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Category:Letter type:NL
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-24-0349, 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-24-0340, 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-24-0261, 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-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel 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-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift 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-24-0064, 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-24-0137, 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-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel 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-24-0115, 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-24-0092, 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 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0828, Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift2023-11-30030 November 2023 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit 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-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal 2024-09-04
[Table view] Category:License-Application for (Amend/Renewal/New) for DKT 30
[Table view] Category:40
MONTHYEARNL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-21-0307, Report on Status of Decommissioning Funding2021-03-31031 March 2021 Report on Status of Decommissioning Funding NL-17-0429, ISFSI Decommissioning Funding Plan Triennial Update2017-03-30030 March 2017 ISFSI Decommissioning Funding Plan Triennial Update NL-15-0574, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))2015-03-26026 March 2015 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1)) NL-14-0290, Units 1 & 2 and ISFSI - Decommissioning Funding Plan2014-03-31031 March 2014 Units 1 & 2 and ISFSI - Decommissioning Funding Plan NL-13-0675, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))2013-03-29029 March 2013 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1)) 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 NL-11-1357, Response to Request for Additional Information - Decommission Funding Status Report2011-07-15015 July 2011 Response to Request for Additional Information - Decommission Funding Status Report NL-11-0450, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1)2011-03-29029 March 2011 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1) ML0424000832004-08-26026 August 2004 FRN-Notice of Consideration of Issuance of Amendments NL-03-1511, Joseph A. Farley, Amendment Request to Revise Technical Specifications Control Room Emergency Filtration/Pressurization System and Penetration Room Filtration System, Revision 22003-07-16016 July 2003 Joseph A. Farley, Amendment Request to Revise Technical Specifications Control Room Emergency Filtration/Pressurization System and Penetration Room Filtration System, Revision 2 2023-03-29
[Table view] Category:70
MONTHYEARNL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-21-0307, Report on Status of Decommissioning Funding2021-03-31031 March 2021 Report on Status of Decommissioning Funding NL-17-0429, ISFSI Decommissioning Funding Plan Triennial Update2017-03-30030 March 2017 ISFSI Decommissioning Funding Plan Triennial Update NL-15-0574, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))2015-03-26026 March 2015 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1)) NL-14-0290, Units 1 & 2 and ISFSI - Decommissioning Funding Plan2014-03-31031 March 2014 Units 1 & 2 and ISFSI - Decommissioning Funding Plan NL-13-0675, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))2013-03-29029 March 2013 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1)) 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 NL-11-1357, Response to Request for Additional Information - Decommission Funding Status Report2011-07-15015 July 2011 Response to Request for Additional Information - Decommission Funding Status Report NL-11-0450, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1)2011-03-29029 March 2011 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1) ML0424000832004-08-26026 August 2004 FRN-Notice of Consideration of Issuance of Amendments NL-03-1511, Joseph A. Farley, Amendment Request to Revise Technical Specifications Control Room Emergency Filtration/Pressurization System and Penetration Room Filtration System, Revision 22003-07-16016 July 2003 Joseph A. Farley, Amendment Request to Revise Technical Specifications Control Room Emergency Filtration/Pressurization System and Penetration Room Filtration System, Revision 2 2023-03-29
[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-24-0230, 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-24-0064, 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 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-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-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 ML21313A3272021-10-28028 October 2021 0, Technical Specification Bases ML21313A3262021-10-28028 October 2021 0 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications 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 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-19-0006, 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) 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 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-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases2017-04-20020 April 2017 Joseph M. Farley Nuclear Plant, Technical Specifications Bases ML17117A3742017-04-20020 April 2017 Technical Specifications Bases 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-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.2016-07-28028 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application. NL-15-1761, Response to Request for Additional Information Regarding Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294)2015-09-17017 September 2015 Response to Request for Additional Information Regarding Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294) 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-14-1531, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process2015-04-13013 April 2015 License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process ML14335A6292014-11-24024 November 2014 Basis for Proposed Changes. Part 2 of 2 NL-14-1385, Basis for Proposed Changes. Part 1 of 22014-11-24024 November 2014 Basis for Proposed Changes. Part 1 of 2 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-13-0081, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,Using the Consolidated Line Item Improvement...2013-01-23023 January 2013 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,Using the Consolidated Line Item Improvement... NL-12-0403, Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST)2012-02-28028 February 2012 Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST) 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-11-0299, Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.42012-01-18018 January 2012 Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.4 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 NL-10-0272, License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated..2010-10-29029 October 2010 License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated.. 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-08-0535, 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 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 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 NL-05-0068, Technical Specification Amendment Request to Incorporate Best Estimate LOCA Analysis Using Astrum2005-10-0606 October 2005 Technical Specification Amendment Request to Incorporate Best Estimate LOCA Analysis Using Astrum NL-05-0740, Submittal of Joseph M. Farley Nuclear Plant, Technical Specifications Revision Spent Fuel Cask Loading Requirements2005-05-17017 May 2005 Submittal of Joseph M. Farley Nuclear Plant, Technical Specifications Revision Spent Fuel Cask Loading Requirements ML0512300672005-04-22022 April 2005 Enclosure, Correction Ltr. on Amendment Nos. 167 & 159 for Elimination of Hydrogen Recombiners and Monitors (Tac No. MC3224, MC3225) ML0507303042005-03-0808 March 2005 Enclosure, Amendment 168 & 160, TS Revision on 5.6 Reporting Requirements 2024-08-16
[Table view] Category:Amendment
MONTHYEARNL-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 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-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-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-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 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-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-14-0635, 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-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 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-08-0535, 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 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 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 NL-05-0740, Submittal of Joseph M. Farley Nuclear Plant, Technical Specifications Revision Spent Fuel Cask Loading Requirements2005-05-17017 May 2005 Submittal of Joseph M. Farley Nuclear Plant, Technical Specifications Revision Spent Fuel Cask Loading Requirements ML0512300672005-04-22022 April 2005 Enclosure, Correction Ltr. on Amendment Nos. 167 & 159 for Elimination of Hydrogen Recombiners and Monitors (Tac No. MC3224, MC3225) ML0507303042005-03-0808 March 2005 Enclosure, Amendment 168 & 160, TS Revision on 5.6 Reporting Requirements NL-03-2454, Exigent Technical Specification Revision Request Regarding Electrical Power Systems AC Sources - Operating2003-12-0303 December 2003 Exigent Technical Specification Revision Request Regarding Electrical Power Systems AC Sources - Operating NL-03-1914, Request for Technical Specification Changes Regarding DC Sources - Operating2003-09-19019 September 2003 Request for Technical Specification Changes Regarding DC Sources - Operating NL-03-1470, Withdrawal of Request for Technical Specification Changes Deletion of LCO 3.6.1, Condition a and Addition of LCO 3.0.8, Inoperability of Non-Technical Specification Support Systems2003-08-18018 August 2003 Withdrawal of Request for Technical Specification Changes Deletion of LCO 3.6.1, Condition a and Addition of LCO 3.0.8, Inoperability of Non-Technical Specification Support Systems NL-03-0779, Request for Revise TS Control Room Emergency Filtration/Pressurization System & Penetration Room Filtration System - Revision 12003-05-20020 May 2003 Request for Revise TS Control Room Emergency Filtration/Pressurization System & Penetration Room Filtration System - Revision 1 ML0202402792002-01-0404 January 2002 Units 1 & 2, Technical Specifications 2024-05-03
[Table view] |
Text
Mark J. Ajluni, P.E. Southern Nuclear Nuclear Licensing Director Operating Company. Inc.
40 Inverness Center Parkway Post Office Box 1295 Bi rm ingham, Alabama 35201 Tel 205.992.7673 Fax 205 .992 .7885 September 9, 2011 SOUIHERN ' \
COMPANY Docket Nos.: 50-348 NL-11-1057 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Units 1 and 2 License Amendment Request for Technical Specification Table 3.3.1-1 Ladies and Gentlemen :
In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) is submitting a request for an amendment to the Technical Specifications (TS) for Farley Nuclear Plant (FNP) Units 1 and 2.
The proposed change will add Surveillance Requirement (SR) 3.3.1.14 to FNP TS Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." SR 3.3.1.14 requires verification that the RTS RESPONSE TIME is within limits every 18 months on a STAGGERED TEST BASIS. Function 3 is the Power Range Neutron Flux High Positive Rate Trip (PFRT) function . This change is being proposed based on a reanalysis of the Rod Cluster Control Assembly Bank Withdrawal at Power event. provides a description and justification for the proposed change . provides the marked-up TS pages and TS Bases pages for the proposed change . Enclosure 3 provides the clean typed TS pages and TS Bases pages.
SNC requests approval of the proposed license amendments by August 31, 2012. The proposed change will be implemented 90 days from the date of issuance.
This letter contains no NRC commitments.
If you have any questions, please contact Jack Stringfellow at (205) 992-7037.
u.s. Nuclear Regulatory Commission NL-11-1057 Page 2 Mr. M. J. Ajluni states he is Nuclear Licensing Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.
Respectfully submitted, M. J. Ajluni Nuclear Licensing Director
. ' 0 and subscribe before me this !/Ii.- day o~~
MJAlDWM/lac EnClosures: 1. Basis for Proposed Change
- 2. Technical Specifications and Bases Markup Pages
- 3. Technical Specifications and Bases Clean Typed Pages cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. J. T. Gasser, Executive Vice President Mr. M. L. Stinson Vice President - FNP Ms. P. M. Marino, Vice President - Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - FNP Mr. E. L. Crowe, Senior Resident Inspector - FNP Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Farley Nuclear Plant Units 1 & 2 License Amendment Request for Technical Specification Table 3.3.1-1 Enclosure 1 Basis for Proposed Change
Farley Nuclear Plant Units 1 & 2 License Amendment Request for Technical Specification Table 3.3.1-1 Enclosure 1 Basis for Proposed Change Table of Contents 1.0 Summary Description 2.0 Detailed Description 3.0 Technical Evaluation 4.0 Regulatory Evaluation 4.1 Significant Hazards Consideration 4.2 Applicable Regulatory Requirements / Criteria 4.3 Precedent 4.4 Conclusions 5.0 Environmental Consideration 6.0 References
Enclosure 1 to NL-11-1057 September 09, 2011 Basis for Proposed Change 1.0 Summary Description In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) is proposing a change to the Farley Nuclear Plant (FNP) Unit 1 and Unit 2 Technical Specifications (TS). This proposed change would revise TS 3.3.1, "Reactor Trip System (RTS) Instrumentation" for FNP Units 1 and 2 to add Surveillance Requirement (SR) 3.3.1.14 to Function 3, "Power Range Neutron Flux High Positive Rate" of TS Table 3.3.1-1, "Reactor Trip System Instrumentation."
2.0 Detailed Description TS 3.3.1 Table 3.3.1-1 Proposed Change The proposed change would revise TS 3.3.1 to add SR 3.3.1.14 to Function 3 of TS Table 3.3.1-1. SR 3.3.1.14 requires that RTS RESPONSE TIMES be verified to be within limits every 18 months on a STAGGERED TEST BASI S. Function 3 is the power range neutron flux high positive rate trip (PFRT) function. This change is being proposed based on a reanalysis of the Rod Control Cluster Control Assembly Bank Withdrawal at Power event.
3.0 Technical Evaluation SR 3.3.1.14 requires a verification that RTS RESPONSE TIMES are within limits every 18 months on a STAGGERED TEST BASIS, as defined in the FNP TS . As stated in the TS Bases, SR 3.3.1.14 verifies that the individual channel/train actuation response times are less than or equal to the maximum values assumed in the accident analysis. Response time testing acceptance criteria are included in the Final Safety Analysis Report (FSAR), Chapter 16 (Reference 1). Individual component response times are not modeled in the analyses. The analyses model the overall or total elapsed time, from the point at which the parameter exceeds the trip setpoint value at the sensor to the point at which the equipment reaches the required functional state (i.e., control and shutdown rods fully inserted in the reactor core).
FNP FSAR Table 7.2-5 lists the associated response time as N/A for item 3 (Power Range Neutron Flux High Positive Rate). As a result, the response time for the PFRT is not being verified.
RWAP RCS Overpressure Analyses for FNP Nuclear Safety Advisory Letter (NSAL) 09-1 dated February 4,2009 (Reference 2), issued by Westinghouse discussed the potential for Reactor Coolant System (RCS) overpressurization as a result of a control rod bank withdrawal during power operation (RWAP) and the overall results of analyses crediting PFRT for this event. Westinghouse determined that the methodology used for the generic and plant-specific RWAP RCS overpressure analyses incorrectly assumed that a minimum initial power level creates the most limiting condition. Previous analyses have assumed an initial power level of 10 percent of rated thermal power (RTP), minus calorimetric uncertainty. Further investigation has identified cases from higher initial power levels that are more limiting. With the generic E1 - 2 to NL-11-1057 September 09, 2011 Basis for Proposed Change analysis key parameters and methodology, some cases exceeded the RCS overpressure limit for initial power levels in the range of 60 percent to 80 percent RTP.
Since these are the results of very conservative methodology, Westinghouse has concluded that a substantial safety hazard does not exist for Westinghouse PWRs or within the AP1 000 design certification. However, Westinghouse completed specific analyses for FNP Units 1 and 2 which addressed the potential for RCS overpressure following a RWAP. The results for FNP, using a conservative methodology, demonstrate that the RCS overpressure limit listed in FNP TS 2.1.2 (i.e., 2735 psig) is not violated, assuming that credit is taken for a PFRT at or below 9 percent of RTP with a lag time constant of 2 seconds and a trip delay time of 0.65 second.
These analyses were based on the key parameters for the Farley units listed on Table A-1. The Farley analyses for a PFRT at 9% of RTP with 0.65 second delay involved 680 individual LOFTRAN computer runs at various initial conditions and reactivity insertion rates. The results are plotted on the attached Figure A-1. Two plots are provided: peak RCS pressure versus reactivity insertion rate; and peak RCS pressure versus initial power level. Both plots are based on the 340 transient calculations starting from a pressurizer pressure of 2200 psia and the 340 transient calculations starting from a pressurizer pressure of 2300 psia.
These analyses calculated an acceptable result (i.e., RCS peak pressure not in excess of 2750 psia) with a PFRT at 9% of RTP, a lag time constant of 2.0 seconds, and a trip delay time of 0.65 second.
Table A-1: Key Reactor Trip Parameters Used for the FNP Units 1 and 2 RWAP RCS Pressure Analysis 118 High Flux Trip SAL (%)
0.5 High Flux Tr~ Delay (sec) 2440 High Przr Pressure Trip Setpoint (psia) 1 High Przr Pressure Trip Delay (sec) 9 Positive Flux Rate Trip SAL (%)
2 Positive Flux Rate Trip Time Constant (sec) 0.65 Positive Flux Rate Trip Delay (sec)
E1 - 3
Enclosure 1 to NL-11-1 057 September 09, 2011 Basis for Proposed Change The initial conditions and sequence for FNP of events of the worst case analyzed (peak RCS pressure) are:
Initial Conditions:
Power 0.75 fraction of RTP Pressurizer pressure 2200 psia 3
Pressurizer water volume 740.15ft RCS Tavg 575.65 of Reactivity insertion rate 27 pcm/sec Time Sequence of Events:
Event Value Time (sec)
High PZR pressure trip point reached
- 2440 psia 10.17 PFRT trip point reached 9% of RTP 11.10 RCCAs released and began falling N/A 11.17 Maximum core heat flux reached 1.0994 fraction 12.20 of RTP Maximum RCS pressure reached 2715.50 psia 13.50 High neutron flux trip point reached 118% of RTP 999.99 **
- The RCCAs were released via the high PZR pressure signal; the Farley high PZR pressure trip delay is 1 sec. The RCCAs were released via the PFRT signal for other cases analyzed. The maximum calculated RCS pressure would not have met the analysis acceptance criterion in some of those other cases if the PFRT had not been credited.
- The High Neutron Flux (HNF) trip point was not reached during the event; the "999.99 sec" default indicates that this trip was not reached .
E1 - 4 to NL-11-1 057 September 09, 2011 Basis for Proposed Change Figure A-1 2750 2700
.m til, 2650 Q.
ui 2600
.:II:
2550 I___
- 223 00 I i 2500 2~5a 2 ~ OO 0 20 40 60 80 100 120 Reactivity Rate, pcmfse'c Farley, ALA, With PFRT
- 7 C O
<II
~
US 0 0.
i:3 26 50 til 31 :::6: 0 0: 2550 220 VI 1__ 23 °10
~ 251)0 m
a.. ~450 24!l'0 Power, Fraction of RTP E1 - 5
Enclosure 1 to NL-11-1057 September 09, 2011 Basis for Proposed Change Power Range Neutron Flux High Positive Rate Response Time Verification The PFRT response time of 0.65 second, is explicitly credited in the RWAP analysis and must be met. The definition of Reactor Trip System (RTS)
Response Time in the Farley Units 1 and 2 Technical Specifications states: The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage."
The PFRT response time is verified as per WCAP-14036-P-A, Revision 1, "Elimination of Periodic Protection Channel Response Time Tests" (Reference 3).
This approach is based on having performed an initial baseline RTS response time test. Following the initial RTS response time test on this reactor trip function, periodic response time tests are not required consistent with WCAP-14036-P-A, Revision 1, since other required tests ensure that the response time continues to be met.
Since the PFRT response time is essentially the same as the Power Range Neutron Flux - High (PRNF - High) reactor trip function, the PFRT response time can be implicitly verified during the response time test for the PRNF-High reactor trip function as discussed below.
The PFRT circuitry is part of the Nuclear Instrumentation System (NIS). The circuit consists of the difference between the Power Range Nuclear Flux (PRNF) signal and that same signal with a first order lag . That is, PFRT trip signal = Flux - FluX/(1 +1s),
where T is the time constant and s is the Laplacian operator.
The nominal trip setpoint (difference) for the PFRT reactor trip function contained in FNP TS 3.3.1 is 5 percent of RTP with a time constant (T) 2! 2 seconds. Both the PRI\lF-High and PFRT reactor trip signals are sent from the 1\lIS to the protection system via the same components and are processed from the same PRNF signals and identical bistables. There is no significant time delay for the PFRT added by the additional signal processing to form the difference between the flux signal and the lagged flux signal. Other than having different nominal trip setpoints, the PFRT trip signal sent to the protection system has a response time similar to the PRNF-High reactor trip function.
Therefore, verifying the PRNF-High reactor trip function response time provides reasonable assurance of the PFRT reactor trip function response time, until verification of the PFRT response time can be performed. Adding SR 3.3.1.14 to TS 3.3.1 Table 3.3.1-1 Function 3 would require verification of RTS response times for the PFRT.
SNC has reviewed preoperational test data and confirmed that, during preoperational testing, the response time of the NIS and Solid State Protection System (SSPS) for the PFRT function was measured and recorded. The slowest response time measured for a channel was 0.235 second. Per the Westinghouse E1 - 6 to NL-11-1057 September 09, 2011 Basis for Proposed Change analysis, the total function response time limit is ~ 0.65 second. SNC has confirmed that the PRNF overall function response time is ~ 0.65 second. This confirmation is based upon the response time measured during preoperational testing of the NIS and SSPS processing time, and the most recent surveillance data for the other components that comprise the string.
4.0 Regulatory Evaluation 4.1 Significant Hazards Consideration Southern Nuclear Operating Company (SNC) has evaluated whether or not a significant hazards consideration is involved with the proposed changes by focusing on three standards set forth in 10 CFR 50.92(c) as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change to Farley Nuclear Plant (FNP) Technical Specification (TS) 3.3.1, "Reactor Trip System (RTS)
Instrumentation," Table 3.3.1-1, "Reactor Trip System Instrumentation," does not significantly increase the probability or consequences of an accident previously evaluated in the Update Final Safety Analysis Report (UFSAR). The overall protection system performance will remain within the bounds of the accident analysis since there are no hardware changes. The design of the Reactor Trip System (RTS) instrumentation, specifically the power range neutron flux high positive rate trip (PFRT) function, will be unaffected. The reactor protection system will continue to function in a manner consistent with the plant design basis. All design, material, and construction standards, that were applicable prior to the request, are maintained.
The proposed change imposes additional surveillance requirements to assure safety related structures, systems, and components (SSCs) are verified to be consistent with the safety analysis and licensing basis. In this specific case, a response time verification requirement will be added to the PFRT function.
The proposed changes will not modify any system interface. The proposed changes will not affect the probability of any event initiators. There will be no degradation in the performance of, or an increase in the number of challenges imposed on, safety related equipment assumed to function during an accident situation. There will be no change to normal plant operating parameters or accident mitigation performance. The proposed change will not alter any assumptions nor change any mitigation E1 - 7 to NL-11-1057 September 09, 2011 Basis for Proposed Change actions in the radiological consequences evaluations in the UFSAR.
The proposed change does not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configuration of the facility or the manner in which the plant is operated and maintained. The proposed changes do not alter nor prevent the ability of SSCs from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed change is consistent with the safety analyses assumptions and resultant consequences.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
There are no hardware changes nor are there any changes in the method by which any safety related plant system performs its safety function. This change will not affect the normal method of plant operation nor change any operating parameters. No performance requirements will be affected; however, the proposed change does impose additional surveillance requirements. The additional surveillance requirements are consistent with assumptions made in the safety analyses and licensing basis.
No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures are introduced as a result of this change. There will be no adverse effect or challenges imposed on any safety-related system as a result of this change.
Therefore, the proposed change does not create the possibility of a new or different accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed change does not affect the acceptance criteria for any analyzed event nor is there a change to any Safety Limits.
There will be no effect on the manner in which Safety Limits or Limiting Conditions of Operations are determined nor will there be any effect on those plant systems necessary to assure the accomplishment of protection functions.
The safety analyses limits assumed in the accident analysis are unchanged. The imposition of additional surveillance requirements increases the margin of safety by assuring that the affected safety analyses assumptions on equipment response time E1 - 8 to NL-11-10S7 September 09, 2011 Basis for Proposed Change are verified on a periodic frequency. Therefore, the proposed change does not involve a significant reduction in the margin of safety.
Based on the above, SNC concludes that the proposed amendment does not involve a significant hazards consideration under the standard set forth in 10 CFR SO.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.2 Applicable Regulatory Requirements I Criteria The following lists the regulatory requirements and plant - specific design bases related to the proposed changes.
- GDC-13 requires that instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems.
- GDC-20 requires that the protection system(s) shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.
- GDC-21 requires that the protection system(s) shall be designed for high functional reliability and testability.
- GDC-22 through GDC-2S and GDC-29 require various design attributes for the protection system(s), including independence, safe failure modes, separation from control systems, requirements for reactivity control malfunctions, and protection against anticipated operational occurrences .
- Regulatory Guide 1.22 describes an acceptable method for ensuring that the protection system is designed to permit periodic testing of its functioning during reactor operation.
- 10 CFR SO.SSa paragraph (h), "Protection systems," states, in part, that "protective systems must meet the requirements stated in either IEEE Std. 279, "Criteria for Protection Systems for Nuclear Power Generating Stations," or in IEEE Std. 603-1991, "Criteria for Safety Systems for Nuclear Power Generating Stations."
E1 - 9 to NL-11-1 057 September 09, 2011 Basis for Proposed Change
- 10 CFR 50.36 paragraph (c)(1)(ii)(A), "Safety limits, limiting safety system settings, and limiting control settings" requires limiting safety system settings to be included in the Technical Specifications and to be "so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded."
states "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
4.3 Precedent Vogtle Technical Specification Amendments 159/141, Unit 1 and Unit 2 respectively, dated February 7, 2011.
Comanche Peak Technical Specification Amendments 151/151, Unit 1 and Unit 2 respectively, dated April 26, 2010.
4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 Environmental Consideration 10 CFR 51.22(c)(9) provides criteria for identification of licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed license amendment will not:
- 1. Involve a Significant hazards conSideration,
- 2. Result in a significant change in the types, or a significant increase in the amounts, of any effluents that may be released offsite, or
- 3. Result in a significant increase in individual or cumulative occupational radiation exposure.
E1 - 10 to NL-11-1057 September 09, 2011 Basis for Proposed Change SNC has evaluated the proposed changes and determined the changes do not involve (1) a significant hazards consideration, (2) a significant change in the types or significant increase in the amounts of any effluents that may be released off-site, or (3) a significant increase in the individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9), and an environmental assessment of the proposed change is not required.
6.0 References
- 1. FNP Updated Final Safety Analysis Report, Revision 23.
- 2. Westinghouse Nuclear Safety Advisory Letter (NSAL) 09-1, "Rod Withdrawal at Power Analysis for Reactor Control System Overpressure." February 4, 2009.
- 3. WCAP-14036-P-A, Revision 1 "Elimination of Periodic Protection Channel Response Time Tests."
E1 - 11
Farley Nuclear Plant Units 1 & 2 License Amendment Request for Technical Specification Table 3.3.1-1 Enclosure 2 Technical Specifications and Bases Markup Pages
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 8)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 1. Manual Reactor 1,2 2 B SR 3.3.1.12 NA NA Trip 3 (a) , 4 (a) , 5 (a) 2 C SR 3.3.1.12 NA NA
- 2. Power Range Neutron Flux
- a. High 1,2 4 D SR 3.3.1.1 :::; 109.4% RTP :::; 109%
SR 3.3.1.2 RTP SR 3.3.1.7 SR3.3.1.10 SR3.3.1.14
- b. Low 1(b),2 4 E SR 3.3.1.1 :::; 25.4% RTP :::; 25% RTP SR 3.3.1.8 SR 3.3.1.10 SR3.3.1.14
- 3. Power Range 1,2 4 D SR 3.3.1.7 :::; 5.4% RTP :::; 5% RTP Neutron Flux High SR 3.3.1.10 with time with time Positive Rate constant constant ISR 3.3.1. 14 ;:0, 2 sec ;:0, 2 sec
- 4. Intermediate 1(b), 2(c) 2 F,G SR 3.3.1.1 :::;40% RTP :::; 35% RTP Range Neutron SR 3.3.1.8 Flux SR 3.3.1.10 2(d) 2 H SR 3.3.1.1 :::;40% RTP :::; 35% RTP SR 3.3.1.8 SR 3.3.1.10 (a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.
(b) Below the P-10 (Power Range Neutron Flux) interlocks.
(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.
(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
Farley Units 1 and 2 3.3.1-14 Amendment No. f~t] (Unit 1)
Amendment No. (Unit 2)
RTS Instrumentation B 3.3.1 BASES APPLICABLE 3. Power Range Neutron Flux - High Positive Rate (continued)
SAFETY ANALYSES, LCO, and Power Range Neutron Flux - High and Low Setpoint trip APPLICABILITY Functions to ensure that the criteria are met f a rod ejection event.
The LCO requires all four of the wer Range Neutron Flux High Positive Rate channe 0 be OPERABLE. The channels are combined in a 2-0 -of-4 trip Logic.
In MODE 1 , when there is a potential to add a large amouQ.kJ positive reactivity from a rod ejection accident (REA),
re activity excursions such t--_ _ --'-t hIEY..,..'pQwer Range Neutron Flux - High Positive Rate trip must L1l as an inadvertent control be OPERABLE. In MODE 3, 4, 5, or 6, the Power Range rod withdrawal or Neutron Flux- High Positive Rate trip Function does not have to be OPERABLE because other RTS trip Functions and administrative controls will provide protection against positive reactivity additions. Also, since only the shutdown banks may be withdrawn in MODE 3, 4, or 5, the remaining complement of control bank worth ensures a sufficient degree of SDM in the event of an REA. In MODE 6, no rods are withdrawn and the SDM is increased during refueling operations. The reactor vessel head is also removed or the closure bolts are detensioned preventing any pressure buildup.
(continued)
Farley Units 1 and 2 B3.3.1-11 IBevision 401
Farley Nuclear Plant Units 1 & 2 License Amendment Request for Technical Specification Table 3.3.1-1 Enclosure 3 Technical Specifications and Bases Clean Typed Pages
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 8)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 1. Manual Reactor 1,2 2 B SR 3.3.1.12 NA NA Trip 3 (a) , 4 (a) , 5 (a) 2 C SR 3.3.1.12 NA NA
- 2. Power Range Neutron Flux
- a. High 1.2 4 D SR 3.3.1.1 s 109.4% RTP s 109%
SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1 .10 SR 3.3.1.14
- b. Low 1(b),2 4 E SR 3.3.1.1 s 25.4% RTP s 25% RTP SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.14
- 3. Power Range 1,2 4 D SR 3.3.1.7 s 5.4% RTP s 5% RTP Neutron Flux High SR 3.3.1 .10 with time with time Positive Rate SR3.3.1 .14 constant constant
~ 2 sec ~ 2 sec
- 4. Intermediate 1(b).2(c) 2 F,G SR 3.3.1.1 s 40% RTP s 35% RTP Range Neutron SR 3.3.1.8 Flux SR 3.3.1.10 2(d) 2 H SR 3.3.1.1 s 40% RTP s 35% RTP SR 3.3.1.8 SR 3.3.1.10 (a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.
(b) Below the P-10 (Power Range Neutron Flux) interlocks .
(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.
(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
Farley Units 1 and 2 3.3.1-14 Amendment No. (Unit 1)
Amendment No. (Unit 2)
RTS Instrumentation B 3.3.1 BASES APPLICABLE 3. Power Range Neutron Flux - High Positive Rate (continued)
SAFETY ANALYSES, LCO, and Power Range Neutron Flux - High and Low Setpoint trip APPLICABILITY Functions to ensure that the criteria are met for reactivity excursions such as an inadvertent control rod withdrawal or a rod ejection event.
The LCO requires all four of the Power Range Neutron Flux High Positive Rate channels to be OPERABLE. The channels are combined in a 2-out-of-4 trip Logic.
In MODE 1 or 2, when there is a potential to add a large amount of positive reactivity from a rod ejection accident (REA),
the Power Range Neutron Flux - High Positive Rate trip must be OPERABLE. In MODE 3,4,5, or 6, the Power Range Neutron Flux - High Positive Rate trip Function does not have to be OPERABLE because other RTS trip Functions and administrative controls will provide protection against positive reactivity additions. Also, since only the shutdown banks may be withdrawn in MODE 3, 4, or 5, the remaining complement of control bank worth ensures a sufficient degree of SDM in the event of an REA. In MODE 6, no rods are withdrawn and the SDM is increased during refueling operations. The reactor vessel head is also removed or the closure bolts are detensioned preventing any pressure buildup.
(continued)
Farley Units 1 and 2 B3.3.1-11