (Reference 6),
and the guidance in Regulatory Guide (RG) 1.163 (Reference 7).
This safety evaluation addresses the safety analyses for the increased reactor steam dome nominal operating pressure to establish the post-accident primary containment internal pressure values, Pa, in TS Section 5.5.12 for Units 1 and 2.
3.0 TECHNICAL EVALUATION
The licensee evaluated the 10 psi increase in the nominal reactor steam dome operating pressure under the provisions of 10 CFR 50.59, Changes, tests and experiments. The licensee reviewed the balance of plant and the nuclear steam supply system systems, structures, analyses, transients and special events. The impact of the pressure increase on applicable plant programs, such as motor operator valve testing, equipment qualification and Appendix J testing, was also examined by the licensee. As a result of these analyses and evaluations, the licensee determined that, with the exception of the Appendix J testing, the 10 psi increase can be accomplished under the provisions of 10 CFR 50.59 since:
- The increased nominal pressure, from 1035 psig to 1045 psig, is within the reactor steam dome pressure TS 3.4.10 limiting condition for operation requirement of 1058 psig.
- No change is required to any TS allowable value associated with instrument settings that initiate protective functions, including (a) the reactor pressure vessel (RPV) steam dome pressure trip analytical limit or TS allowable value, and (b) the RPV water level trip analytical limits or TS allowable values.
- No change is required to the currently approved rated thermal power level of 2804 MW(t).
- No change is required to the maximum reactor core flow or power-to-flow map.
Plant implementation of the 10 psi increase will be accomplished through the SNC design change process. Following completion, the affected final safety analysis report (FSAR) sections will be submitted under the provisions of 10 CFR 50.71(e), Maintenance of records, making of reports, to reflect the change.
The licensee analyzed the containment response to the design-basis loss-of-coolant accident (LOCA) for the 10 psi increase in the nominal reactor steam dome operating pressure. This pressure increase resulted in a 1 EF increase in the saturation temperature in the steam dome.
All other plant parameters remained at their previously accepted values. The previously accepted analytical method, NEDO-10320 (Reference 8), was used for the analyses. The Unit 1 peak containment pressure increased from 50.5 psig to 50.8 psig. The Unit 2 peak
containment pressure increased from 46.9 psig to 47.3 psig. The design pressure is 56 psig for both units.
The NRC staff finds the licensees analyses of the peak containment pressure acceptable since the safety analysis method used has been previously accepted by the NRC staff and, with the exception of the increased pressure and temperature in the reactor steam dome, the other plant parameters remained at their previously acceptable values.
The licensee addressed the long-term suppression pool heatup in response to the NRC staffs RAI. The impact of the pressure and temperature increase on the peak suppression pool temperature was evaluated by the licensee. The previously accepted single bounding analysis from the extended power uprate (Reference 9) long-term containment (peak temperature) analysis was used for the assessment. This analysis, described in the Unit 2 FSAR Section 6.2.3.1.2.2, Containment Long-Term Response, used conservative inputs and assumptions to maximize the calculated suppression pool temperature response. The calculated peak suppression pool temperature was 208 EF. The licensees conservative evaluation concluded that the effect of the increased pressure and temperature in the reactor steam dome (sensible energy) on the long-term containment design-basis LOCA response is insignificant (less than 0.3 EF increase in the peak suppression pool temperature). The suppression pool design temperature is 281 EF for Unit 1 and 340 EF for Unit 2.
The existing Hatch long-term analysis takes no credit for passive structural heat sinks in the drywell, and suppression chamber (airspace and pool). After the RPV is depressurized, the suppression pool is the only heat sink considered in the analysis. Since the decay heat, the heat source, is dependent on the initial power level, which is unchanged with the pressure increase, the long-term containment response will not be significantly impacted by the 10 psi reactor steam dome nominal operating pressure increase. The main effect of the pressure increase is the increase in the initial stored sensible energy in the fluid and the solid components within the RPV. The additional sensible energy in the RPV is an insignificant contributor to the overall peak suppression pool temperature response when compared to the other conservative input assumptions used for the long-term containment analysis. The NRC staff agrees with the licensees assessment that the peak suppression pool temperature during the design-basis LOCA remains bounded by the currently accepted value of 208 EF.
3.1
SUMMARY
The NRC staff finds the licensees revised safety analyses for the design-basis LOCA, used to determine the values for the proposed change to the peak calculated post-accident primary containment internal pressure value, Pa, in TS Section 5.5.12, Primary Containment Leakage Rate Testing Program, acceptable. The safety analysis method used has been previously accepted by the NRC staff and, with the exception of the increased pressure and temperature in the reactor steam dome, the other plant parameters remained at their previously accepted values.
The NRC staff finds the licensees proposed change to TS 5.5.12, increasing Pa from 50.5 psig to 50.8 psig for Unit 1 and from 46.9 psig to 47.3 psig for Unit 2, acceptable. The revised values for Pa, the calculated peak containment internal pressure for the design-basis LOCA, were conservatively calculated using an acceptable safety analysis method.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Georgia State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (69 FR 2747). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. H. L. Sumner, Jr., Southern Nuclear Operating Company, letter NL-03-2353, Edwin I.
Hatch Nuclear Plant Proposed Technical Specifications Revision to Primary Containment Leakage Rate Testing Program, to U.S. Nuclear Regulatory Commission, December 1, 2003 (ML033381137).
- 2. H. L. Sumner, Jr., Southern Nuclear Operating Company, letter NL-04-0371, Edwin I.
Hatch Nuclear Plant Clarification of the Proposed Technical Specifications Revision to Primary Containment Leakage Rate Testing Program, to U.S. Nuclear Regulatory Commission, March 10, 2004 (ML040720423).
- 3. H. L. Sumner, Jr., Southern Nuclear Operating Company, letter NL-04-0392, Edwin I.
Hatch Nuclear Plant Request for Additional Information on the Proposed Technical Specifications Revision to Primary Containment Leakage Rate Testing Program, to U.S.
Nuclear Regulatory Commission, March 30, 2004 (ML040930186).
- 4. S. Bloom, U.S. Nuclear Regulatory Commission, letter, Edwin I. Hatch Nuclear Plant, Unit 1 and 2 - Issuance of Amendments Regarding Appendix K Measurement Uncertainty Recovery, to H.L. Sumner, Jr., Southern Nuclear Operating Company, September 23, 2003 (ML032590944).
- 5. Appendix J to Part 50 -- Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B -- Performance-Based Requirements.
- 6. American National Standard ANSI/ANS-56.8-1994, Containment System Leakage Testing Requirements, dated August 4, 1994.
- 7. RG 1.163, Performance-Based Containment Leak-Test Program, dated September 1995.
- 8. NEDO-10320, The General Electric Pressure Suppression Containment Analytical Model, General Electric Company, April 1972; Supplement 1 May 1971; Supplement 2 January 1973.
- 9. NEDC-32749P, Extended Power Uprate Safety Analysis Report for Edwin I. Hatch Nuclear Plants Units 1 and 2, July 1997.
Principal Contributor: E. Throm Date: May 28, 2004
Edwin I. Hatch Nuclear Plant cc:
Laurence Bergen Arthur H. Domby, Esq.
Oglethorpe Power Corporation Troutman Sanders 2100 East Exchange Place Nations Bank Plaza P.O. Box 1349 600 Peachtree Street, NE, Suite 5200 Tucker, GA 30085-1349 Atlanta, GA 30308-2216 Mr. R. D. Baker Chairman Manager - Licensing Appling County Commissioners Southern Nuclear Operating County Courthouse Company, Inc. Baxley, Georgia 31513 P. O. Box 1295 Birmingham, Alabama 35201-1295 Mr. J. B. Beasley, Jr.
Executive Vice President Resident Inspector Southern Nuclear Operating Plant Hatch Company, Inc.
11030 Hatch Parkway N. P. O. Box 1295 Baxley, Georgia 31531 Birmingham, Alabama 35201-1295 Harold Reheis, Director Mr. G. R. Frederick Department of Natural Resources General Manager, Edwin I. Hatch 205 Butler Street, SE., Suite 1252 Nuclear Plant Atlanta, Georgia 30334 Southern Nuclear Operating Company, Inc.
Steven M. Jackson U.S. Highway 1 North Senior Engineer - Power Supply P. O. Box 2010 Municipal Electric Authority Baxley, Georgia 31515 of Georgia 1470 Riveredge Parkway, NW Mr. K. Rosanski Atlanta, Georgia 30328-4684 Resident Manager Oglethorpe Power Corporation Mr. Reece McAlister Edwin I. Hatch Nuclear Plant Executive Secretary P. O. Box 2010 Georgia Public Service Commission Baxley, Georgia 31515 244 Washington St., S. W.
Atlanta, Ga. 30334