Letter Sequence Request |
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EPID:L-2021-LLA-0054, 3 to Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, 10 CFR 50.59 Summary Report and Revised NRC Commitments Report (Approved, Closed) |
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MONTHYEARNL-20-0173, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values2021-03-30030 March 2021 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values Project stage: Request ML21102A2222021-03-30030 March 2021 3 to Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, 10 CFR 50.59 Summary Report and Revised NRC Commitments Report Project stage: Request 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 Project stage: Acceptance Review NL-21-0444, Supplement to License Amendment Request to Revise Technical Specification 3.3.5.2 Allowable Values2021-05-0606 May 2021 Supplement to License Amendment Request to Revise Technical Specification 3.3.5.2 Allowable Values Project stage: Supplement ML21131A2172021-05-11011 May 2021 NRR E-mail Capture - Acceptance Review - Vogtle TS 3.3.5, Loss of Power (LOP) Instrumentation, Surveillance Requirement (SR) 3.3.5.2, Allowable Values LAR (L-2021-LLA-0054) Project stage: Acceptance Review 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 Project stage: Approval 2021-04-19
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Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 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-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 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-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) 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-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 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-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) 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-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 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-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-22-0764, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology2022-12-21021 December 2022 License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology ND-22-0894, License Amendment Request for Technical Specification SR 3.0.3 for Never-Performed Surveillances (LAR-22-005)2022-12-19019 December 2022 License Amendment Request for Technical Specification SR 3.0.3 for Never-Performed Surveillances (LAR-22-005) NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, 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 NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0288, License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2022-06-30030 June 2022 License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-22-0208, License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902022-06-30030 June 2022 License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-21-0989, License Amendment Request to Relocate Augmented Piping Inspection Program Details2021-12-22022 December 2021 License Amendment Request to Relocate Augmented Piping Inspection Program Details NL-21-0994, Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes2021-12-22022 December 2021 Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes NL-21-0925, Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2021-12-22022 December 2021 Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves NL-21-0930, Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-10-21021 October 2021 Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections NL-21-0845, License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2021-09-30030 September 2021 License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements NL-21-0658, Joseph Farley, Units 1 and 2, Vogtle, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for for Steam Generator Tube Inspections2021-09-17017 September 2021 Joseph Farley, Units 1 and 2, Vogtle, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for for Steam Generator Tube Inspections NL-21-0613, Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, .2021-06-30030 June 2021 Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, . NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications2021-06-22022 June 2021 License Amendment Request to Remove Table of Contents from Technical Specifications NL-21-0042, Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System2021-06-0909 June 2021 Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System NL-20-0173, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values2021-03-30030 March 2021 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values NL-21-0065, License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls2021-03-25025 March 2021 License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls NL-20-0949, License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 22020-10-30030 October 2020 License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2 ML20224A4642020-08-11011 August 2020 Southern Nuclear Operating Co, Inc - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML20192A1402020-06-30030 June 2020 Southern Nuclear Operating Co., Inc. - License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ND-20-0093, Supplement to Request for License Amendment: Tornado Missile Protection for Main Steam Vent Stacks and Wall 11 (LAR-19-014S1)2020-02-14014 February 2020 Supplement to Request for License Amendment: Tornado Missile Protection for Main Steam Vent Stacks and Wall 11 (LAR-19-014S1) ND-19-1483, Request for License Amendment: Reconciliation of Environmental Conditions Inputs to Civil Structural Design Licensing Basis (LAR-19-019)2019-12-13013 December 2019 Request for License Amendment: Reconciliation of Environmental Conditions Inputs to Civil Structural Design Licensing Basis (LAR-19-019) NL-19-0963, Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process2019-12-11011 December 2019 Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process NL-19-1063, Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition2019-12-10010 December 2019 Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-19-0635, End State Revision from Hot Shutdown to Cold Shutdown for Several Technical Specifications2019-07-0909 July 2019 End State Revision from Hot Shutdown to Cold Shutdown for Several Technical Specifications NL-18-1302, License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line ...2018-12-19019 December 2018 License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line ... ML18226A0942018-08-0909 August 2018 Edwin I. Hatch, Units 1 and 2; and Vogtle, Units 1 and 2 - License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-shift Staff Tables NL-18-1043, License Amendment Request: Supplement to Request to Incorporate Seismic Probabilistic Risk Assessment Into the Categorization Process2018-08-0606 August 2018 License Amendment Request: Supplement to Request to Incorporate Seismic Probabilistic Risk Assessment Into the Categorization Process ND-18-0417, Supplement to Request for License Amendment and Exemption: Changes to Tier 2 Departure Evaluation Process2018-04-0606 April 2018 Supplement to Request for License Amendment and Exemption: Changes to Tier 2 Departure Evaluation Process ND-18-0199, Supplement to Request for License Amendment and Exemption Regarding Technical Specifications for Reactor Coolant System Vacuum Fill and Inspections, Tests, Analyses, and Acceptance Criteria for Containment Floodup (LAR-17-027S3)2018-02-14014 February 2018 Supplement to Request for License Amendment and Exemption Regarding Technical Specifications for Reactor Coolant System Vacuum Fill and Inspections, Tests, Analyses, and Acceptance Criteria for Containment Floodup (LAR-17-027S3) NL-17-1199, Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-09-12012 September 2017 Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17208B0182017-08-31031 August 2017 Issuance of Amendments Regarding Technical Specification Requirements for Diesel Fuel Oil (TSTF-374) NL-17-1088, Submittal of License Amendment Request, Relocation of the Emergency Operations Facility2017-08-30030 August 2017 Submittal of License Amendment Request, Relocation of the Emergency Operations Facility NL-16-2382, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process2017-06-22022 June 2017 License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process NL-17-1026, Revision to Technical Specifications Pages for Limiting Condition for Operation 3.7.142017-06-0202 June 2017 Revision to Technical Specifications Pages for Limiting Condition for Operation 3.7.14 NL-17-0236, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.1.32017-05-24024 May 2017 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.1.3 NL-17-0058, Request to Revise Technical Specifications LCO 3.7.9 for a Change to Support Nuclear Service Cooling Water Transfer Pump Repairs2017-03-24024 March 2017 Request to Revise Technical Specifications LCO 3.7.9 for a Change to Support Nuclear Service Cooling Water Transfer Pump Repairs NL-16-2631, Exigent Request to Revise Technical Specifications LCO 3.7.9 for a One-Time Change to Support Unit 2 Nuclear Service Cooling Water Transfer Pump Repair2016-12-13013 December 2016 Exigent Request to Revise Technical Specifications LCO 3.7.9 for a One-Time Change to Support Unit 2 Nuclear Service Cooling Water Transfer Pump Repair ML16340A0052016-12-0101 December 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Rev 4, Clarify Use and Application Rules. NL-16-1026, Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2016-11-21021 November 2016 Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements NL-16-2080, Change (TSTF-427) to Add LCO 3.0.1 0, Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2016-11-15015 November 2016 Change (TSTF-427) to Add LCO 3.0.1 0, Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process NL-16-2205, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Improvement Process2016-11-15015 November 2016 License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Improvement Process 2023-08-28
[Table view] Category:Technical Specification
MONTHYEARML23165A2192023-06-13013 June 2023 Enclosure 9: Vogtle Electric Generating Plant, Units 3 and 4, Technical Specifications Bases, Revision 73 NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0020, Emergency License Amendment Request: Technical Specification Limiting Conditions for Operation 3.4.11, 3.4.12, and 3.4.13 Operability Requirements for Automatic Depressurization System Stage 4 Flow Paths Prior to Initial Criticality2023-01-12012 January 2023 Emergency License Amendment Request: Technical Specification Limiting Conditions for Operation 3.4.11, 3.4.12, and 3.4.13 Operability Requirements for Automatic Depressurization System Stage 4 Flow Paths Prior to Initial Criticality ND-22-0881, License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002)2023-01-0303 January 2023 License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002) ND-22-0894, License Amendment Request for Technical Specification SR 3.0.3 for Never-Performed Surveillances (LAR-22-005)2022-12-19019 December 2022 License Amendment Request for Technical Specification SR 3.0.3 for Never-Performed Surveillances (LAR-22-005) ML22307A0072022-11-0202 November 2022 Draft LAR for TS 3.8.3 Inverters Operating Completion Time Extension ML22326A1092022-10-31031 October 2022 Bases for Improved Technical Specifications NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0609, Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2022-09-13013 September 2022 Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-22-0208, License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902022-06-30030 June 2022 License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 ML22179A1482022-06-15015 June 2022 Technical Specifications Bases, Revision 70 NL-21-0925, Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2021-12-22022 December 2021 Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves NL-21-0984, Southern Nuclear Operating Company - Second Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls2021-11-10010 November 2021 Southern Nuclear Operating Company - Second Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls NL-21-0845, License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2021-09-30030 September 2021 License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System NL-21-0613, Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, .2021-06-30030 June 2021 Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, . NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications2021-06-22022 June 2021 License Amendment Request to Remove Table of Contents from Technical Specifications ML21179A0952021-06-15015 June 2021 8 to Technical Specifications Bases, List of Effective Sections NL-21-0444, Supplement to License Amendment Request to Revise Technical Specification 3.3.5.2 Allowable Values2021-05-0606 May 2021 Supplement to License Amendment Request to Revise Technical Specification 3.3.5.2 Allowable Values ML21102A2222021-03-30030 March 2021 3 to Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, 10 CFR 50.59 Summary Report and Revised NRC Commitments Report NL-21-0265, 3 to Updated Final Safety Analysis Report, Bases for Improved Technical Specifications2021-03-30030 March 2021 3 to Updated Final Safety Analysis Report, Bases for Improved Technical Specifications NL-20-0173, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values2021-03-30030 March 2021 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values NL-19-1063, Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition2019-12-10010 December 2019 Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition NL-19-1183, Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown2019-10-17017 October 2019 Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-18-1302, License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line ...2018-12-19019 December 2018 License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line ... ML18226A0942018-08-0909 August 2018 Edwin I. Hatch, Units 1 and 2; and Vogtle, Units 1 and 2 - License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-shift Staff Tables ND-18-0647, Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-Containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017)2018-07-20020 July 2018 Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-Containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017) ND-18-0374, Request for License Amendment: Technical Specification Changes to Support Operability During Mode 5 Vacuum Fill Operations (LAR-18-009)2018-04-13013 April 2018 Request for License Amendment: Technical Specification Changes to Support Operability During Mode 5 Vacuum Fill Operations (LAR-18-009) ND-17-1559, Request for License Amendment: Technical Specification Changes to Support Control Rod Testing in Cold Shutdown with Reactor Coolant Pumps Not in Operation (LAR-17-034)2017-09-22022 September 2017 Request for License Amendment: Technical Specification Changes to Support Control Rod Testing in Cold Shutdown with Reactor Coolant Pumps Not in Operation (LAR-17-034) NL-16-1026, Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2016-11-21021 November 2016 Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements NL-16-2206, Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvement Process2016-11-15015 November 2016 Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvement Process NL-16-2080, Change (TSTF-427) to Add LCO 3.0.1 0, Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2016-11-15015 November 2016 Change (TSTF-427) to Add LCO 3.0.1 0, Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process NL-16-1246, Request to Revise Technical Specifications LCO 3.7.9 for a One-Time Change to Support a Unit 2 Nuclear Service Cooling Water Transfer Pump Refurbishment2016-08-12012 August 2016 Request to Revise Technical Specifications LCO 3.7.9 for a One-Time Change to Support a Unit 2 Nuclear Service Cooling Water Transfer Pump Refurbishment NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.2016-07-28028 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application. NL-16-0686, Response to Request for Additional Information Regarding Adoption of TSTF-432, Rev. 1, Change in Technical Specifications End States (WCAP-16294)2016-05-0909 May 2016 Response to Request for Additional Information Regarding Adoption of TSTF-432, Rev. 1, Change in Technical Specifications End States (WCAP-16294) NL-14-1974, Clarification of Response to Request for Additional Information on License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Rev. 0, Risk Informed Technical Specifications Initiative 4b, Risk-Managed.2014-12-12012 December 2014 Clarification of Response to Request for Additional Information on License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Rev. 0, Risk Informed Technical Specifications Initiative 4b, Risk-Managed. NL-14-0869, Response to Request for Additional Information Regarding Revision to Technical Specification 3.7.14 Completion Time2014-05-30030 May 2014 Response to Request for Additional Information Regarding Revision to Technical Specification 3.7.14 Completion Time NL-13-1727, Response to NRC Request for Additional Information for License Amendment Request to Revise Technical Specification 3.7.9 Ultimate Heat Sink (UHS)2013-08-0707 August 2013 Response to NRC Request for Additional Information for License Amendment Request to Revise Technical Specification 3.7.9 Ultimate Heat Sink (UHS) NL-13-0081, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,Using the Consolidated Line Item Improvement...2013-01-23023 January 2013 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,Using the Consolidated Line Item Improvement... NL-12-1192, Units 1 and 2, Technical Specification Revision Request for TS 3.7.14, Engineered Safety Features (ESF) Room Cooler and Safety-Related Chiller System2012-09-26026 September 2012 Units 1 and 2, Technical Specification Revision Request for TS 3.7.14, Engineered Safety Features (ESF) Room Cooler and Safety-Related Chiller System NL-12-1344, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (Rmts) Guidelines.2012-09-13013 September 2012 License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (Rmts) Guidelines. NL-12-0561, License Amendment Request to Revise Technical Specification Sections, 5.5.9, Steam Generator (SG) Program and 5.6.10, Steam Generator Tube Inspection Report.2012-03-22022 March 2012 License Amendment Request to Revise Technical Specification Sections, 5.5.9, Steam Generator (SG) Program and 5.6.10, Steam Generator Tube Inspection Report. ML1120709912011-07-26026 July 2011 Vogtle, License Amendment Request to Revise the Minimum Nitrogen Cover Pressure Specified in Technical Specification Surveillance Requirement 3.5.1.3 and Make an Administrative Change to Technical Specification Surveillance Requirement 3.6. NL-11-1004, Vogtle, License Amendment Request to Revise the Minimum Nitrogen Cover Pressure Specified in Technical Specification Surveillance Requirement 3.5.1.3 and Make an Administrative Change to Technical Specification Surveillance Requirement 3.2011-07-26026 July 2011 Vogtle, License Amendment Request to Revise the Minimum Nitrogen Cover Pressure Specified in Technical Specification Surveillance Requirement 3.5.1.3 and Make an Administrative Change to Technical Specification Surveillance Requirement 3.6. NL-10-2078, License Amendment Request for Incorporation of Previously NRC Approved Tech Spec Task Force Standard Technical Specification Change Traveler TSTF-361-A, Rev 2, Allow Standby Sdc/Rhr/Dhr Loop to Inoperable to Support Testing.2011-03-14014 March 2011 License Amendment Request for Incorporation of Previously NRC Approved Tech Spec Task Force Standard Technical Specification Change Traveler TSTF-361-A, Rev 2, Allow Standby Sdc/Rhr/Dhr Loop to Inoperable to Support Testing. NL-10-1609, Emergency Technical Specification Revision Request for TS 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety-Related Chiller System2010-08-18018 August 2010 Emergency Technical Specification Revision Request for TS 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety-Related Chiller System 2023-06-13
[Table view] Category:Bases Change
MONTHYEARML23165A2192023-06-13013 June 2023 Enclosure 9: Vogtle Electric Generating Plant, Units 3 and 4, Technical Specifications Bases, Revision 73 NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0020, Emergency License Amendment Request: Technical Specification Limiting Conditions for Operation 3.4.11, 3.4.12, and 3.4.13 Operability Requirements for Automatic Depressurization System Stage 4 Flow Paths Prior to Initial Criticality2023-01-12012 January 2023 Emergency License Amendment Request: Technical Specification Limiting Conditions for Operation 3.4.11, 3.4.12, and 3.4.13 Operability Requirements for Automatic Depressurization System Stage 4 Flow Paths Prior to Initial Criticality ND-22-0881, License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002)2023-01-0303 January 2023 License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002) ML22326A1092022-10-31031 October 2022 Bases for Improved Technical Specifications NL-22-0208, License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902022-06-30030 June 2022 License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 ML22179A1482022-06-15015 June 2022 Technical Specifications Bases, Revision 70 NL-21-0845, License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2021-09-30030 September 2021 License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System ML21179A0952021-06-15015 June 2021 8 to Technical Specifications Bases, List of Effective Sections NL-20-0173, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values2021-03-30030 March 2021 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values NL-21-0265, 3 to Updated Final Safety Analysis Report, Bases for Improved Technical Specifications2021-03-30030 March 2021 3 to Updated Final Safety Analysis Report, Bases for Improved Technical Specifications ML21102A2222021-03-30030 March 2021 3 to Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, 10 CFR 50.59 Summary Report and Revised NRC Commitments Report NL-19-1183, Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown2019-10-17017 October 2019 Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-18-1302, License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line ...2018-12-19019 December 2018 License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line ... ND-18-0374, Request for License Amendment: Technical Specification Changes to Support Operability During Mode 5 Vacuum Fill Operations (LAR-18-009)2018-04-13013 April 2018 Request for License Amendment: Technical Specification Changes to Support Operability During Mode 5 Vacuum Fill Operations (LAR-18-009) ND-17-1559, Request for License Amendment: Technical Specification Changes to Support Control Rod Testing in Cold Shutdown with Reactor Coolant Pumps Not in Operation (LAR-17-034)2017-09-22022 September 2017 Request for License Amendment: Technical Specification Changes to Support Control Rod Testing in Cold Shutdown with Reactor Coolant Pumps Not in Operation (LAR-17-034) NL-16-2080, Change (TSTF-427) to Add LCO 3.0.1 0, Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2016-11-15015 November 2016 Change (TSTF-427) to Add LCO 3.0.1 0, Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process NL-16-2206, Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvement Process2016-11-15015 November 2016 Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvement Process NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.2016-07-28028 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application. NL-16-0686, Response to Request for Additional Information Regarding Adoption of TSTF-432, Rev. 1, Change in Technical Specifications End States (WCAP-16294)2016-05-0909 May 2016 Response to Request for Additional Information Regarding Adoption of TSTF-432, Rev. 1, Change in Technical Specifications End States (WCAP-16294) NL-13-0081, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,Using the Consolidated Line Item Improvement...2013-01-23023 January 2013 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,Using the Consolidated Line Item Improvement... NL-12-1192, Units 1 and 2, Technical Specification Revision Request for TS 3.7.14, Engineered Safety Features (ESF) Room Cooler and Safety-Related Chiller System2012-09-26026 September 2012 Units 1 and 2, Technical Specification Revision Request for TS 3.7.14, Engineered Safety Features (ESF) Room Cooler and Safety-Related Chiller System NL-12-0561, License Amendment Request to Revise Technical Specification Sections, 5.5.9, Steam Generator (SG) Program and 5.6.10, Steam Generator Tube Inspection Report.2012-03-22022 March 2012 License Amendment Request to Revise Technical Specification Sections, 5.5.9, Steam Generator (SG) Program and 5.6.10, Steam Generator Tube Inspection Report. NL-10-2078, License Amendment Request for Incorporation of Previously NRC Approved Tech Spec Task Force Standard Technical Specification Change Traveler TSTF-361-A, Rev 2, Allow Standby Sdc/Rhr/Dhr Loop to Inoperable to Support Testing.2011-03-14014 March 2011 License Amendment Request for Incorporation of Previously NRC Approved Tech Spec Task Force Standard Technical Specification Change Traveler TSTF-361-A, Rev 2, Allow Standby Sdc/Rhr/Dhr Loop to Inoperable to Support Testing. NL-09-1431, License Amendment Request for Technical Specification Table 3.3.1-12010-02-0202 February 2010 License Amendment Request for Technical Specification Table 3.3.1-1 NL-06-0266, Request for Technical Specification Amendment Re Containment Tendon Surveillance Program2006-03-29029 March 2006 Request for Technical Specification Amendment Re Containment Tendon Surveillance Program NL-04-2205, Changes to Technical Specification Bases2004-11-10010 November 2004 Changes to Technical Specification Bases NL-04-0564, Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors2004-05-21021 May 2004 Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors NL-03-1365, Revision to Bases2003-06-24024 June 2003 Revision to Bases NL-03-1388, Revision to Technical Requirements Manual2003-06-24024 June 2003 Revision to Technical Requirements Manual NL-03-1140, Changes to Technical Specification Bases2003-06-11011 June 2003 Changes to Technical Specification Bases 2023-06-13
[Table view] |
Text
Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316 cagayhea@southernco.com March 30, 2021 NL-20-0173 10 CFR 50.90 Docket Nos.: 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values Ladies and Gentlemen:
Pursuant to the provisions Section 50.90 of Title 10 Code of Federal Regulations (CFR),
Southern Nuclear operating Company (SNC) hereby requests a license amendment to Vogtle Electric Generating Plant (VEGP) Unit 1 renewed operating license NFP-68 and Unit 2 renewed operating license NFP-81. The proposed amendment revises Technical Specification (TS) 3.3.5, Loss of Power (LOP) Instrumentation, Surveillance Requirement (SR) 3.3.5.2 Allowable Values. The current Allowable Values listed in SR 3.3.5.2 are the same as the Analytical Limits for their respective trip functions. SNC proposes to change the values in SR 3.3.5.2 to Allowable Values, ensuring an appropriately conservative trip setpoint.
Using Analytical Limits as Allowable Values is not consistent with the standard technical specifications (NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 4). This creates the possibility that the trip setpoints will be insufficient to perform their required trip function. Therefore, in accordance with the guidance in NRC Regulatory Guide 1.239, Licensee Actions to Address Non-Conservative Technical Specifications, this license amendment request is required to resolve the non-conservative TS and is not a voluntary request to change the VEGP licensing basis. Currently, plant operations are administratively controlled as described in Regulatory Guide 1.239.
SNC requests approval of the proposed amendment by April 1, 2022. The proposed changes would be implemented within 60 days after issuance of the amendments.
In accordance with 10 CFR 50.91, a copy of this application is being provided to the designated Georgia Official.
U. S. Nuclear Regulatory Commission NL-21-0173 Page 2 This letter contains no regulatory commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the
___ day of March 2021.
Respectfully submitted, C. A. Gayheart Director, Regulatory Affairs Southern Nuclear Operating Company CAG/kgl/cg
Enclosure:
Basis for Proposed Changes Attachments: 1. Proposed Technical Specification Changes (Marked-up Pages)
- 2. Revised Technical Specification Pages (Clean Typed)
- 3. Proposed Technical Specification Bases Changes (Marked-up Pages for Information Only) cc: Regional Administrator, Region ll NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector - Vogtle 1 & 2 State of Georgia Environmental Protection Division RType: CVC7000
ENCLOSURE Vogtle Electric Generating Plant - Units 1 and 2 Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values Basis for Proposed Changes
Basis for Proposed Changes 1.0
SUMMARY
DESCRIPTION In accordance with 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, Southern Nuclear Operating Company (SNC) requests an amendment to Renewed Facility Operating Licenses NFP-68 and NFP-81 for Vogtle Electric Generating Plant (VEGP) Units 1 and 2, respectively. The proposed amendment revises Technical Specification (TS) 3.3.5, Loss of Power (LOP) Instrumentation, Surveillance Requirement (SR) 3.3.5.2 Allowable Values. The current values listed in SR 3.3.5.2 are the same as the Analytical Limits for their respective trip functions. SNC proposes to change these values to Allowable Values, ensuring an appropriately conservative trip setpoint.
2.0 DETAILED DESCRIPTION 2.1 System Design and Operation The Class 1E AC power system is divided into two independent divisions to provide AC power to the two divisions of engineered safety features (ESF) loads. The standby power source for each ESF bus is its associated emergency diesel generator set. Each 4.16-kV Class 1E bus is equipped with undervoltage relays (located at the sequencer for each Class 1E train) for diesel generator start initiation and undervoltage annunciation.
Upon recognition of a loss of, or degraded voltage on, a 4.16-kV Class 1E bus, a logic signal is initiated. Two voltage sensing schemes for each Class 1E 4.16-kV bus are employed to initiate the logic signal. One scheme will recognize a loss of voltage, and the other will recognize degraded voltage conditions. Each scheme is provided voltage signals through four potential transformers located on each bus.
Logic is provided to allow load shedding and tripping of the incoming breaker on two-out-of-four undervoltage logic signals. These devices are set to operate with a time delay of 0.8 s at a minimum of 71% of nominal voltage which is below the minimum expected voltage during diesel generator sequencing. The undervoltage sensing device design meets the applicable requirements of IEEE 279.
Additional undervoltage logic circuits are provided for each bus to recognize degraded voltage conditions. These circuits are set to operate at a minimum of 89.6% of nominal voltage with a maximum time delay of 20 s. This setpoint is above the minimum motor starting voltage during normal operation; however, the time delay has been selected to prevent unwanted tripping and undervoltage induced damage to the safety-related loads. Load shedding and tripping of the incoming breaker is provided by two-out-of-four undervoltage logic.
The Loss of Voltage and Degraded Voltage instrument Functions provide signals to their respective sequencer to ensure an adequate ESF bus voltage is maintained and provide an anticipatory automatic start of the auxiliary feedwater pumps. A two-out-of-four logic combination for Loss of Voltage or Degraded Voltage on an ESF bus will initiate sequencer circuits to start the diesel generator, shed bus loads, and sequence loading of the diesel generator if required. The two-out-of-four logic on one ESF bus will also initiate sequencer circuits to start the motor-driven auxiliary feedwater pump associated with that bus.
The LOP DG start instrumentation is required for the systems to function in any accident with a loss of offsite power.
E-1
Basis for Proposed Changes SR 3.3.5.2 is the performance of a channel calibration. The Nominal Trip Setpoint considers factors that may affect channel performance such as rack drift, etc. Therefore, the Nominal Trip Setpoint (within the calibration tolerance) is the expected value for the channel calibration.
Therefore, a channel with an actual Trip Setpoint value that is conservative with respect to the Allowable Value is considered Operable; but the channel should be reset to the Nominal Trip Setpoint value (within the calibration tolerance) to allow for factors which may affect channel performance (such as rack drift) prior to the next surveillance.
2.2 Reason for the Proposed Change 10 CFR 50.36 states that the TSs will include items in the categories of safety limits, limiting safety system settings (LSSS), and limiting control settings. Thus, the LSSS may not be maintained in plant procedures. Rather, the LSSS must be specified as a TS-defined limit in order to satisfy the requirements of 10 CFR 50.36. For the Standard Technical Specifications, the NRC staff designated the Allowable Value as the LSSS.
In association with the trip setpoint and limiting conditions for operation (LCOs), the LSSS establishes the threshold for protective system action to prevent acceptable limits being exceeded during design basis accidents. The LSSS therefore ensures that automatic protective action will correct the abnormal situation before a safety limit is exceeded. The Allowable Value is the limiting value that the trip setpoint can have when tested periodically, beyond which the instrument channel is considered inoperable and corrective action must be taken in accordance with the TSs. The LSSS should be developed in accordance with the setpoint methodology used in the licensing basis, with the LSSS listed in the TS.
Therefore, using Analytical Limits as Allowable Values conflicts with the Standard Technical Specifications and creates the possibility that the trip setpoints will be insufficient to perform their required trip function. In accordance with the guidance in NRC Regulatory Guide 1.239, Licensee Actions to Address Non-Conservative Technical Specifications, (Reference 1), this license amendment request is required to resolve non-conservative TS and is not a voluntary request to change the VEGP licensing basis. Currently, plant operations are administratively controlled as described in Regulatory Guide 1.239.
2.3 Description of the Proposed Change The loss of voltage and degraded voltage limits for the LOP channel calibration performed by SR 3.3.5.2 are below. A channel with an actual Trip Setpoint value that is conservative with respect to the Allowable Value is considered Operable Current SR 3.3.5.2 A. Loss of voltage Allowable Value > 2912 V with a time delay of < 0.8 second.
B. Degraded voltage Allowable Value > 3683 V with a time delay of < 20 seconds.
SNC proposes to change the Allowable Value for each of the functions in SR 3.3.5.2 as shown below. The Allowable Values for the loss of voltage and the degraded voltage setpoints are calculated in accordance with the VEGP Setpoint Program and are substituted for the existing values in SR 3.3.5.2. Note that the time delay does not change in either function.
Proposed SR 3.3.5.2 A. Loss of voltage Allowable Value > 2958.2 V with a time delay of < 0.8 second.
B. Degraded voltage Allowable Value > 3729.2 V with a time delay of < 20 seconds.
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Basis for Proposed Changes The current SR for channel calibration of the loss of voltage and the degraded voltage Allowable Value limits are equivalent to the Analytical Limits for loss of voltage and degraded voltage, and should be more conservative than the Analytical Limits.
3.0 TECHNICAL EVALUATION
Setpoint calculations establish a Nominal Trip Setpoint based on the Analytical Limit of the Safety Analysis to ensure that trips or protective actions will occur prior to exceeding the process parameter value assumed by the Safety Analysis calculations. These setpoint calculations also calculate an allowed limit of expected change (i.e., the as-found tolerance) between performances of the surveillance test for assessing the value of the setpoint setting.
The least conservative as-found instrument setting value that a channel can have during calibration without requiring performing a TS remedial action is the setpoint Allowable Value.
Discovering an instrument setting to be less conservative than the Allowable Value indicates that there may not be sufficient margin between the setting and the Analytical Limit. TS channel calibrations, channel operational tests, and trip actuation operational tests (with setpoint verification) are performed to verify channels are operating within the assumptions of the setpoint methodology calculated Nominal Trip Setpoint and that channel settings have not exceeded the TS Allowable Values. When the measured as-found setpoint is non-conservative with respect to the Allowable Value, the channel is inoperable and the actions identified in the TS must be taken. The Allowable Values and Nominal Trip Setpoints are included in the VEGP TSs. The Allowable Values indicate the least conservative value that the as-found trip point may have during testing for the channel to be Operable. The Allowable Values listed in the TS satisfy the 10 CFR 50.36 requirements that the LSSS be in the TSs. Additionally, to ensure proper use of the Allowable Value, field setting, and Nominal Trip Setpoint, the methodology for calculating the as-left and as-found tolerances are specified in plant specific setpoint methodology.
SNC has performed an analysis to determine the Allowable Value setpoint for SR 3.3.5.2 using the plant specific setpoint methodology. This methodology was submitted to the NRC (Reference 2) and reviewed by the NRC (Reference 3). The uncertainty methodology is based on the square root of the sum of the square method (SRSS).
The Allowable Value is established by considering the terms associated with rack effects only and applies only to TS reactor protection or ESF actuation functions, which include the diesel generator start functions. The Allowable Value is performance based and serves as an operability limit for the purpose of the Channel Operational Tests. The Allowable Value allows for deviation of the "as found" setting from the Nominal Trip Setpoint during calibration. The magnitude of the Allowable Value accounts for a two-sided rack calibration accuracy (RCA) and rack drift from the most conservative allowed "as left" setting during calibration. A bistable trip setpoint found non-conservative with respect to the Allowable Value requires appropriate action by plant operating personnel.
The Allowable Value is determined by adding (or subtracting) the RCA of the device tested during the Channel Operational Test to the Nominal Trip Setpoint in the non-conservative direction (i.e., toward or closer to the Safety Analysis Limit) for the application.
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Basis for Proposed Changes The Nominal Trip Setpoint was previously calculated and is contained in SR 3.3.5.2. The Nominal Trip Setpoint is not being changed by this request. The calculation for the Allowable Value is shown below using the Nominal Trip Setpoint values from the TS.
TS Allowable Value for Loss of Voltage > [Nominal Trip Setpoint - (RCA X span voltagepri]
> [2975 VAC - [0.0032 x 5250 VAC)]
> 2958.2 VAC TS Allowable Value for Degraded Voltage > [Nominal Trip Setpoint - (RCA X span voltagepri]
> [3746 VAC - [0.0032 x 5250 VAC)]
> 3729.2 VAC The RCA is the Combined Rack Calibration Accuracy. This is based on the accuracy of the modules that make up the rack.
The voltage to current (E/I) module and the analog to digital (A/D) module provide the uncertainties that are used to calculate the RCA. The Square Root Sum of the Squares method was used to determine the RCA. This is acceptable because the E/I module and A/D module were supplied from separate vendors and are statistically independent. The percent uncertainty for the rack calibration is calculated as shown below.
RCA = [E/I module2 % + A/D module2 % + bistable2 %]1/2 Where:
E/I module = 0.25 - supplied by the module vendor, Dataforth A/D module = 0.20 - supplied by the module vendor, ABB Bistable = 0 - since the number of software bits utilized to implement its setpoints is such that its error is negligible compared to the rest of the channel Therefore, RCA = [0.252% + 0.202% + 0%]1/2 = 0.32%
The Allowable Values calculated above are requested to be incorporated in the TS in place of the current Allowable Value.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria Criterion 13, "Instrumentation and Control," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities,"
requires, among other things, that instrumentation be provided to monitor variables and systems and that controls be provided to maintain these variables and systems within prescribed operating ranges. Instrumentation and controls are provided to monitor and control neutron flux, control rod position, fluid temperatures, pressures, flows, and levels, as necessary, to assure that adequate plant safety can be maintained. Instrumentation is provided in the reactor coolant system, steam and power conversion system, containment, engineered safety features systems, radioactive waste management systems, and other auxiliary systems.
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Basis for Proposed Changes Criterion 20, "Protection System Functions," of Appendix A to 10 CFR Part 50 requires, among other things, that the protection system be designed to initiate operation of appropriate systems to ensure that specified acceptable fuel design limits are not exceeded. A fully automatic protection system with appropriate redundant channels is provided to cope with transient events where insufficient time is available for manual corrective action. The ESF actuation system automatically initiates emergency core cooling and other safety functions by sensing accident conditions, using redundant analog channels measuring diverse variables.
Paragraph (c)(1)(ii)(A) of § 50.36, "Technical Specifications," of 10 CFR Part 50 requires, in part, that, where a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded. The safety analysis establishes an Analytical Limit in terms of a measured or calculated variable and a specific time after that value is reached to begin protective action. Satisfying these two constraints will ensure that the safety limit in 10 CFR 50.36 will not be exceeded during anticipated operational occurrences and design-basis events. The purpose of an LSSS is to assure that protective action is initiated before the process conditions reach the Analytical Limit, thereby limiting the consequences of a design-basis event to those predicted by the safety analyses. The LSSS is derived from the Analytical Limit in a manner determined by the setpoint calculation methodology. The LSSS may be the allowable value.
4.2 Precedent No identical precedent was identified.
4.3 No Significant Hazard Consideration Determination Analysis Southern Nuclear Operating Company (SNC) has evaluated the proposed changes to the Technical Specifications (TS) using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration.
The proposed changes revise TS 3.3.5, Loss of Power (LOP) Instrumentation, Surveillance Requirement (SR) 3.3.5.2 Allowable Values by replacing the existing Allowable Values for the loss of voltage and degraded voltage setpoints in SR 3.3.5.2. The values are revised to provide appropriately conservative setpoints to ensure that the affected equipment will perform its safety function as designed.
As required by 10 CFR 50.91(a), the SNC analysis of the issue of no significant hazards consideration is presented below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change to the LOP functions allow the protection scheme to function as originally designed. The proposed change involves a change to the Allowable Values stated in TS SR 3.3.5.2. The proposed change does not affect the probability or consequences of any accident. Analysis was performed to determine appropriately conservative Allowable Values for the loss of voltage function and the degraded voltage function. Use of the calculated Allowable Values ensures that automatic protective action will correct the E-5
Basis for Proposed Changes abnormal situation before a safety limit is exceeded. Therefore, the diesel generators started by these loss of power functions will perform their design basis function should a loss-of-offsite power or degraded offsite power event occur with or without a concurrent accident.
The proposed changes do not adversely affect accident initiators or precursors, and do not alter the design assumptions, conditions, or configuration of the plant or the manner in which the plant is operated or maintained. The proposed changes ensure that the 4.16kV distribution system remains connected to the offsite power system when adequate offsite voltage is available.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation.
The change does not alter assumptions made in the safety analysis but ensures that the diesel generator operates as assumed in the accident analysis. The proposed change is consistent with the safety analysis assumptions. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed changes to the loss of voltage and degraded voltage Allowable Values continue to provide margin for the protection of equipment from loss of power and degraded voltage conditions. During an actual loss of power or degraded voltage condition, the revised Allowable Values ensure that automatic protective action will correct the abnormal situation before a safety limit is exceeded. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
4.4 Conclusion In conclusion, based on the considerations discussed above, SNC concludes: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, and would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in E-6
Basis for Proposed Changes the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change. Accordingly, the amendment meets 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 amendment.
6.0 REFERENCES
- 1. NRC Regulatory Guide 1.239, Licensee Actions to Address Non-Conservative Technical Specifications, November 2020
- 2. Letter from SNC to NRC, dated August 12, 2011, NRC Request for Additional Information for License Amendment Request for Steam Generator Water Level High-High (P-14) Setpoint Change (ML11228A119)
- 3. Letter from NRC to SNC, dated February 27, 2012, Issuance of Amendments Regarding Steam Generator Water Level High-High Technical Specification, Table 3.3.1-1 and Table 3.3.2-1 Setpoint Changes (ML12033A126)
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Vogtle Electric Generating Plant - Units 1 and 2 Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values Attachment 1 Proposed Technical Specification Changes (Marked-up Pages)
LOP Instrumentation 3.3.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Actions and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Times not met in MODES AND 1, 2, 3, or 4.
D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. Required Action and E.1 Enter applicable Immediately associated Completion Condition(s) and Time not met when the Required Action(s) for the associated DG is associated DG made required OPERABLE by inoperable by LOP DG LCO 3.8.2. start instrumentation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2 Perform CHANNEL CALIBRATION with Nominal Trip In accordance with Setpoint and Allowable Value as follows: the Surveillance Frequency Control A. Loss of voltage Allowable Value 2912 2958.2 Program V with a time delay of 0.8 second.
Loss of voltage Nominal Trip Setpoint 2975 V with a time delay of 0.8 second.
B. Degraded voltage Allowable Value 3683 3729.2 V with a time delay of 20 seconds.
Degraded voltage Nominal Trip Setpoint 3746 V with a time delay of 20 seconds.
(continued)
Vogtle Units 1 and 2 3.3.5-2 Amendment No. 158 (Unit 1)
Amendment No. 140 (Unit 2)
Vogtle Electric Generating Plant - Units 1 and 2 Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values Attachment 2 Revised Technical Specification Pages
LOP Instrumentation 3.3.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Actions and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Times not met in MODES AND 1, 2, 3, or 4.
D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. Required Action and E.1 Enter applicable Immediately associated Completion Condition(s) and Time not met when the Required Action(s) for the associated DG is associated DG made required OPERABLE by inoperable by LOP DG LCO 3.8.2. start instrumentation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2 Perform CHANNEL CALIBRATION with Nominal Trip In accordance with Setpoint and Allowable Value as follows: the Surveillance Frequency Control A. Loss of voltage Allowable Value 2958.2 V Program with a time delay of 0.8 second.
Loss of voltage Nominal Trip Setpoint 2975 V with a time delay of 0.8 second.
B. Degraded voltage Allowable Value 3729.2 V with a time delay of 20 seconds.
Degraded voltage Nominal Trip Setpoint 3746 V with a time delay of 20 seconds.
(continued)
Vogtle Units 1 and 2 3.3.5-2 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Vogtle Electric Generating Plant - Units 1 and 2 Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values Attachment 3 Proposed Technical Specification Bases Changes (Mark-Up) for Information Only
LOP DG Start Instrumentation B 3.3.5 BASES BACKGROUND Trip Setpoints and Allowable Values (continued)
The Trip Setpoints used in the bistables are based on the analytical limits used in the load flow calculations for each Unit. presented in FSAR, Chapter 15 (Ref. 2). These analytical limits have been incorporated into SR 3.3.5.2 as the Allowable Values. The selection of the Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account.
The Allowable Values (AV) allow for deviation of the as found setting from the Nominal Trip Setpoint during testing, and serves as an operability limit for the purpose of the Channel Operational Test (COT). The magnitude of the AV is determined using specified allowances for rack calibration accuracy and rack drift.
APPLICABLE The LOP DG start instrumentation is required for the ESF SAFETY ANALYSES Systems to function in any accident with a loss of offsite power. Its design basis is that of the ESFAS.
(continued)
Vogtle Units 1 and 2 B 3.3.5-2 Rev. 1-3/00
LOP DG Start Instrumentation B 3.3.5 BASES ACTIONS E.1 (continued) required to be entered immediately. The actions of this LCO provide for adequate compensatory actions to support unit safety.
SURVEILLANCE SR 3.3.5.1 REQUIREMENTS SR 3.3.5.1 is the performance of a COT. A COT is performed on each required channel to ensure the entire channel will perform the intended Function. There is a plant specific program which verifies that the instrument channel functions as required by verifying the as-left and as-found setting are consistent with those established by the setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.3.5.2 SR 3.3.5.2 is the performance of a CHANNEL CALIBRATION. The Nominal Trip Setpoint considers factors that may affect channel performance such as rack drift, etc. Therefore, the Nominal Trip Setpoint (within the calibration tolerance) is the expected value for the CHANNEL CALIBRATION. However, the Allowable Value is the value that was used for the loss of voltage and degraded grid studies.
Therefore, aA channel with an actual Trip Setpoint value that is conservative with respect to the Allowable Value is considered OPERABLE; but the channel should be reset to the Nominal Trip Setpoint value (within the calibration tolerance) to allow for factors which may affect channel performance (such as rack drift) prior to the next surveillance.
The setpoints, as well as the response to a loss of voltage and a degraded voltage test, shall include a single point verification that the trip occurs within the required time delay.
CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.
There is a plant specific program which verifies that the instrument channel functions as required by verifying the as-left and as-found setting are consistent with those established by the setpoint methodology.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
Vogtle Units 1 and 2 B 3.3.5-8 REVISION 26