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Category:Letter type:NL
MONTHYEARNL-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-24-0349, 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-24-0259, 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-24-0340, 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-24-0321, 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-24-0201, 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-24-0238, 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-24-0134, 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 NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application 2024-09-04
[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-24-0281, 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-24-0234, 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-24-0238, 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-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-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 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, 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-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-21-0925, 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-21-0930, 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-21-0385, 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-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 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-19-0963, Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process2019-12-11011 December 2019 Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process NL-19-1063, Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition2019-12-10010 December 2019 Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-19-0771, Risk Informed Technical Specification Information Only Bases Changes2019-06-27027 June 2019 Risk Informed Technical Specification Information Only Bases Changes NL-18-0668, Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2018-12-14014 December 2018 Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material NL-18-1189, Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-4712018-11-29029 November 2018 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-471 ML18226A0942018-08-0909 August 2018 Edwin I. Hatch, Units 1 and 2; and Vogtle, Units 1 and 2 - License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-shift Staff Tables NL-18-0039, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ...2018-07-27027 July 2018 License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ... NL-18-0733, Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information2018-06-0707 June 2018 Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures NL-17-0190, Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidate Line Item Improvement Process2017-12-21021 December 2017 Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidate Line Item Improvement Process NL-17-0611, Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow2017-12-21021 December 2017 Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow NL-17-1088, Submittal of License Amendment Request, Relocation of the Emergency Operations Facility2017-08-30030 August 2017 Submittal of License Amendment Request, Relocation of the Emergency Operations Facility NL-16-2384, Non-Voluntary License Amendment Request to Correct Non-Conservative Technical Specification 3.7.12017-03-22022 March 2017 Non-Voluntary License Amendment Request to Correct Non-Conservative Technical Specification 3.7.1 ML15329A0322017-01-23023 January 2017 Issuance of Amendment Related to Renewed Facility Operating License Condition 2.C.(23) Required Completion Date ML16340A0052016-12-0101 December 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Rev 4, Clarify Use and Application Rules. NL-16-1026, Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2016-11-21021 November 2016 Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements 2024-09-04
[Table view] Category:Technical Specifications
MONTHYEARML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) 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-23-0506, 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-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 ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves NL-22-0091, Correction of Technical Specification Typographical Omission2022-02-24024 February 2022 Correction of Technical Specification Typographical Omission ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls 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 ML20303A1192020-12-11011 December 2020 Issuance of Amendment Nos. 232 and 229 Regarding Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19071A1382019-07-16016 July 2019 Issuance of Amendments 223 and 220 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations TSTF-51 and TSTF-471 ML18151A1742018-06-27027 June 2018 Issuance of Amendment Nos. 219 and 216, Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable ML17333A0792017-12-0606 December 2017 Reissue of Corrected Technical Specification Page 3.6.6-3 NL-17-1974, Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package2017-11-21021 November 2017 Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package NL-17-1067, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-06-0808 June 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request ML17034A1932017-02-16016 February 2017 Issuance of Amendments to Adopt TSTF-427 Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML16232A0002016-10-17017 October 2016 Issuance of Amendments Related to NFPA-805 Supplement ML16272A1892016-10-0303 October 2016 Correction to Amendment Nos. 203 (Unit 1) and 199 (Unit 2) ML15289A2272016-06-10010 June 2016 Issuance of Amendments Related to TSTF-432-A, Revision 1 ML16083A2652016-05-17017 May 2016 Issuance of Amendments to Revise Technical Specification 3.4.14 NL-16-0034, License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding2016-03-16016 March 2016 License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding NL-15-1956, Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions2016-03-14014 March 2016 Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions NL-15-2062, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 22015-11-25025 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 2 NL-15-0722, Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request2015-11-20020 November 2015 Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request ML15180A3342015-08-0303 August 2015 Issuance of Amendments ML15083A0982015-06-0202 June 2015 Issuance of Amendments (TAC Nos. MF4828, MF4829, MF4889, and MF4890) ML14308A0482015-03-10010 March 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) NL-15-0188, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52015-02-13013 February 2015 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 NL-14-0115, Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52014-09-17017 September 2014 Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 ML14155A3022014-08-15015 August 2014 Issuance of Amendment Regarding Minimum Condensate Storage Tank Level Technical Specifications ML14069A3442014-05-13013 May 2014 Issuance of Amendments to Incorporate the Schedule for Degraded Grid Voltage Modification NL-12-0867, License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank2012-08-20020 August 2012 License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank NL-12-0868, Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report2012-08-15015 August 2012 Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report NL-12-1226, License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report2012-08-14014 August 2012 License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report NL-12-1552, Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating2012-07-23023 July 2012 Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating 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-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-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-09-1676, Request to Revise Technical Specification 3.7.8, Service Water System (Sws).2009-10-21021 October 2009 Request to Revise Technical Specification 3.7.8, Service Water System (Sws). NL-09-1622, 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-09-1861, License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report2009-09-15015 September 2009 License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report ML0917706642009-09-0404 September 2009 Southern Nuclear Operating Company Plants, License Amendments, Regarding Elimination of Working Hour Restrictions from Technical Specifications ML0827300082008-09-29029 September 2008 Tech Spec Pages for Amendment Nos. 178 and 171 Revised TS for Limiting Condition for Operation 3.9.3, Containment Penetrations. NL-08-0832, Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications.2008-06-12012 June 2008 Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications. ML0818202472008-05-23023 May 2008 Updated Final Safety Analysis Report, Revision 21, Technical Specifications Bases NL-06-2801, Technical Specification Amendment Request, Containment Leakage Rate Testing Program2007-11-0505 November 2007 Technical Specification Amendment Request, Containment Leakage Rate Testing Program NL-07-1079, Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization2007-07-17017 July 2007 Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization 2024-08-27
[Table view] |
Text
Southern Nuclear Operating Company, Inc.
September 15, 2009 SOUTHERN'\
COMPANY FIIClg\' TO Sen'" JOII/' World Docket Nos.: 50-348 NL-09-1861 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Units 1 & 2 License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report Ladies and Gentlemen:
Southern Nuclear Operating Company (SNC) hereby transmits an application for amendment to Facility Operating License Nos. NPF-2 (Unit 1) and NPF-8 (Unit
- 2) for Joseph M. Farley Nuclear Plant (FNP), in accordance with the provisions of 10 CFR 50.90.
The proposed amendment is administrative in nature and clarifies the application of Technical Specification (TS) 3.3.2 Condition K, which is applicable to the P-11 and P-12 permissive/interlock functions of the Engineered Safety Feature Actuation System (ESFAS). In addition, an editorial change is proposed for TS 5.6.8 to correct the citation of a condition requiring a report for the Post Accident Monitoring (PAM) instrumentation. provides the basis for the proposed TS changes. Enclosure 2 provides the marked-up TS and TS Bases pages. Enclosure 3 provides the clean typed TS and TS Bases pages.
SNC requests approval of the proposed amendment request by September 30, 2010. The proposed changes will be implemented within 30 days from the date of issuance.
A copy of th~ proposed changes has been sent to Dr. D. E. Williamson, the Alabama State Designee, in accordance with 10 CFR 50.91 (b)(1).
U. S. Nuclear Regulatory Commission NL-09-1861 Page 2 Mr. M. J. Ajluni states he is Nuclear Licensing Manager 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.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY rvu~~
M. J. Ajluni Manager, Nuclear Licensing Sworn to and subscribed before me this J-~day o
~ f , 2009.
~o2f/.~r~~
Notary Public My commission expires: ? . . ..s J... 1';<
MJA/DWD/phr
Enclosures:
- 1. Basis for Proposed Changes
- 2. Marked-up Technical Specification and Bases Pages
- 3. Clean-Typed Technical Specification and Bases Pages cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Ms. P. M. Marino, Vice President - Engineering RType: CFA04.054 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Joseph M. Farley Nuclear Plant, Units 1 & 2 License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report Enclosure 1 Basis for Proposed Changes
Enclosure 1 Basis for Proposed Changes 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 Joseph M. Farley Nuclear Plant (FNP) Unit 1 and Unit 2 Technical Specifications (TSs).
The Limiting Conditions for Operation (LCOs) for TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," include Condition K, which is applicable to permissives/interlocks P-11 and P-12.
The current text of Condition K addresses the specific condition of two channels being inoperable. Each P-11 and P-12 function has three channels; however, conditions of one or three inoperable channels could also occur. These possibilities are not encompassed by the existing wording of Condition K; therefore, it is proposed to revise the Condition K text to address all possible conditions of inoperable channels.
The proposed new text for Condition K conforms to the corresponding condition statement applicable to P-11 and P-12 which is contained in the Improved Standard Technical Specifications (STS) (NUREG-1431, Vol. 1, Rev. 3.1) applicable to FNP.
Also, with respect to the reporting requirements described in TS 5.6.8, "PAM Report," an editorial correction is proposed to reference TS LCO Condition "F" rather than "G."
2.0 Detailed Description TS LCO 3.3.2 Condition K Proposed Change Change 'Two channels inoperable" to "One or more channels inoperable."
TS Paragraph 5.6.8, "PAM Report," Proposed Change Change "When a report is required by Condition B or G of LCO 3.3.3 ...." to "When a report is required by Condition B or F of LCO 3.3.3 .... "
3.0 Technical Evaluation From TS Table 3.3.2-1, "Engineered Safety Features Actuation System Instrumentation," LCO 3.3.2 Condition K is applicable to permissives/
interlocks P-11 and P-12. Final Safety Analysis Report (FSAR) 7.3 provides a general description of the Engineered Safety Feature Actuation System. Principal functions of P-11 and P-12 are listed in FSAR Table 7.3 4, "Interlocks for Engineered Safety Feature Actuation System," and are described in the Bases for TS 3.3.2, "Engineered Safety Features Actuation System (ESFAS) Instrumentation."
E1 2
Enclosure 1 Basis for Proposed Changes P-11 is an ESFAS permissive/interlock which permits normal unit cooldown and depressurization without actuation of safety injection (SI) from pressurizer low pressure. With two-out-of-three pressurizer pressure instrument channels less than the P-11 setpoint, the operator can manually block the Pressurizer Pressure - Low SI signal. The P-11 interlock provides the following two safety functions. With two-out-of-three pressurizer pressure channels above the P-11 setpoint, the Pressurizer Pressure - Low SI actuation is automatically reinstated. With two-out-of three channels below the P-11 setpoint, the pressurizer power operated relief valves (PORVs) are interlocked closed in the automatic control mode to prevent uncontrolled reactor coolant system (RCS) de-pressurization due to a control system failure or malfunction.
The P-11 function must be operable in Modes 1,2 and 3 to automatically reinstate SI during normal unit heatup and to allow an orderly cooldown and depressurization of the unit without the actuation of a Pressurizer Pressure - Low SI. Also, P-11 is required to interlock automatic PORV operation, if necessary. This function does not have to be operable in Modes 4, 5, or 6 because the associated safety functions are not required.
P-12 is an ESFAS permissive/interlock which permits normal unit cooldown and depressurization without actuation of SI and main steam line isolation (MSLI) on Steam Line Pressure - Low. On decreasing reactor coolant temperature with two-out-of-three Tavg channels below the setpoint, the P 12 interlock allows the operator to manually block SI and MSLI on Steam Line Pressure - Low to permit a normal unit cooldown. The P-12 interlock provides the following three safety functions. On increasing reactor coolant temperature with two-out-of-three channels above the setpoint, the P-12 interlock automatically reinstates the SI and MSLI on Steam Line Pressure
- Low. On decreasing temperature with two-out-of-three Tavg channels below the setpoint, the P-12 safety function is to generate MSLI on High Steam Flow in Two Steam Lines Coincident with Tavg - Low Low.
Another P-12 safety function on decreasing temperature with two-out-of three Tavg channels below the setpoint is for the P-12 interlock to block the steam dump valves to prevent an excessive cooldown of the ReS due to a control system failure or malfunction.
The P-12 function must be operable in Modes 1, 2, and 3 during plant heatup to automatically reinstate SI and MSLI on Steam Line Pressure Low when RCS Tavg is above the P-12 setpoint. In Modes 1,2, and 3, P 12 must be operable to afford protection should a secondary side break, stuck open relief or safety valve, or steam dump malfunction result in the rapid depressurization of the steam lines. This function is operable when the interlock is in the required state for the unit condition. This function does not have to be operable in Modes 4, 5, or 6 because there is insufficient energy in the secondary side to require mitigation of a postulated event.
E1-3
Enclosure 1 Basis for Proposed Changes TS Table 3.3.2-1, "Engineered Safety Feature Actuation System Instrumentation," lists the P-11 and P-12 functions as items 7.c and 7.d.
Per item 7.c, three channels are required for P-11, and the applicable TS LCO 3.3.2 Condition is Condition K. Per item 7.d, one channel per loop (i.e., three channels total) is required for P-12, and LCO 3.3.2 Condition K is applicable.
Both P-11 and P-12 voting logic circuits in each train use input from three protection channels. The current wording of Condition K states, "Two channels inoperable." As a result, Condition K does not explicitly address the possible conditions of one channel or three channels inoperable, possibly creating a literal compliance issue. The existing Condition K wording was implemented when FNP converted to the Improved STS. The wording was intended to maintain consistency with the original FNP licensing basis and the STS action statement for inoperable P-11 or P-12 channels.
The proposed Condition K change from "Two channels inoperable" to "One or more channels inoperable" will resolve the current literal compliance issue created during the conversion to the Improved STS. The change does not alter the current Condition K required action, which requires the operator to verify that the interlock is in the required state for the existing unit condition. The proposed change clarifies that the required action must be performed for one, two, or three P-11 or P-12 channels inoperable.
Also, neither the Completion Time nor the Required Action Time is being changed. The required action will verify that the interlock is in the required state for the existing unit condition. As long as the interlock is in the required state for the existing condition, it is immaterial as to the actual number of inoperable channels. The determination for one, two or more channels must be made within one hour. The one hour Completion Time is equal to the time allowed by LCO 3.0.3 to initiate shutdown actions in the event of a complete loss of ESFAS function.
Main control room indications are provided for the operator to determine the state of the P-11 and P-12 channel bistables, the permissive logic circuits, and the associated Pressurizer Pressure - Low SI & MSLI block circuits.
The proposed Condition K change does not alter these indication circuits or the methods used to verify the state of the P-11 or P-12 permissives/interlocks.
This proposed change to the LCO 3.3.2 Condition K text is consistent with the Improved STS. The proposed Condition K wording is identical to the wording used in the Improved STS for the corresponding condition applicable to the P-11 and P-12 protection channels (reference Improved STS LCO 3.3.2 Condition L).
The proposed change to TS LCO 3.3.2 Condition K does not impact the FNP safety analyses. The change clarifies that the Condition K action E1 4
Enclosure 1 Basis for Proposed Changes requirements are applicable should one, two, or three P-11 and/or P-12 protection channels be inoperable.
With regard to the proposed editorial correction of TS 5.6.8, a citation error was discovered during review of this section. The current TS 5.6.8 text states, "When a report is required by Condition B or G of LCO 3.3.3.... " The review disclosed that the citation of Condition B is correct while Condition G does not currently exist for LCO 3.3.3; instead TS 5.6.8 should cite Condition F.
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 the 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 TS 3.3.2 does not significantly increase the probability or consequences of an accident previously evaluated in the FSAR. These interlocks do not directly initiate an accident. The consequences of accidents previously evaluated in the FSAR are not adversely affected by these changes because the changes are made to reflect the Improved Standard Technical Specifications and the interlocks are verified to be in the required state for the unit condition.
The proposed change to TS 5.6.8 corrects an editorial error and therefore does not significantly increase the probability or consequences of a previously evaluated accident.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change to TS 3.3.2 does not create the possibility of a new or different kind of accident than any accident already evaluated in the FSAR. No new accident scenario, failure mechanisms, or limiting single failures are introduced as a result of the proposed change. The proposed TS 3.3.2 change does not challenge the performance or integrity of any safety-related systems. Therefore, this change does not E1 5
Enclosure 1 Basis for Proposed Changes create the possibility of a new or different kind of accident from any accident previously analyzed.
The proposed change to TS 5.6.8 corrects an editorial error and therefore does not create the possibility of a new or different kind of accident from any accident previously analyzed.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed change to TS 3.3.2 does not involve a significant reduction in a margin of safety. The proposed change is made to accurately reflect the format of the Improved Standard Technical Specifications. The actuation setpoints specified by the Technical Specifications and safety analysis limits assumed in the accident analysis are unchanged. The margin of safety associated with these trip setpoints and the safety analysis acceptance criteria is unchanged.
Therefore, the proposed change to TS 3.3.2 will not significantly reduce the margin of safety as defined in the Technical Specifications.
The proposed change to TS 5.6.8 corrects an editorial error and therefore involves no significant reduction in a margin of safety.
Based on the above, SNC concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(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.
Regarding the Proposed Change to TS 3.3.2:
The regulatory basis for TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," is to ensure that appropriate plant parameters are sensed, compared with predetermined safety limits and logically combined to send actuation signals to appropriate engineered safety feature devices. The ESFAS meets following requirements:
- 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 13, "Instrumentation and Control," requires that instrumentation be provided to monitor variables under normal, anticipated and accident E1-6
Enclosure 1 Basis for Proposed Changes conditions to assure adequate safety, with appropriate controls provided to maintain variables.
- GOC 20, "Protection System Functions," requires that the protection system initiate automatically to assure fuel design limits are not exceeded and that the system sense accident conditions and initiate operation of systems and components important to safety.
- GOC 21, "Protection System Reliability and Testability," requires that the system be designed for high functional reliability and in service testability, with redundancy and independence sufficient to preclude loss of the protection function from a single failure and preservation of minimum redundancy despite removal from service of any component or channel.
- GOC 22, "Protection System Independence," requires that the system be designed so that natural phenomena, operating, maintenance, testing and postulated accident conditions do not result in loss of the protection function.
- GOC 23, "Protection System Failure Modes," requires that the system be designed to fail to a safe state in the event of conditions such as disconnection, loss of energy, or postulated adverse environments.
- GOC 24, "Separation of Protection and Control Systems," requires that interconnection of the protection and control systems be limited to assure safety in case of failure or removal from service of common components.
- 10 CFR 50.36(d)(2)(ii)(C) Criterion 3, which requires that a TS LCO be established.
- 10 CFR 50.55a(h) requires that the protection systems meet IEEE 279-1971. Section 4.2 of IEEE 279-1971 discusses the general functional requirement for protection systems to assure they satisfy the single failure criterion.
Regarding the Proposed Change to TS 5.6.8:
The change corrects an editorial error in citing the appropriate report requirement reference; therefore no discussion of regulatory requirements is applicable.
E1-7
Enclosure 1 Basis for Proposed Changes 4.3 Precedent Regarding the proposed change to TS 3.3.2:
The proposed new text for Condition K would bring TS 3.3.2 Condition K into conformance with the current text of the corresponding condition statement applicable to P-11 and P-12 contained in NUREG-1431, Volume 1, Revision 3.1, "Standard Technical Specifications Westinghouse Plants."
Regarding the proposed change to TS 5.6.8:
The change corrects an editorial error in citing the appropriate report requirement reference; no discussion of precedents is applicable.
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 plant 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 Southern Nuclear has determined that the proposed amendment would change requirements with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, Southern Nuclear has evaluated the proposed amendment and has determined that the amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in the individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed amendment is not required.
6.0 References
- 1. NUREG-1431, Volume 1, Revision 3.1, "Standard Technical Specifications Westinghouse Plants."
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Joseph M. Farley Nuclear Plant, Units 1 & 2 license Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report Enclosure 2 Technical Specifications and Bases Markup Pages
ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I. One channel inoperable. 1.1 ---------NOTE------------
The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 1.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> J. One or more Main J.1 Restore channel(s) to Prior to next required Feedwater Pump trip OPERABLE status. TADOT channels inoperable on one or more Main Feedwater Pumps.
K. ihanne,s inoperable. K.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required state for existing unit condition.
OR lone or more I
K.2.1 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND K.2.2 Be in MODE 4. 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> L. One train inoperable. L.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required state for existing unit condition.
OR (continued)
Farley Units 1 and 2 3.3.2-5 Amendment No. 180 (Unit 1)
Amendment No. 173 (Unit 2)
Reporting Requirements 5.6 5.6 Reporting ReqUirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a. The reactor coolant system pressure and temperature limits, including heatup and cooldown rates, shall be established and documented in the PTLR for LCO 3.4.3.
- b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC letters dated March 31, 1998 and April 3, 1998.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor fluence period and for any revision or supplement thereto.
5.6.7 EDG Failure Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures shall be reported within 30 days.
Reports on EDG failures shall include a description of the failures, underlying causes, and corrective actions taken per the Emergency Diesel Generator Reliability Monitoring Program.
5.6.B PAM Report fl When a report is required by Condition B or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
(continued)
Farley Units 1 and 2 5.6-5 Amendment No. 174 (Unit 1)
Amendment No. 167 (Unit 2)
ESFAS Instrumentation B3.3.2 BASES ACTIONS 4J. (continued) to be lost and the associated Completion Time of prior to the next required TADOT surveillance are acceptable based on the backup nature of this function. This function is not relied on as the primary actuation signal for AFW auto-start in any DBA analysis.
K.1, K.2.1, and K.2.2 Condition K applies to the P-11 and P-12 interlocks. This Condition is applicable when the interlock is inoperable to the extent that an ESFAS function which should not be blocked in the current MODE is blocked.
With on channel inoperable, the operator is not required to take any or more channels .. . , the operator must verify that the interlock is in the required state for the existing unit condition.
This action manually accomplishes the function of the interlock.
Determination must be made within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. 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 equal to the time allowed by LCO 3.0.3 to initiate shutdown actions in the event of a complete loss of ESFAS function. If the interlock is not in the required state (or placed in the required state) for the existing unit condition, the unit must be placed in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the follOWing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
Placing the unit in MODE 4 removes all requirements for OPERABILITY of these interlocks.
L.1, L.2, L.3.1, and L.3.2 Condition L applies to the automatic actuation logic and actuation relays for the P-4, P-11 and P-12 interlocks. This Condition is applicable when the interlock is inoperable to the extent that an ESFAS function Which should not be blocked in the current MODE is blocked.
With one train inoperable, the operator must verify that the interlock is in the required state for the existing unit condition. This action manually accomplishes the function of the interlock. Determination must be made within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the interlock is not in the required state (or placed in the required state) for the existing unit condition, the interlock must be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the unit must be placed in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and (continued)
Farley Units 1 and 2 B.3.3.2-40 Revision 46
Joseph M. Farley Nuclear Plant, Units 1 & 2 License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report Enclosure 3 Technical Specifications Clean Typed Pages
ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I. One channel inoperable. 1.1 -----------NOTE------------
The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 1.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> J. One or more Main J.1 Restore channel(s) to Prior to next required Feedwater Pump trip OPERABLE status. TADOT channels inoperable on one or more Main Feedwater Pumps.
K. One or more channels K.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit condition.
OR K.2.1 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND K.2.2 Be in MODE 4. 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> L. One train inoperable. L.1 Verify interlock is in "' hour required state for existing unit condition.
OR (continued)
Farley Units 1 and 2 3.3.2-5 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a. The reactor coolant system pressure and temperature limits, including heatup and cooldown rates, shall be established and documented in the PTLR for LCO 3.4.3.
- b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC letters dated March 31,1998 and April 3, 1998.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor fluence period and for any revision or supplement thereto.
5.6.7 EDG Failure Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures shall be reported within 30 days.
Reports on EDG failures shall include a description of the failures, underlying causes, and corrective actions taken per the Emergency Diesel Generator Reliability Monitoring Program.
5.6.8 PAM Report When a report is required by Condition B or F of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the folloWing 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
(continued)
Farley Units 1 and 2 5.6-5 Amendment No. (Unit 1)
Amendment No. (Unit 2)
ESFAS Instrumentation B 3.3.2 BASES ACTIONS g (continued) to be lost and the associated Completion Time of prior to the next required TADOT surveillance are acceptable based on the backup nature of this function. This function is not relied on as the primary actuation signal for AFW auto-start in any DBA analysis.
K.1, K.2.1, and K.2.2 Condition K applies to the P-11 and P-12 interlocks. This Condition is applicable when the interlock is inoperable to the extent that an ESFAS function which should not be blocked in the current MODE is blocked.
With one or more channels inoperable, the operator must verify that the interlock is in the required state for the existing unit condition.
This action manually accomplishes the function of the interlock.
Determination must be made within 'I hour. 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 equal to the time allowed by LCO 3.0.3 to initiate shutdown actions in the event of a complete loss of ESFAS function. If the interlock is not in the required state (or placed in the required state) for the existing unit condition, the unit must be placed in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
Placing the unit in MODE 4 removes all requirements for OPERABILITY of these interlocks.
L.1, L.2, L.3.1, and L.3.2 Condition L applies to the automatic actuation logic and actuation relays for the P-4, P-11 and P-12 interlocks. This Condition is applicable when the interlock is inoperable to the extent that an ESFAS function which should not be blocked in the current MODE is blocked.
With one train inoperable, the operator must verify that the interlock is in the required state for the existing unit condition. This action manually accomplishes the function of the interlock. Determination must be made within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the interlock is not in the required state (or placed in the required state) for the existing unit condition, the interlock must be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the unit must be placed in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and (continued)
Farley Units 1 and 2 B 3.3.2-40 Revision