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MONTHYEARML11237A1542011-08-25025 August 2011 NRR E-mail Capture - Acceptance Review of License Amendment Request for TS 3.5.1.3 Minimum N2 Cover Pressure for Safety Injection Accumulators Project stage: Acceptance Review ML12219A0562012-08-14014 August 2012 Issuance of Amendment Regarding Revising the Minimum Nitrogen Cover Pressure in Technical Specification Requirement 3.5.1.3 Project stage: Approval 2011-08-25
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Category:Letter
MONTHYEARNL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) IR 05000424/20244032024-05-0101 May 2024 Cyber Security Inspection Report 05000424/2024403 and 05000425/2024403 Public ML24120A2832024-04-30030 April 2024 Project Manager Reassignment NL-24-0170, Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report2024-04-25025 April 2024 Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000424/20240012024-04-23023 April 2024 –Integrated Inspection Report 05000424/2024001 and 05000425/2024001 NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report ML24030A9092024-04-10010 April 2024 Issuance of Amendment Nos. 224 and 207, Regarding Revision to Technical Specification 3.4.14 (Reactor Coolant System) Pressure Isolation Valve Leakage Surveillance Requirement 3.4.14.1 ML24079A0062024-04-10010 April 2024 – Proposed Alternative to the Requirements of ASME Code of Operation and Maintenance of Nuclear Power Plants for Pressure Isolation Valve Testing Frequency ML24096A1322024-04-0505 April 2024 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing and Order (EPID L-2024-LLA-0043) - Letter NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0128, License Amendment Request: Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) Testing Frequency2024-04-0404 April 2024 License Amendment Request: Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) Testing Frequency NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0112, Request for Revision to NRC Staff Assessment of Vogtle Site Updated Seismic Hazards2024-03-28028 March 2024 Request for Revision to NRC Staff Assessment of Vogtle Site Updated Seismic Hazards NL-24-0098, Report on Status of Decommissioning Funding2024-03-28028 March 2024 Report on Status of Decommissioning Funding NL-24-0097, Exemption Request: Final Safety Analysis Report Update Schedule2024-03-22022 March 2024 Exemption Request: Final Safety Analysis Report Update Schedule NL-22-0267, License Amendment Request to Revise Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, AC Sources – Operating, Surveillance Requirements2024-03-20020 March 2024 License Amendment Request to Revise Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, AC Sources – Operating, Surveillance Requirements ML24047A0362024-03-0404 March 2024 Response to Hatch and Vogtle FOF Dates Change Request (2025) 2024-09-09
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances ML24176A1632024-07-0101 July 2024 – Regulatory Audit Supplement in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1 Surveillance Requirements EPID L-2024-LLA-0031 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) ML24030A9092024-04-10010 April 2024 Issuance of Amendment Nos. 224 and 207, Regarding Revision to Technical Specification 3.4.14 (Reactor Coolant System) Pressure Isolation Valve Leakage Surveillance Requirement 3.4.14.1 ML24016A1132024-01-30030 January 2024 Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants ML23279A0042024-01-17017 January 2024 Amendment No. 194 to Remove Combined License Appendix C ML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23311A2452023-11-0707 November 2023 Pre-Submittal Meeting on November 7, 2023 - License Amendment Request to Revise the Ultimate Heat Sink Mission Time (Slides) ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing ML23283A0452023-10-0808 October 2023 E-Mail Re Plant Vogtle - Neop Letter Dated October 8, 2023 - Vogtle 3 & 4 - TS 3.7.6 License Amendment Request ML23283A0472023-10-0808 October 2023 Neop Letter Dated October 8, 2023 - Vogtle 3 & 4 - TS 3.7.6 License Amendment Request ML23093A0282023-08-0101 August 2023 Issuance of Amendments Nos. 220 and 203, Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23158A0182023-07-31031 July 2023 Issuance of Amendments Nos. 219 and 202, Regarding Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 ML23158A2082023-07-19019 July 2023 LAR-23-005 U/4 Amd 189 Timing of TS Effectiveness Prior to Initial Criticality Amendment ML23115A1492023-06-15015 June 2023 Issuance of Amendments No. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology ML23150A0802023-05-30030 May 2023 Acceptance Review - Vogtle Units 1 and 2 - Proposed LAR and Relief Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23048A0682023-03-0101 March 2023 Summary of February 13, 2023, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc. Regarding a Proposed License Amendment Request for Vogtle Electric Generating Plant, Units 1 and 2 ML23013A2182023-01-13013 January 2023 Amendment No. 189 to License NPF-91 - Tech Spec Limiting Conditions for Operability Req for Auto Depressurization System Stage 4 Flow Paths Prior to Initial Criticality ML22279A0122022-11-22022 November 2022 Attachment Amendment 187 U4 (LAR-22-003) ML22116A0842022-07-0505 July 2022 Issuance of Amendment Nos. 215 and 198, Regarding Revision to Technical Specification 3.7.2, Main Steam Isolation Valves (Msivs) ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21314A1502021-12-0707 December 2021 Issuance of Amendment Nos. 210 and 193, Regarding Revision to Technical Specification 3.3.5, 4.16 (Kilovolt) Kv (Engineered Safety Feature) Esf Bus Loss of Power (LOP) Instrumentation (EPID L 2021-LLA-0054 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls 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 ML21225A5532021-08-31031 August 2021 August 13,2021, Public Meeting Summary with Southern Nuclear Operating Regarding Proposed LAR to Revise Technical Specifications Related to Reactor Trip System & Engineered Safety Feature Actuation System Instrumentation for Vogtle 1&2 (L-2 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 ML21068A0822021-07-30030 July 2021 Issuance of Amendment Nos. 206 and 189, Regarding a License Amendment Request for a Risk-Informed Resolution to GSI-191 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 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 ML19346E4632020-01-30030 January 2020 Issuance of Amendments Nos. 202 and 185 Regarding End State Revision from Hot Shutdown to Cold Shutdown for Several Technical Specifications ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19312A0542019-11-19019 November 2019 Figure 3.4.16-1 - Reactor Coolant Dose Equivalent I-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific Activity ML19046A0882019-06-24024 June 2019 Issuance of Amendments Request for TS Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line Item 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 ML18304A3942019-01-11011 January 2019 Issuance of Amendment Nos. 198 and 181, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18263A0392018-10-29029 October 2018 Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MG0240 and MG0241; EPID L-2017-LLA-0295) ML18180A0622018-08-10010 August 2018 Issuance of Amendment Nos. 196 and 179 Regarding Application of the Seismic Probabilistic Risk Assessment Into the Previously Approved 10 CFR.50.69. Categorization Process 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) ML18123A5142018-05-31031 May 2018 Amendment 124 - Vogtle Electric Generating Plant Unit 3 COLR and Consistency Changes (LAR-18-006) ML18123A5152018-05-31031 May 2018 Amendment 123 - Vogtle Electric Generating Plant Unit 4 COLR and Consistency Changes (LAR-18-006) ML18075A1022018-03-29029 March 2018 Amendment - Vogtle Electric Generating Plant Unit 4 LAR 17-027 ML18075A1002018-03-29029 March 2018 Amendment - Vogtle Electric Generating Plant Unit 3 LAR 17-027 ML18012A0682018-02-0707 February 2018 Issuance of Amendments Regarding Changes to Surveillance Requirement 3.3.1.3 (CAC Nos. MF9745 and MF9746; EPID L-2017-LLA-0231) ML17214A5462017-10-0202 October 2017 Issuance of Amendments Regarding the Adoption of TSTF-547, Revision 1, Clarification of Rod Position Requirements ML17213A1332017-09-19019 September 2017 Issuance of Amendments Regarding Changes to Technical Specification 3.7.9 to Support Nuclear Service Cooling Water Transfer Pump Repairs ML17198B6332017-09-0505 September 2017 Issuance of Amendments Regarding Technical Specification Requirements for Unavailable Barriers (TSTF-427) 2024-07-23
[Table view] Category:Safety Evaluation
MONTHYEARML24243A0932024-08-30030 August 2024 Non-concurrence Text No Annotations ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) ML24030A9092024-04-10010 April 2024 Issuance of Amendment Nos. 224 and 207, Regarding Revision to Technical Specification 3.4.14 (Reactor Coolant System) Pressure Isolation Valve Leakage Surveillance Requirement 3.4.14.1 ML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23243B0492023-12-19019 December 2023 VEGP Units 3 and 4, Safety Evaluation, LAR-22-002, TS 3.8.3 Inverters Operating, Completion Time Extension - Enclosure 3 ML23335A1232023-12-19019 December 2023 Safety Evaluation Final Integrated Plan ML23310A2922023-12-0707 December 2023 Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007 ML23326A1362023-11-28028 November 2023 Safety Evaluation for Amendment 195 & 192 for TS 3.1.9 More Restrictive Action ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing 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 ML23093A0282023-08-0101 August 2023 Issuance of Amendments Nos. 220 and 203, Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23158A0182023-07-31031 July 2023 Issuance of Amendments Nos. 219 and 202, Regarding Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 ML23159A1022023-07-31031 July 2023 Safety Evaluation - Vogtle Electric Generating Plant, Unit 3 Amendment No. 192 (LAR 23-001) ML23158A2062023-07-19019 July 2023 LAR-23-005 U/4 Amd 189 Timing of TS Effectiveness Prior to Initial Criticality Safety Evaluation ML23115A1492023-06-15015 June 2023 Issuance of Amendments No. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology ML23109A0702023-05-0404 May 2023 Enclosure - Safety Evaluation for VEGP3&4 ISI1-ALT-18 ML23072A2742023-05-0101 May 2023 Enclosure 3 - LAR 22-005 Safety Evaluation ML23095A2962023-04-14014 April 2023 Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds (Vegp 3&4-Isi1- Alt-17) ML23095A2972023-04-14014 April 2023 Enclosure - VEGP 3&4-ISI1-ALT-17 Safety Evaluation ML23037A0912023-02-0808 February 2023 Safety Evaluation - Vogtle Unit 3 Amendment No. 190, Tech Spec Exceptions for In-Containment Refueling Water Storage Tank Operability Prior to Initial Criticality (Exigent Circumstances) ML23013A2202023-01-13013 January 2023 Safety Evaluation for License Amendment No. 189 Tech Spec Limiting Conditions for Operability Reqs for Auto Depressurization System Stage 4 Flow Paths Prior to Initial Criticality ML22284A1332022-11-22022 November 2022 LAR-22-003 U4 Electrical ITAAC Consolidation Amendment Safety Evaluation ML22286A1252022-11-16016 November 2022 Issuance of Amendments Nos. 217 & 200 Regarding Revision to Technical Specifications to Adopt TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes ML22259A1822022-09-22022 September 2022 Request for Proposed Inservice Testing Alternative ALT-VR-01 ML22249A0922022-09-14014 September 2022 Enclosure - Safety Evaluation the Requirements of the ASME Code for Main Turbine System Valve Testing, VEGP 3&4-IST-ALT-02 ML22116A0842022-07-0505 July 2022 Issuance of Amendment Nos. 215 and 198, Regarding Revision to Technical Specification 3.7.2, Main Steam Isolation Valves (Msivs) ML22118A0772022-05-13013 May 2022 Safety Evaluation Regarding Request for Alternative Requirements for Inservice Test Interval Code Edition (VEGP 3&4-IST-ALT-01R2) ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21314A1502021-12-0707 December 2021 Issuance of Amendment Nos. 210 and 193, Regarding Revision to Technical Specification 3.3.5, 4.16 (Kilovolt) Kv (Engineered Safety Feature) Esf Bus Loss of Power (LOP) Instrumentation (EPID L 2021-LLA-0054 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21237A2402021-10-15015 October 2021 Safety Evaluation for Amendment No. LAR-21-001: Clarification of ITAAC Regarding Invessel Components 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 ML21217A0282021-09-17017 September 2021 Safety Evaluation for Vogtle Electric Generating Plant Units 3 and 4 Regarding Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21068A0822021-07-30030 July 2021 Issuance of Amendment Nos. 206 and 189, Regarding a License Amendment Request for a Risk-Informed Resolution to GSI-191 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 ML20268A0702021-07-30030 July 2021 Safety Evaluation - Vogtle GSI-191 LAR ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality ML21090A2472021-04-0909 April 2021 Safety Evaluation by the Office of Nuclear Reactor Regulation Regarding Proposed ASME Code Alternative Requirements for ASME Section XI Examination Coverage of Weldolet Branch Connections ML20352A1552021-01-11011 January 2021 Proposed Relief Request for Alternative VEGP-ISI-ALT-04-04 to the Requirements of the ASME Code ML20314A0162020-12-0707 December 2020 Safety Evaluation Vacuum Relief Valve Technical Specification Changes (LAR 20-005) ML20307A1412020-11-12012 November 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal ML20269A4002020-10-27027 October 2020 Interim Staff Evaluation for Vogtle Electric Generating Plant, Units 3 and 4 Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 ML20247J4642020-10-14014 October 2020 Safety Evaluation Report for Vogtle Electric Generating Plant for Amendments 185/183 (LAR 20-004) ML20237F4952020-09-24024 September 2020 Safety Evaluation for Vogtle Electric Generating Plant Units 3 and 4 Amendment Nos. 184/182 (LAR 20-003) 2024-08-30
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 14, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING REVISING THE MINIMUM NITROGEN COVER PRESSURE IN TECHNICAL SPECIFICATION REQUIREMENT 3.5.1.3 (TAC NOS. ME6759 AND ME6760)
Dear Mr. Ajluni:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 166 to Renewed Facility Operating License NPF-68 and Amendment No. 148 to Renewed Facility Operating License NPF-81 for the Vogtle Electric Generating Plant, Units 1 and 2, respectively.
The amendments consist of changes to the License and Technical Specifications (TSs) in response to your application dated July 26, 2011. The amendments revise TS Surveillance Requirement (SR) 3.5.1.3, "Accumulators," and SR 3.6.2.1 "Containment Air Locks." A copy of the related Safety Evaluation is also enclosed.
A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Sincerely, Patrick G. Boyle, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425
Enclosures:
- 1. Amendment No. 166 to NPF-68 2. Amendment No. 148 to NPF-81 3. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC. GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-424 VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 166 Renewed License No. NPF-68 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility)
Renewed Facility Operating License No. NPF-68 filed by the 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 July 26, 2011 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations set forth in 10 CFR Chapter I; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-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-68 is hereby amended to read as follows: Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 166 , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shaH operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ncy Salgado, Chief lant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-68 and the Technical Specifications Date of Issuance:
August 14, 2012
-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-81 is hereby amended to read as follows: Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 148 , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-'1,.....-,........,,0 ancy Salgado, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-81 and the Technical Spedflcations Date of Issuance:
August 14. 2012
TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Pages Insert Pages License License License No. NPF-68, page 4 License No. NPF-68, page 4 License No. NPF-81, page 3 License No. NPF-81, page 3 TSs TSs 3.5.1-2 3.5.1-2 3.6.2-5 3.6.2-5
-4 Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core pOYier levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein. Technical Specifications and Environmental Protection Plan The Technical contained in Appendix A. as revised through Amendment No. J.tb and the Environmental Protection Plan contained in Appendix B, both oj which are attached hereto, are hereby incorporated into this Southern Nuclear shall operate lhe facility in accordance with the Technical Specifications and the Environmental Protection Plan. Southern Nuclear Operating Company shan be capable of establishing containment hydrogen monitoring within 90 minutes of initiating safely injection following a loss of coolant accident. Deleted Deleted Deleted Deleted Deleted Deleted Mitig,lI,ign Strate m::
Condition The licensee shall develop and maintain strategies for addressing large fires and exploSions and that include the following key areas: Fire fighting response strategy with the following elements: . Pre-defined coordinated fire response strategy and guidance Assessment of mutual aid fire fighting assets Designated staging areas for equipment alid materials Command and control Training of response personnel Operations to mitigate fuel damage considering the following: Protection and use of personnel assets Communications Minimizing fire spread Procedures for implementing integrated lire response strategy Identtncation of readily-available pre-staged equipment Training on integrated fire response strategy Renewed Operating License No. NPF-68 . ArnendmentNo.
166 Georgia Power Company. Oglethorpe Power Corporation.
Municipal Electric Authority of Georgia, and City of Dalton, Georgia. pursuant to the Act and 10 CFR Part 50, to possess but not operate the facility at the designated location in Burke County, Georgia. ;n accordance with the procedures and limitations set forth in this license; Southem Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any lime special nuclear material as reactor fuel,ln accordance with the limitations for storage and amounts required for reactor operation.
as described in the Final Safety Analysis Report. as supplemented and amended; Southem Nuclear, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any lime any byproduct, source and special nuclear material as sealed neutron sources for reactor startup. sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Southem Nuclear, pursuant to the Act and 10 CFR Parts 3D, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to Chemical or physical fonn, for sample analYsis or instrument calibration or associated with radioactive apparatus or components; Southem Nuclear, pursuant to the Act and 10 CFR Parts 30, 40. and 70, to possess, but not separate, such byproduct and special nudear mater"lals as may be produced by the operation of the facility authorized herein. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules. regulatiOns.
and orders of the Commission now or hereafter in effect, and is SUbject to the additional conditions specified or incorporated be:ow, Maximum Power Southem Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the ronditions specified herein. Technical SoecificatiQOs and Environmental Protection Plan The Technical Stecifications contained In Appendix A, as revised through Amendment No: .l4ti and the Environmental Protection Plan contained in Appendix 8, both OT which are attached hereto. are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. The Surveillance Requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment No. 74. The SRs listed belQIN snaIl be Renewed Operating license NPF*R1 Amendment No. 148
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. In accordance with the Surveillance Frequency Control Program SR 3.5.1.2 Verify borated water volume in each accumulator is :2!: 6555 gallons and S; 6909 gallons. In accordance with the Surveillance Frequency Control Program SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is :2!: 626 psig and :S 678 psig. In accordance with the Surveillance Frequency Control Program SR 3.5.1.4 Verify boron concentration in each accumulator is :2!: 1900 ppm and :S 2600 ppm. In accordance with the Surveillance Frequency Control Program For each affected accumulator, once within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of:2!: 67 gallons, that is not the result of addition from the refueling water storage tank SR 3.5.1.5 Verify power is removed from each accumulator isolation valve operator when pressurizer pressure is > 1000 psig. In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.5.1-2 Amendment No.166 (Unit 1) Amendment No. 148 (Unit 2)
3.6.2 Containment
Air Locks SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1
- 1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test. 2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1. Perform required air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program. In accordance with the Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be opened at a time. In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.6.2-5 Amendment No. 166 (Unit 1) Amendment No. 148 (Unit 2)
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 166 TO RENEWED FACILITY OPERATING LICENSE NPF-68 AND AMENDMENT NO. 148 TO RENEWED FACILITY OPERATING LICENSE NPF-81 SOUTHERN NUCLEAR OPERATING COMPANY. INC. VOGTLE ELECTRIC GENERATING PLANT. UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425
1.0 INTRODUCTION
By application dated July 26,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 112160414), Southern Nuclear Operating Company, Inc. (SNC, the licensee), requested changes to the Technical Specifications (TSs) for the Vogtle Electric Generating Plant, Units 1 and 2 (Vogtle1 and 2). The proposed changes would revise TS Surveillance Requirement (SR) 3.5.1.3, "Accumulators," to specify a new minimum indicated nitrogen cover pressure for the Safety Injection accumUlators in Surveillance Requirement (SR) 3.5.1.3. The proposed change comes from the need to account for uncertainty associated with the accumulator pressure indication instrumentation.
The proposed revision to the SR would be: "Verify nitrogen cover pressure in each accumulator is 626 psig [pounds per square inch gauge] and:::. 678 psig." SNC is currently administratively controlling the minimum indicated accumulator pressure to 626 psig. The proposed amendments also include an editorial change to SR 3.6.2.1. The current TS 3.6.2, "Containment Air Locks," SR 3.6.2.1 states, "Perform required air lock leakage rate testing in accordance with the Containment Leakage Rage Testing Program." The proposed change would revise SR 3.6.2.1 to state, "Perform required air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program" changing the word "rage" to "rate," thus correcting a typographical error.
2.0 REGULATORY EVALUATION
The Commission's regulatory requirements related to the contents of TS, set forth in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, require that the TS limiting conditions for operations are consistent with assumed values of the initial conditions in the licensee's safety analyses.
Section 50.36(c)(2)(i) states: "limiting conditions for operation are the lowest functional
-2 capability or performance levels of equipment required for safe operation of the facility.
TSs are required to include items in the following five specific categories related to station operation:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met." NRC Administrative Letter 98-10 covers the discovery of TS that are insufficient to assure plant safety. The discovery of an improper or inadequate TS value or required action is considered a degraded or nonconforming condition as defined in Generic Letter 91-18. ImpOSing administrative controls in response to improper or inadequate TS is considered an acceptable short-term corrective action. The staff expects that, following the imposition of administrative controls, an amendment to the TS, with appropriate justification and schedule, will be submitted in a timely fashion. Once any amendment correcting the TS is approved, the licensee must update the final safety analysis report, as necessary, to comply with 10 CFR 50.71(e).
3.0 TECHNICAL
EVALUATION The functions of the Emergency Core Cooling System accumulators are to supply water to the reactor vessel during the blow-down phase of a loss of coolant accident (LOCA), to provide inventory to help accomplish the refill phase that follows thereafter, and to provide Reactor Coolant System (RCS) makeup for a small break LOCA. The accumulators are pressure vessels partially filled with borated water and pressurized with nitrogen gas. The accumulators are passive components, since no operator or control actions are required in order for them to perform their function.
Internal accumulator tank pressure is sufficient to discharge the accumulator contents to the RCS, if RCS pressure decreases below the accumulator pressure.
The accumulator size, water volume, and nitrogen cover pressure are selected so that three of the four accumulators are sufficient to partially cover the core before significant clad melting or zirconium water reaction can occur following a LOCA. The need to ensure that three accumulators are adequate for this function is consistent with the LOCA assumption that the entire contents of one accumulator will be lost via the RCS pipe break during the blow-down phase of the LOCA. The TS requirements help ensure that the 10 CFR 50.46 acceptance criteria are met following a LOCA. The requirements are: Maximum fuel element cladding temperature is s2200°F Maximum cladding oxidation is s 0.17 times the total cladding thickness before oxidation Maximum hydrogen generation from a zirconium water reaction is sO.01 times the hypothetical amount that would be generated if all of the metal in the cladding cylinders surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react Core is maintained in a coolable geometry.
-The large and small break LOCA analyses are performed at the minimum nitrogen cover pressure, since sensitivity analyses have demonstrated that higher nitrogen cover pressure results in a computed peak clad temperature benefit. The maximum nitrogen cover pressure limit prevents accumulator relief valve actuation, and ultimately preserves accumulator integrity.
SNC revised the instrument uncertainty associated with the accumulator nitrogen cover pressure indication instrumentation.
The uncertainty was increased and necessitated a change in the TS required minimum nitrogen pressure.
The licensee performed an uncertainty calculation reconstitution for the accumulator pressure transmitters and a temperature compensation shift bias of 1.58% was added. This shift bias was added to reflect current methodology and came after discussion with Westinghouse.
Currently, the accumulator pressure assumed in large and small break LOCA analyses is 596.6 psig and has an uncertainty of 20.4 psi. When the 596.6 psig assumed is added to the uncertainty value of 20.4 the current TS value of 617 psig for the minimum indicated accumulator nitrogen cover pressure is reached. The addition of the temperature compensation shift bias of 1.58% caused the new uncertainty calculation of accumulator nitrogen pressure from the indication instruments to the main control board to be 28.8 psi which is 8.4 psi greater than the current value assumed in the TS, making the current TS non-conservative.
The requested TS 3.5.1.3 minimum indicated nitrogen cover pressure is the current large and small break LOCA analyses nitrogen pressure of 596.6 psig plus the revised uncertainty of 28.8 psi to reach 625.4 which the licensee rounded conservatively to 626 psig. The maximum accumulator nitrogen cover pressure is not assumed in safety analysis.
The maximum accumulator nitrogen cover pressure is used to make sure the accumulator relief valve is not actuated.
The setpoint for the maximum accumulator nitrogen cover pressure is 678 psig while the relief valve setpoint is 700 psig. SNC stated that the revised accumulator pressure indication uncertainty will not affect the maximum nitrogen cover pressure based on operating experience that 678 psig setpoint is sufficient to prevent accumulator relief valve actuation.
SNC is currently administratively controlling the minimum indicated accumulator nitrogen cover pressure to psig. The staff has reviewed the proposed amendment to TS SR 3.5.1.3 and found the proposed change to appropriately maintain the current accumulator pressure assumed in design-basis accident (DBA) analyses.
The staff also reviewed the proposed editorial change to SR 3.6.2.1. The current TS 3.6.2, "Containment Air Locks," SR 3.6.2.1 states: "Perform required air lock leakage rate testing in accordance with the Containment Leakage Rage Testing Program." The proposed change would revise SR 3.6.2.1 to state: "Perform required air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program."
-The staff found the change to be editorial and acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's 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 and change surveillance requirements.
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 (76 FR 55131, September 6, 2011). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
In addition, the editorial correction to SR 3.6.2.1 meets the categorical exclusion criteria set forth in 10 CFR 51.229( c)(1 0). 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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's 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. Principal Contributor:
J Miller NRR/DSS/SRXB Date: August 14,2012 August 14, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING REVISING THE MINIMUM NITROGEN COVER PRESSURE IN TECHNICAL SPECIFICATION REQUIREMENT 3.5.1.3 (TAC NOS. ME6759 AND ME6760)
Dear Mr. Ajluni:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 166 to Renewed Facility Operating License NPF-68 and Amendment No. 148 to Renewed Facility Operating License NPF-81 for the Vogtle Electric Generating Plant, Units 1 and 2, respectively.
The amendments consist of changes to the License and Technical Specifications (TSs) in response to your application dated July 26, 2011. The amendments revise TS Surveillance Requirement (SR) 3.5.1.3, "Accumulators," and SR 3.6.2.1 "Containment Air Locks." A copy of the related Safety Evaluation is also enclosed.
A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket Nos. 50-424 and 50-425
Enclosures:
- 1. Amendment No. 166 to NPF-68 2. Amendment No. 148 to NPF-81 3. Safety Evaluation cc w/encrs: Distribution via Listserv DISTRIBUTION:
Public LPL2-1 R/F RidsAcrsAcnw MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource Sincerely, IRA! Patrick G. Boyle, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDssSrxb Resource RidsNrrPMVogtie Resource (hard copy) RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsRgn2MailCenter Resource J. Miller ADAMS Accession No ML 12219A056
- via memo dated OFFICE NRRILPL2-1/PM NRR/LPL2-1/LA NRRlSRXB/BC OGC NLO NRR/LPL2-1/BC NRRILPL2-1/PM NAME PBoyle (RMartin for) SFigueroa SMiranda*
MSpencerwl changes NSalgado (JBoska for) PBoyle (RMartin for) DATE 08/13/12 08/08/12 07/31/2012 08/09/12 08/14/12 08/14/12 OFFICIAL RECORD COpy