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Category:Letter type:NL
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator NL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 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 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-24-0286, 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 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions 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-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 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-24-0201, 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) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0194, 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) NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits 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 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-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 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-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0098, Report on Status of Decommissioning Funding2024-03-28028 March 2024 Report on Status of Decommissioning Funding 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-24-0097, 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 NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 2024-09-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information 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-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 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-24-0087, 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-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 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 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-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit 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, – Units 1 & 2, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology2022-12-21021 December 2022 – Units 1 & 2, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 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-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value 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-21-0925, 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-21-0994, 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-21-0989, 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-21-1017, License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure2021-12-13013 December 2021 License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure 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 NL-20-0275, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2020-05-29029 May 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues 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-19-0331, License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors2019-12-12012 December 2019 License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors 2024-09-04
[Table view] Category:Technical Specification
MONTHYEARNL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information 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 NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 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-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency ML23318A0702023-10-31031 October 2023 Technical Specifications Bases ML23165A2192023-06-13013 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 ML23076A0502023-03-21021 March 2023 Correction of Amendment Nos. 244 and 241 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a License Controlled Document 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-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis 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-21-1017, License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure2021-12-13013 December 2021 License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure 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 ML21313A3262021-10-28028 October 2021 0 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML21313A3272021-10-28028 October 2021 0, Technical Specification Bases 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 ML20125A2122020-04-28028 April 2020 Revisions to Technical Specification Bases Changes NL-19-0331, License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors2019-12-12012 December 2019 License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors 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-19-0771, Risk Informed Technical Specification Information Only Bases Changes2019-06-27027 June 2019 Risk Informed Technical Specification Information Only Bases Changes NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)2019-05-0303 May 2019 Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI) 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 ... ML18312A0772018-10-30030 October 2018 Technical Specifications Bases 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) NL-17-2095, Supplement Submittal of Corrected Technical Specification Definition of Iodine 1-131 for the Ast. TSTF-448 and TSTF-312 Amendment Package2017-12-18018 December 2017 Supplement Submittal of Corrected Technical Specification Definition of Iodine 1-131 for the Ast. TSTF-448 and TSTF-312 Amendment Package 2024-08-16
[Table view] Category:Amendment
MONTHYEARNL-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 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 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 ML23076A0502023-03-21021 March 2023 Correction of Amendment Nos. 244 and 241 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a License Controlled Document 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-23-0020, 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-22-0894, 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 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-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis 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-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-21-1017, License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure2021-12-13013 December 2021 License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure 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-21-0613, 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-21-0444, 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 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-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)2019-05-0303 May 2019 Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI) 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) NL-17-2095, Supplement Submittal of Corrected Technical Specification Definition of Iodine 1-131 for the Ast. TSTF-448 and TSTF-312 Amendment Package2017-12-18018 December 2017 Supplement Submittal of Corrected Technical Specification Definition of Iodine 1-131 for the Ast. TSTF-448 and TSTF-312 Amendment Package 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-16-1246, 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-15-0421, J. M. Farley, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Regarding Generic Letter 2008-01, Managing Gas Accumulation in Accordance with TSTF-523, Revision 2, Using the Consolidated Line Item Improvement P2015-05-12012 May 2015 J. M. Farley, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Regarding Generic Letter 2008-01, Managing Gas Accumulation in Accordance with TSTF-523, Revision 2, Using the Consolidated Line Item Improvement Pro 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-14-0635, License Amendment Request to Revise Technical Specifications Reactor Trip System Instrumentation2014-06-0303 June 2014 License Amendment Request to Revise Technical Specifications Reactor Trip System Instrumentation 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-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-12-0346, Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST)2012-02-20020 February 2012 Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST) NL-11-1057, License Amendment Request for Technical Specification Table 3.3.1-12011-09-0909 September 2011 License Amendment Request for Technical Specification Table 3.3.1-1 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-10-1609, 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 NL-09-1644, Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (SWS)2009-10-0808 October 2009 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (SWS) NL-09-0154, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position2009-03-30030 March 2009 Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position NL-08-1519, Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.82008-10-0808 October 2008 Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.8 NL-08-0535, Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using Consolidated Line Item Improvement Process2008-10-0808 October 2008 Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using Consolidated Line Item Improvement Process ML0818202032008-06-27027 June 2008 Enclosure 2, Markup of Proposed Technical Specifications NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 2, Markup of Proposed Technical Specifications2008-06-27027 June 2008 Vogtle, Units 1 and 2 - Enclosure 2, Markup of Proposed Technical Specifications ML0818202082008-06-27027 June 2008 Enclosure 3, Typed Pages for Technical Specification NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 3, Typed Pages for Technical Specification2008-06-27027 June 2008 Vogtle, Units 1 and 2 - Enclosure 3, Typed Pages for Technical Specification ML0803503492008-02-27027 February 2008 Technical Specifications for License Amendments Regarding Measurement Uncertainty Recapture Power Uprate ML0733801002007-11-30030 November 2007 Transmittal of Vogtle, Units 1 and 2 - License Amendment Request to Technical Specification (TS) Sections TS 5.5.9, Steam Generator (SG) Program and TS 5.6.10, Steam Generator Tube Inspection Report NL-06-0708, Request for License Amendment Related to Technical Specification 5.5.9, Steam Generator (SG) Tube Surveillance Program.2006-07-20020 July 2006 Request for License Amendment Related to Technical Specification 5.5.9, Steam Generator (SG) Tube Surveillance Program. ML0611504462006-04-14014 April 2006 Technical Specifications, Revise TS Section 5.5.6, Pre-Stressed Concrete Containment Tendon Surveillance Program, for Consistency with the Requirements of 10 CFR 50.55a(g)(4) for Components Classified as Code Class CC NL-05-0856, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2005-11-0202 November 2005 Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process 2024-07-25
[Table view] |
Text
Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316
cagayhea@southernco.com
December 22, 2021
Docket Nos.: 50-348 50-424 NL-21-0925 50-364 50-425
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001
Southern Nuclear Operating Company Farley Nuclear Plant Units 1&2 Vogtle Electric Generating Plant Units 1&2 Adoption of TSTF-269-A, Revision 2, Allow Administ rative Means of Position Verification for Locked or Sealed Valves
Ladies and Gentlemen:
Pursuant to 10 CFR 50.90, Southern Nuclear Operatin g Company (SNC) hereby requests a license amendment to the Joseph M. Farley Nuclear P lant (FNP) Unit 1 Renewed Facility Operating License (RFOL) NPF-2 and Unit 2 RFOL NPF-8, and the Vogtle Electric Generating Plant (VEGP) Unit 1 RFOL NPF-68 and Unit 2 RFOL NPF -81. The proposed amendment is consistent with NRC-approved Technical Specificatio n Task Force (TSTF) Traveler 269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves.
The proposed changes modify Technical Specification (TS) 3.6.3, Containment Isolation Valves. Consistent with TSTF-269-A, Notes would b e added to allow isolation devices that are locked, sealed or otherwise secured be verified by use of administrative means.
Approval of the proposed amendment is requested wit hin one year of completion of the NRCs acceptance review. Once approved, the amendment sh all be implemented within 60 days.
In accordance with 10 CFR 50.91, a copy of this app lication is being provided to the designated Alabama and Georgia Officials.
This letter contains no regulatory commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
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ENCLOSURE
Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2
Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves
Evaluation of the Proposed Changes
Enclosure to NL-21-0925 Evaluation of the Proposed Changes
1
SUMMARY
DESCRIPTION
Southern Nuclear Operating Company (SNC) hereby requests a lice nse amendment to the Joseph M. Farley Nuclear Plant (FNP) Unit 1 Renewed Facility Op erating License (RFOL)
NPF-2 and Unit 2 RFOL NPF-8, and the Vogtle Electric Generating Plant (VEGP) Unit 1 RFOL NPF-68 and Unit 2 RFOL NPF-81. The proposed amendment is consi stent with NRC-approved Technical Specification Task Force (TSTF) Traveler 269-A, Revis ion 2, "Allow Administrative Means of Position Verification for Locked or Sealed Valves (Reference 1).
The proposed changes modify Technical Specification (TS) 3.6.3, Containment Isolation Valves. Consistent with TSTF-269-A, Notes would be added to a llow isolation devices that are locked, sealed or otherwise secured be verified by use of administrative means.
2 DETAILED DESCRIPTION
2.1 Description of the Proposed Change The proposed change modifies TS 3.6.3, Containment Isolation V alves. This specification requires penetration flow paths with inoperable isolation devic es be isolated and periodically verified to be isolated. Consistent with TSTF-269-A, Revision 2, notes are proposed to be added to FNP TS 3.6.3, Required Actions A.2, C.2 and D.2, and VEGP TS 3.6.3, Required Actions A.2 and C.2, to allow isolation devices that are locked, sealed, or otherwise secured to be verified using administrative means.
SNC is proposing the following variations from the TS changes described in TSTF-269-A. There are two differences in the Required Action identifiers between TSTF-269-A and the FNP TS and the VEGP TS. TSTF-269-A identifies a change to TS 3.6.3 Require d Action E.2. The equivalent action in the FNP TS is Required Action D.2. The equivalent Required Action in the VEGP TS is C.2. These Required Actions are equivalent, and the identifier differences do not affect the applicability of TSTF-269-A to FNP or VEGP. In addition, the VEGP TS do not contain a Condition equivalent to Condition C in TSTF-269-A. Therefore, that change is not applicable to VEGP.
3 TECHNICAL EVALUATION
3.1 Summary of the Approved Traveler Justification The purpose of the periodic verification that a penetration wit h an inoperable isolation valve continues to be isolated is to detect and correct inadvertent r epositioning of the isolation device.
However, the function of locking, sealing, or securing an isola tion device is to ensure that the device is not inadvertently repositioned. Therefore, it is sufficient to assume that the initial establishment of component status (e.g., isolation valves close d) was performed correctly and subsequent periodic re-verification need only be a verification of the administrative control that ensures that the component remains in the required state. It is unnecessary and undesirable to remove the lock, seal, or other means of securing the component solely to perform an active verification of the required state as it would increase the cha nce of mispositioning due to the frequent manipulation.
The justification presented in approved Traveler TSTF-269-A is applicable to FNP and VEGP.
The Traveler is being adopted by FNP and VEGP with no changes beyond that described above in Section 2.1.
E-1 Enclosure to NL-21-0925 Evaluation of the Proposed Changes
The NRC implemented the approved Traveler, and its contents are reflected in NUREG-1431, Revision 5.
4 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met.
The regulations of Title 10 of the Code of Federal Regulations (10 CFR) 50.36, Technical Specifications, establish the requirements related to the content of the Technical Specifications.
Section 50.36(c)(2) states: When a limiting condition for operation of a nuclea r reactor is not met, the licensee shall shut down the reactor or fo llow any remedial action permitted by the technical specifications until the condition can be met. There is no regulatory requirement that specifies what remedial actions are to be taken whe n a limiting condition for operation is not met. The proposed changes remove an operational res triction not needed for safety. The proposed changes are consistent with the Standard W estinghouse Technical Specifications (i.e., NUREG-1431).
4.2 Precedent Precedent for a plant-specific NRC approval of the changes in TSTF-269-A includes:
Brunswick Steam Electric Plant (Reference 2)
4.3 No Significant Hazard Consideration Determinati on Analysis Southern Nuclear Operating Company (SNC) has evalua ted the proposed changes to the Technical Specifications using the criteria in 10 C FR 50.92 and has determined that the proposed changes do not involve a significant hazar ds consideration.
The proposed amendment is consistent with NRC-appro ved Technical Specification Task Force (TSTF) Traveler 269-A, Revision 2, Allow Administr ative Means of Position Verification for Locked or Sealed Valves. The proposed changes mod ify Farley Nuclear Plant (FNP) and Vogtle Electric Generating Plant (VEGP) Technical S pecification (TS) 3.6.3, Containment Isolation Valves by adding Notes to allow isolatio n devices that are locked, sealed or otherwise secured be verified by use of administrative means.
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 i ncrease in the probability or consequences of an accident previously evaluated ?
Response: No
The proposed change modifies TS 3.6.3, Containment Isolation Valves. This specification requires penetration flow paths with inoperable isolation devices be isolated and periodically verified to be isolated. Consistent with TSTF-269-A, Revision 2, Notes are proposed to be added to FNP T S 3.6.3, Required Actions A.2, C.2 and D.2, and VEGP TS 3.6.3, Required Actions A. 2 and C.2, to allow isolation devices that are locked, sealed, or otherwise secur ed to be verified using administrative means. The proposed change does not affect any plant equipment, test methods, or plant operation, and is not an ini tiator of any analyzed accident
E-2 Enclosure to NL-21-0925 Evaluation of the Proposed Changes
sequence. The inoperable containment penetrations will continue to be isolated, and hence perform their isolation function. Operation in accordance with the proposed Technical Specifications will ensure that all analyzed accidents will continue to be mitigated as previously analyzed.
Therefore, the proposed changes do not involve a significant in crease 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 proposed changes do not involve a physical alteration to th e plant (i.e., no new or different type of equipment will be installed) or a change t o the methods governing normal plant operation. The changes do not alter the assumptions made in the safety analysis.
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 change will not affect operation of plant equipment or the function of any equipment assumed in the accident analysis. Affected contai nment penetrations will continue to be isolated as required by the existing Technical Specifications.
Therefore, the proposed change does not involve a significant r eduction 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 w ill not be endangered by operation in the proposed manner, (2) such activities will be c onducted 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 pub lic.
5 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 propose d change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released of fsite, or (iii) a significant increase in individual or cumulative occupational radiation exp osure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusio n 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 cha nge. Accordingly, the
E-3 Enclosure to NL-21-0925 Evaluation of the Proposed Changes
amendment meets the eligibility cri teria 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 REFERENCES
- 1. Technical Specification Task Force (TSTF)-269-A, Rev 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves, ap proved July 26, 1999.
- 2. Letter from Nuclear Regulatory Commission to Brunswick Steam El ectric Plant, "Issuance Of Amendment Nos. 296 And 324 To Adopt Technical Spec ification Task Force Traveler TSTF-269-A, Revision 2, "Allow Administrative Means Of Position Verification For Locked Or Sealed Valves," dated November 21, 2019
[ML19281A330].
E-4 Southern Nuclear Operating Company Farley Nuclear Plant - Units 1 and 2
Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves
Attachment 1a
Proposed Technical Specification Changes (Marked-up Pages)
Containment Isolation Valves 3.6.3
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
A. ------------NOTE------------- A.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Only applicable to penetration flow path by penetration flow paths use of at least one closed OR with two containment and de-activated isolation valves. automatic valve, closed In accordance with
manual valve, blind the Risk Informed flange, or check valve Completion Time One or more penetration with flow through the Program flow paths with one valve secured.
containment isolation valve inoperable except AND for purge valve penetration leakage not A.2 -------------NOTES-----------
within limit. 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
Farley Units 1 and 2 3.6.3-2 Amendment No. 225 (Unit 1)
Amendment No. 222 (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
C. ------------NOTE------------ C.1 Isolate the affected 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Only applicable to penetration flow path by penetration flow paths use of at least one closed OR with only one and de-activated containment isolation automatic valve, closed In accordance with valve and a closed manual valve, or blind the Risk Informed system. flange. Completion Time
Program AND One or more penetration flow paths with one C.2 -------------NOTES-----------
containment isolation 1. Isolation devices in valve inoperable. high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days penetration flow path is isolated.
Farley Units 1 and 2 3.6.3-4 Amendment No. 225 (Unit 1)
Amendment No. 222 (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
D. One or more penetration D.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> flow paths containing penetration flow path by containment purge use of at least one valves, with penetration closed and de-activated leakage such that the automatic valve, closed sum of the leakage for all manual valve, or blind Type B and C tests is not flange.
within limits.
AND
D.2 ------------NOTES-----------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
AND (continued)
Farley Units 1 and 2 3.6.3-5 Amendment No. 225 (Unit 1)
Amendment No. 222 (Unit 2)
Southern Nuclear Operating Company Vogtle Electric Generating Plant - Units 1 and 2
Adoption of TSTF-269-A, Revision 2, "Allow Administrative Means of Position Verification for Locked or Sealed Valves
Attachment 1b
Proposed Technical Specification Changes (Marked-up Pages)
Containment Isolation Valves 3.6.3
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
A. (continued) A.2 -----------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
(continued)
Vogtle Units 1 and 2 3.6.3-2 Amendment No. 188 (Unit 1)
Amendment No. 171 (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
C. ----------NOTES----------- C.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- 1. Not applicable when penetration flow path by the second use of at least one closed OR containment purge and de-activated valve is intentionally automatic valve, closed In accordance with made inoperable. manual valve, or blind the Risk Informed
- 2. The following Section flange. Completion Time 5.5.22 constraints are Program applicable: parts b, AND c.2, c.3, d, e, f, g, and
- h. C.2 -------------NOTES-----------
1. Isolation devices in high radiation areas One or more penetration may be verified by use flow paths with one or of administrative more containment purge means.
valves not within purge 2. Isolation devices that valve leakage limits. are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
(continued)
Vogtle Units 1 and 2 3.6.3-4 Amendment No. 188 (Unit 1)
Amendment No. 171 (Unit 2)
Southern Nuclear Operating Company Farley Nuclear Plant - Units 1 and 2
Adoption of TSTF-269-A, Revision 2, "Allow Administrative Means of Position Verification for Locked or Sealed Valves
Attachment 2a
Revised Technical Specification Changes
Containment Isolation Valves 3.6.3
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
A. ------------NOTE------------- A.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Only applicable to penetration flow path by penetration flow paths use of at least one closed OR with two containment and de-activated isolation valves. automatic valve, closed In accordance with
manual valve, blind the Risk Informed flange, or check valve Completion Time One or more penetration with flow through the Program flow paths with one valve secured.
containment isolation valve inoperable except AND for purge valve penetration leakage not A.2 -------------NOTES-----------
within limit. 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
Farley Units 1 and 2 3.6.3-2 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
C. ------------NOTE------------ C.1 Isolate the affected 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Only applicable to penetration flow path by penetration flow paths use of at least one closed OR with only one and de-activated containment isolation automatic valve, closed In accordance with valve and a closed manual valve, or blind the Risk Informed system. flange. Completion Time
Program AND One or more penetration flow paths with one C.2 -------------NOTES-----------
containment isolation 1. Isolation devices in valve inoperable. high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days penetration flow path is isolated.
Farley Units 1 and 2 3.6.3-4 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
D. One or more penetration D.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> flow paths containing penetration flow path by containment purge use of at least one valves, with penetration closed and de-activated leakage such that the automatic valve, closed sum of the leakage for all manual valve, or blind Type B and C tests is not flange.
within limits.
AND
D.2 ------------NOTES-----------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
AND (continued)
Farley Units 1 and 2 3.6.3-5 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
D. (continued) D.3 Perform SR 3.6.3.5 for Once per 92 days the penetrations containing resilient seal purge valves closed to comply with Required Action D.1.
E. Required Action and E.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 Time of Condition A, B, AND C, or D not met.
E.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 />
F. One or more penetration F.1 Reduce leakage to within Prior to entering flow paths containing limit. MODE 4 from MODE containment purge 5 if the exiting leakage valves, with penetration is determined during leakage not within the quarterly testing per penetration limits. SR 3.6.3.5.
OR
Prior to entering MODE 4 if excess leakage is determined during MODE 5 per SR 3.6.3.5
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
SR 3.6.3.1 Verify each 48 inch purge valve is seal ed closed, In accordance with except for one purge valve in a penetration flow pa th the Surveillance while in Condition D of this LCO. Frequency Control Program
Farley Units 1 and 2 3.6.3-6 Amendment No. ( Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
SR 3.6.3.2 -----------------------------NOTE------------------ --------------
Valves and blind flanges in high radiation areas may be verified by use of administrative controls.
Verify each containment isolation manual valve and In accordance with blind flange that is located outside containment and the Surveillance not locked, sealed, or otherwise secured and required Frequency Control to be closed during accident conditions is closed, Program except for containment isolation valves that are open under administrative controls.
SR 3.6.3.3 -----------------------------NOTES-------------------------------
- 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2. The blind flange on the fuel transfer canal flange is only required to be verified closed after each draining of the canal.
Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed, except for containment isolation valves that the previous are open under administrative controls. 92 days
SR 3.6.3.4 Verify the isolation time of each automatic power In accordance with operated containment isolation valve in the the INSERVICE INSERVICE TESTING PROGRAM is within limits. TESTING PROGRAM
Farley Units 1 and 2 3.6.3-7 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
SR 3.6.3.5 Perform leakage rate testing for containment In accordance with penetrations containing containment purge valves the Surveillance with resilient seals. Frequency Control Program
AND
Within 92 days after opening the valve
SR 3.6.3.6 Verify each automatic containment isolation valve In accordance with that is not locked, sealed or otherwise secured in the Surveillance position, actuates to the isolation position on an Frequency Control actual or simulated actuation signal. Program
Farley Units 1 and 2 3.6.3-8 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Southern Nuclear Operating Company Vogtle Electric Generating Plant - Units 1 and 2
Adoption of TSTF-269-A, Revision 2, "Allow Administrative Means of Position Verification for Locked or Sealed Valves
Attachment 2b
Revised Technical Specification Changes
Containment Isolation Valves 3.6.3
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
A. (continued) A.2 -----------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
(continued)
Vogtle Units 1 and 2 3.6.3-2 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
B. ----------NOTES----------- B.1 Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
- 1. Not applicable when penetration flow path by the second use of at least one closed OR containment isolation and de-activated valve is intentionally automatic valve, closed In accordance with made inoperable. manual valve, or blind the Risk Informed
- 2. The following Section flange. Completion Time 5.5.22 constraints are Program applicable: parts b, c.2, c.3, d, e, f, g, and h.
One or more penetration flow paths with two containment isolation valves inoperable except for purge valve leakage not within limit.
(continued)
Vogtle Units 1 and 2 3.6.3-3 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
C. ----------NOTES----------- C.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- 1. Not applicable when penetration flow path by the second use of at least one closed OR containment purge and de-activated valve is intentionally automatic valve, closed In accordance with made inoperable. manual valve, or blind the Risk Informed
- 2. The following Section flange. Completion Time 5.5.22 constraints are Program applicable: parts b, AND c.2, c.3, d, e, f, g, and
- h. C.2 -------------NOTES-----------
1. Isolation devices in high radiation areas One or more penetration may be verified by use flow paths with one or of administrative more containment purge means.
valves not within purge 2. Isolation devices that valve leakage limits. are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment
AND
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
(continued)
Vogtle Units 1 and 2 3.6.3-4 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
D. Required Action 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 Time not met. AND
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 />
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
SR 3.6.3.1 Verify each 24 inch purge valve is sealed closed, In accordance with except for one purge valve in a penetration flow path the Surveillance while in Condition D of this LCO. Frequency Control Program
SR 3.6.3.2 Verify each 14 inch purge valve is closed, except In accordance with when the associated penetration(s) is (are) the Surveillance permitted to be open for purge or venting Frequency Control operations and purge system surveillance and Program maintenance testing under administrative control.
SR 3.6.3.3 -----------------------------NOTE--------------------------------
Valves and blind flanges in high radiation areas may be verified by use of administrative controls.
Verify each containment isolation manual valve In accordance with and blind flange that is located outside the Surveillance containment and not locked, sealed, or otherwise Frequency Control secured and required to be closed during accident Program conditions is closed, except for containment isolation valves that are open under administrative controls.
(continued)
Vogtle Units 1 and 2 3.6.3-5 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Containment Isolation Valves 3.6.3
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY
SR 3.6.3.4 -----------------------------NOTES-------------------------------
- 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2. The fuel transfer tube blind flange is only required to be verified closed once after refueling prior to entering MODE 4 from MODE5.
Verify each containment isolation manual valve Prior to entering and blind flange that is located inside containment MODE 4 from and not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within the closed, except for containment isolation valves previous 92 days that are open under administrative controls.
SR 3.6.3.5 Verify the isolation time of each automatic power In accordance operated containment isolation valve is within with the INSERVICE limits. TESTING PROGRAM
SR 3.6.3.6 Perform leakage rate testing for containment In accordance with purge valves with resilient seals. the Surveillance Frequency Control Program
SR 3.6.3.7 Verify each automatic containment isolation valve In accordance with that is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the isolation position on an Frequency Control actual or simulated actuation signal. Program
Vogtle Units 1 and 2 3.6.3-6 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Southern Nuclear Operating Company Farley Nuclear Plant - Units 1 and 2
Adoption of TSTF-269-A, Revision 2, "Allow Administrative Means of Position Verification for Locked or Sealed Valves
Attachment 3a
Proposed Technical Specification Bases Changes (Marked-up Pages )
For Information Only
Containment Isolation Valves B 3.6.3
BASES
ACTIONS A.1 and A.2 (continued)
Required Action A.2 is modified by atwo Notes. Note 1 that applies to isolation devices located in high radiation areas and allows th ese devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherwise secured in positi on and allows these devices to be verified closed by use of administra tive means. Allowing verification by administrative means is consid ered acceptable, since the function of locking, sealing, or securing components is to ensure that these devices are not inadvertentl y repositioned. Therefore, the probability of misalignment of these devices, once they have been verified to be in the proper posit ion, is small.
B.1
With two containment isolation valves in one or more penetrati on flow paths inoperable, the affected penetration flow path must be is olated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a si ngle active failure. Isolation barriers that meet this criterion ar e a closed and de-activated automatic valve, a closed manual valve, and a blind flange. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is consistent with the ACTIO NS of LCO 3.6.1. Alternatively, a Completion Time can be determined using the Risk Informed Completion Time Program (Ref. 6). In the eve nt the affected penetration is isolated in accordance with Required Action B.1, the affected penetration must be verified to be iso lated on a periodic basis per Required Action A.2, which remains in effect. This periodic verification is necessary to assure leak tightness of containment and that penetrations requiring isolation following an accident are isolated. The Completion Time of once per 31 days for verifying each affected penetration flow path is isolated is ap propriate considering the fact that the valves are operated under adminis trative control and the probability of their misalignment is low.
Condition B is modified by two Notes. The first Note states t he Condition is only applicable to penetrations with two containme nt isolation valves. The second Note states RICT entry is not per mitted for this loss of function Condition when the second containment isolation valve is intentionally made inoperable. The RICT pro gram cannot be used for the voluntary removal of systems or componen ts which would result in a loss of safety function. RICT entry is only permitted for situations where a second containment isolation valve is found inoperable or when both isolation valves are simultaneous ly (continued)
Farley Units 1 and 2 B 3.6.3-7 Revision 96 Containment Isolation Valves B 3.6.3
BASES
ACTIONS C.1 and C.2 (continued)
Required Action C.2 is modified by atwo Notes. Note 1 that applies to valves and blind flanges located in high radiation areas and al lows these devices to be verified closed by use of administrative me ans.
Allowing verification by administrative means is considered acc eptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherwise secured in position and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since the function of locking, sealing, or securing components is to ensure that these devices are not inadvertently repositioned. Therefore, the probability of misalignment of these valves, once they have been verified to be in the prop er position, is small.
D.1, D.2, and D.3
In the event one or more penetration flow paths containing containment purge valves, have penetration leakage such that th e sum of the leakage for all Type B and C tests is not within limits, purge valve penetration leakage must be restored such that the overal l Type B and C testing limit is not exceeded, or the affected penetrat ion flow path must be isolated. The method of isolation must be by the use of at least one isolation barrier that cannot be adversely affecte d by a single active failure. Isolation barriers that meet this crite rion are a closed and de-activated automatic valve, closed manual valve, o r blind flange. A purge valve with resilient seals utilized to satisfy Required Action D.1 must have been demonstrated to support the penetrati on meeting the leakage requirements of SR 3.6.3.5. The specified Completion Time is reasonable, considering that one containment purge valve remains closed so that a gross breach of containmen t does not exist.
In accordance with Required Action D.2, this penetration flow path must be verified to be isolated on a periodic basis. The perio dic verification is necessary to ensure that containment penetratio ns required to be isolated following an accident, which are no lon ger capable of being automatically isolated, will be in the isolati on position should an event occur. This Required Action does not require a ny testing or valve manipulation. R ather, it involves verificatio n, through a system walkdown, that those isolation devices outside containme nt capable of being mispositioned are in the correct position. Fo r the isolation devices inside containment, the time period specified as "prior to entering MODE 4 from MODE 5 if not performed within the prev ious
(continued)
Farley Units 1 and 2 B 3.6.3-9 Revision 96 Containment Isolation Valves B 3.6.3
BASES
ACTIONS D.1, D.2, and D.3 (continued)
For the containment penetration containing a containment purge valve with resilient seal that is isolated in accordance with Require d Action D.1, SR 3.6.3.5 must be performed at least once every 92 days. This assures that degradation of the resilient seal is detected and confirms that the leakage rate of the containment purge val ve penetration does not increase during the time the penetration i s isolated. Since more reliance is placed on a single valve whil e in this Condition, it is prudent to perform the SR more often. T herefore, a Frequency of once per 92 days was chosen and has been shown t o be acceptable based on operating experience.
Required Action D.2 is modified by two Notes. Note 1 applies t o isolation devices located in high radiation areas and allows th ese devices to be verified closed by use of administrative means.
Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherw ise secured in position and allows these devices to be verified clo sed by use of administrative means. Allowing verification by administ rative means is considered acceptable, since the function of locking, sealing, or securing components is to ensure that these devices are not inadvertently repositioned.
E.1 and E.2
If the Required Actions and associated Completion Times of Con dition A, B, C, or D are not met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plan t must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 with in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based o n operating experience, to reach the required plant conditions fr om full power conditions in an orderly manner and without challenging p lant systems.
F.1
In the event one or more penetration flow paths containing containment purge valves have penetration leakage which exceeds the individual purge valve penetration leakage limit, purge val ve penetration leakage must be reduced to within the limit prior t o the next time that the unit transitions from MODE 5 to MODE 4. Pro vided that the penetration flow path leakage does not cause the total leakage
(continued)
Farley Units 1 and 2 B 3.6.3-10 Revision 52 Southern Nuclear Operating Company Vogtle Electric Generating Plant - Units 1 and 2
Adoption of TSTF-269-A, Revision 2, "Allow Administrative Means of Position Verification for Locked or Sealed Valves
Attachment 3b
Proposed Technical Specification Bases Changes (Marked-up Pages )
For Information Only
Containment Isolation Valves B 3.6.3
BASES
ACTIONS A.1 and A.2 (continued)
Required Action A.2 is modified by atwo Notes. Note 1 that applies to isolation devices located in high radiation areas and allows th ese valves to be verified closed by use of administrative means. A llowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherwise secured in position and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since the function of locking, sealin g, or securing components is to ensure that these devices are not inadvertently repositioned. Therefore, the probability of misalignment, once they have been verified to be in the proper position, is s mall.
B.1
With two containment isolation valves in one or more penetratio n flow paths inoperable, the affected penetration flow path must be is olated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a si ngle active failure. Isolation barriers that meet this criterion ar e a closed and de-activated automatic valve, a closed manual valve, and a blind flange. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is consistent with the ACTI ONS of LCO 3.6.1. Alternatively, a Completion Time can be determin ed in accordance with the Risk Informed Completion Time Program. In the event the affected penetration is isolated in accordance with Required Action B.1, the affected penetration must be verified to be iso lated on a periodic basis per Required Action A.2, which remains in effe ct.
This periodic verification is necessary to assure that penetrat ions requiring isolation following an accident are isolated. The Co mpletion Time of once per 31 days for verifying each affected penetration flow path is isolated is appropriate considering the fact that the valves are operated under administrative control and the probability of th eir misalignment is low.
CONDITION B is modified by two Notes. The first Note states it is not applicable when the second containment isolation valve is intentionally made inoperable. This Required Action is not intended for voluntary removal of redundant systems or components from service. The Required Action for two containment isolation valv es inoperable is only intended when the second containment isolati on valve is found inoperable and the first valve in the line is al ready
(continued)
Vogtle Units 1 and 2 B 3.6.3-7 REVISION 48 Containment Isolation Valves B 3.6.3
BASES
ACTIONS B.1 (continued)
inoperable, or when both valves are found inoperable at the same time. The second Note indicates the parts of Section 5.5.22, Risk Informed Completion Time Program, which are applicable to this LCO Condition. The Risk Informed Completion Time for this LCO Condition can be no longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Ref. 4).
C.1, C.2, and C.3
In the event one or more containment purge valves in one or more penetration flow paths are not within the purge valve leakage limits, purge valve leakage must be restored to within limits, or the affected penetration flow path must be isolated. The method of isolation must be by the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isola tion barriers that meet this criterion are a closed and de-activated automatic valve, closed manual valve, or blind flange. The spe cified Completion Time is reasonable, considering that one containment purge valve remains closed so that a gross breach of containmen t does not exist.
In accordance with Required Action C.2, this penetration flow path must be verified to be isolated on a periodic basis. The perio dic verification is necessary to ensure that containment penetratio ns required to be isolated following an accident, which are no lon ger capable of being automatically isolated, will be in the isolation position should an event occur. This Required Action does not require any testing or valve manipulation. Rather, it involves verification, through a system walkdown, that those isolation devices outside contain ment capable of being mispositioned are in the correct position. Fo r the isolation devices inside containment, the time period specified as "prior to entering MODE 4 from MODE 5 if not performed within t he previous 92 days" is based on engineering judgment and is considered reasonable in view of the inaccessibility of the iso lation devices and other administrative controls that will ensure that isolation device misalignment is an unlikely possibility.
Required Action C.2 is modified by two Notes. Note 1 applies to isolation devices located in high radiation areas and allows th ese devices to be verified closed by use of administrative means.
Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2
(continued)
Vogtle Units 1 and 2 B 3.6.3-8 REVISION 48 Containment Isolation Valves B 3.6.3
BASES
ACTIONS C.1, C.2, and C.3 (continued)
applies to isolation devices that are locked, sealed, or otherw ise secured in position and allows these devices to be verified clo sed by use of administrative means. Allowing verification by administ rative means is considered acceptable, since the function of locking, sealing, or securing components is to ensure that these devices are not inadvertently repositioned.
Condition C is modified by two Notes. The first Note states it is not applicable when the second containment purge valve is intention ally made inoperable. The Required Action for two containment purge valves inoperable is not intended for voluntary removal of redu ndant systems or components from service. The Required Action is onl y intended if the second containment purge valve is found inopera ble and the first purge valve in the line is already inoperable or if both containment purge valves were found inoperable at the same time.
The second Note indicates the parts of Section 5.5.22, Risk In formed Completion Time Program, which are applicable to this LCO Condition. The Risk Informed Completion Time for this LCO Condition can be no longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Ref. 4).
D.1, and D.2
If the Required Actions and associated Completion Times are not met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowe d Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.3.1 REQUIREMENTS (HV-2626A, HV-2627A, HV-2628A, HV-2629A)
Each 24 inch containment purge valve is required to be verified sealed closed. This Surveillance is designed to ensure that a gross breach of containment is not caused by an inadvertent or spurio us opening of a containment purge valve. Detailed analysis of the purge valves failed to conclusively demonstrate their ability to close during
(continued)
Vogtle Units 1 and 2 B 3.6.3-9 REVISION 48