Letter Sequence Request |
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EPID:L-2019-LLA-0278, 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 (Approved, Closed) |
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Category:Letter type:NL
MONTHYEARNL-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, Plants Units 1&2, 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 Plants Units 1&2, 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-23-0877, 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 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, 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 2024-07-03
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0230, Plants Units 1&2, 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 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0238, 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-21-0925, 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-21-0989, License Amendment Request to Relocate Augmented Piping Inspection Program Details2021-12-22022 December 2021 License Amendment Request to Relocate Augmented Piping Inspection Program Details NL-21-1017, License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure2021-12-13013 December 2021 License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure NL-21-0930, Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-10-21021 October 2021 Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections NL-21-0385, 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 ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application 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 NL-16-2335, Re-Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-11-15015 November 2016 Re-Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies NL-16-1763, License Amendment Request - Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2016-10-11011 October 2016 License Amendment Request - Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process NL-15-1421, License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems- Operating.2016-10-11011 October 2016 License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems- Operating. ML16256A1352016-09-0808 September 2016 License Amendment Request to Revise Facility Operating License Condition 2.C.(23) Required Completion Date 2024-07-18
[Table view] Category:Technical Specification
MONTHYEARNL-24-0230, Plants Units 1&2, 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 Plants Units 1&2, 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 NL-04-0564, Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors2004-05-21021 May 2004 Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors 2024-06-28
[Table view] Category:Bases Change
MONTHYEARNL-24-0230, Plants Units 1&2, 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 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 ML23318A0702023-10-31031 October 2023 Technical Specifications Bases ML21313A3262021-10-28028 October 2021 0 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML21313A3272021-10-28028 October 2021 0, Technical Specification Bases 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-19-0006, 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 ML18312A0772018-10-30030 October 2018 Technical Specifications Bases ML17117A3742017-04-20020 April 2017 Technical Specifications Bases NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases2017-04-20020 April 2017 Joseph M. Farley Nuclear Plant, Technical Specifications Bases 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-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 NL-14-1385, Basis for Proposed Changes. Part 1 of 22014-11-24024 November 2014 Basis for Proposed Changes. Part 1 of 2 ML14335A6292014-11-24024 November 2014 Basis for Proposed Changes. Part 2 of 2 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-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-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-04-0564, Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors2004-05-21021 May 2004 Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors NL-03-1511, 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 NL-03-0605, Request for Technical Specification Changes Unit Two Pressurizer Power Operated Relief Valve Block Valve Surveillance Testing2003-03-31031 March 2003 Request for Technical Specification Changes Unit Two Pressurizer Power Operated Relief Valve Block Valve Surveillance Testing NL-03-0372, Technical Specifications Revision Request Removal of Reference to Plant Operations Review Committee2003-03-21021 March 2003 Technical Specifications Revision Request Removal of Reference to Plant Operations Review Committee ML0234505732002-12-0303 December 2002 Transmittal of Revision 19 of the Technical Specifications Bases ML0203701742002-01-10010 January 2002 Revision 11 to Technical Specification Bases 2024-06-28
[Table view] |
Text
,~ Southern Nuclear Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnade Parkway Birmingham . AL 35243 205 992 5316 tel 205 992 7795 fax DEC 1 2 2019 cagayhea@southernco. com Docket Nos. : 50-348 NL-19-0331 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: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors Ladies and Gentlemen:
Pursuant to 10 CFR 50.90 , Southern Nuclear Operating Company (SNC) hereby requests a proposed amendment to the technical specifications (TS) for Joseph M. Farley Nuclear Plant (FNP), Unit 1 renewed facility operating license NPF-2 and Unit 2 renewed facility operating license NPF-8. The proposed amendment will:
- 1. Revise TS 3.3.1, "Reactor Trip System (RTS) Instrumentation," to delete the measurement unit "RTP" (rated thermal power) from the 3% absolute difference acceptance criterion specified in surveillance requirement (SR) 3.3.1.3. This change is needed to correct the acceptance criterion because the subject absolute difference is a percentage of deviation not expressed in RTP.
- 2. Revise TS 3.3.7, "Control Room Emergency Filtration/Pressurization System (CREFS)
Actuation Instrumentation," to change the unit of measure associated with the trip setpoint of TS Table 3.3.7-1, Function 3, "Control Room Radiation Control Room Air Intake (R-35A, B)," from "s; 800 cpm" to an equivalent value of "S: 1.0x1 0*5 ~Ci/cc" and add a footnote clarifying that the value represents radiation above background with no system flow. This change is needed to make the setpoint independent of the radiation monitor type and manufacturer and to be consistent with the units of the containment radiation gaseous and spent fuel pool room radiation gaseous monitors in TS 3.3.6, "Containment Purge and Exhaust Isolation Instrumentation," and TS 3.3.8 , "Penetration Room Filtration (PRF) System Actuation Instrumentation," respectively.
The enclosure provides a basis for the proposed changes, including a proposed no significant hazards considerations analysis. Attachments 1 and 2 contain marked-up TS pages and revised TS pages, respectively. Attachment 3 contains TS Bases pages marked to show the accompanying proposed changes for information only.
Approval of the proposed amendment is requested by December 31 , 2020. SNC will implement the amendments within 60 days of the NRC approval date.
U.S. Nuclear Regulatory Commission NL-19-0331 Page2 In accordance with 10 CFR 50.91, a copy of this letter and enclosure, including attachments, is being provided to the designated Alabama Official.
No regulatory commitments are made in this submittal.
If you should have any questions regarding this submittal , please contact Jamie Coleman at 205.992.6611.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the
~day of December 2019.
Respectfully submitted, a
Director, egu atory Affairs Southern Nuclear Operating Company CAGfTLE/scm
Enclosure:
Basis for Proposed Change Attachments 1. Technical Specification Marked-Up Pages
- 2. Revised (Clean) Technical Specification Pages
- 3. Technical Specification Bases Marked-up Pages (for information only) cc: Regional Administrator, Region II NRR Project Manager- Farley Senior Resident Inspector- Farley Director, Alabama Office of Radiation Control RType: CFA04.054
Joseph M. Farley Nuclear Plant - Units 1 and 2 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 Enclosure Basis for Proposed Change
Enclosure to NL-19-0331 Basis for Proposed Change
- 1.
SUMMARY
DESCRIPTION The proposed amendment to the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 renewed facility operating licenses consists of two changes:
- 1. Revise surveillance requirement (SR) 3.3.1.3 of Technical Specification (TS) 3.3.1, "Reactor Trip System (RTS) Instrumentation," to delete the measurement unit "RTP" (rated thermal power) from the 3% absolute difference comparison between the incore thermal power detector measurements versus the excore nuclear instrumentation system (NIS) axial flux difference (AFD) ; and
- 2. Revise TS 3.3.7, "Control Room Emergency Filtration/Pressurization System (CREFS)
Actuation Instrumentation," to change the unit of measure associated with the trip setpoint of TS Table 3.3.7-1, Function 3, "Control Room Radiation Control Room Air Intake (R-35A, 8) ," from "S 800 cpm" to an equivalent value of "S 1.0x1 o-s IJCi/cc" and add a footnote clarifying that the value represents radiation above background with no system flow.
- 2. DETAILED DESCRIPTION 2.1 System Design and Operation SR 3.3.1.3 Acceptance Criterion Measurement Units The overtemperature !::. T reactor trip function is provided to ensure that the design limit departure from nucleate boiling ratio is met. The inputs to the overtemperature !::. T trip include pressure, coolant temperature, axial power distribution, and reactor power as indicated by loop !::. T assuming full reactor coolant flow. The overtemperature !::. T trip uses each loop's !::. T as a measure of reactor power and is compared with a setpoint that is automatically varied with reactor coolant average temperature, pressurizer pressure, and axial power distribution. AFD is defined as the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector. AFD is expressed in units of % of flux difference.
SR 3.3.1.3 compares the incore system to the NIS channel output. When the absolute difference is~ 3% between the incore and excore AFD, the NIS channel is adjusted.
CREFS Control Room Air Intake Radiation Monitors Trip Setpoint Measurement Units The FNP Units 1 and 2 common control room must be kept habitable for the operators stationed there during normal operation, anticipated transients, and design basis accidents (DBAs). The control room function is supported by CREFS , which provides an enclosed control room environment from which the units can be operated following an uncontrolled release of radioactivity. Upon receipt of an actuation signal, the CREFS initiates filtered ventilation and pressurization of the control room .
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Enclosure to NL-19-0331 Basis for l?roposed Change TS Table 3.3.7-1, Function 3, "Control Room Radiation Control Room Air Intake (R-35A, B)," provides a trip setpoint to isolate the control room air intake. A high radiation signal from one of these detectors isolates the normal unfiltered outside air supply from the control room. The setpoint is selected to limit the radionuclide concentration in the main control room to ensure that the radiological dose to control room occupants remains well below the 10 CFR 50.67(b)(2)(iii) limit, 10 CFR 50, Appendix A general design criterion (GDC) 19 limit, and the applicable 10 CFR 20 Appendix B limit following a DBA.
2.2 Current Technical Specifications Requirements SR 3.3.1.3 Acceptance Criterion Measurement Units SR 3.3.1.3 compares the results of the incore detector measurements to the NIS AFD.
SR 3.3.1.3 states, in part: "Adjust NIS channel if absolute difference is~ 3% RTP."
CREFS Control Room Air Intake Radiation Monitors Trip Setpoint Measurement Units Table 3.3.7-1, CREFS Actuation Instrumentation, establishes a trip setpoint of "S 800 cpm" for Function 3, "Control Room Radiation Control Room Air Intake (R-35A, B)."
2.3 Reason for the Proposed Change SR 3.3.1.3 Acceptance Criterion Measurement Units This change is needed to correct the acceptance criterion because the subject absolute difference is a percentage deviation not expressed in RTP. The proposed change will also align FNP TS to the equivalent surveillance acceptance criterion specified in SR 3.3.1.3 of NUREG-1431, Revision 4 (Reference 1).
CREFS Control Room Air Intake Radiation Monitors Trip Setpoint Measurement Units The current trip setpoint units of counts per minute (cpm) are specific to the installed Victoreen radiation monitors and would require a change to the TSs if or when the radiation monitors were replaced with a different type that uses different units of measure.
The change in units to microcuries per cubic centimeter (IJCilcc) is consistent with the units assumed in the safety analysis and would be independent of the unit of measure based on a specific radiation monitor type or manufacturer. This change also makes the trip setpoint units consistent with the setpoint units for Function 3 of TS Table 3.3.6-1, "Containment Radiation Gaseous (R-24A, B)," and Function 3 of TS Table 3.3.8-1, "Spent Fuel Pool Room Radiation Gaseous (R-25A, B)."
2.4 Description of the Proposed Change SR 3.3.1.3 Acceptance Criterion Measurement Units The measurement unit "RTP" is proposed to be deleted from the 3% acceptance criterion in the last sentence of SR 3.3.1 .3.
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Enclosure to NL-19-0331 Basis for Proposed Change CREFS Control Room Air Intake Radiation Monitors Trip Setpoint Measurement Units The trip setpoint for Function 3, "Control Room Radiation Control Room Air Intake (R-35A, B) ," in TS Table 3.3.7-1 is proposed to be modified from s 800 cpm to s 1.0 X 10-5 1-JCi/cc.
In addition, proposed footnote (c) is referenced for the trip setpoint. Proposed footnote (c) states: "Above background with no flow."
- 3. TECHNICAL EVALUATION SR 3.3.1.3 Acceptance Criterion Measurement Units The current 3% acceptance criterion for the overtemperature 6.T instrument comparison between incore detector measurements and the NIS AFD in% RTP is not correct because the definition of AFD is % of difference from the normalized flux signals. This change does not alter the intent or meaning of the requirement but rather corrects the error introduced in FNP license amendments 203 and 199, issued on August 3, 2016 for Units 1 and 2, respectively (Reference 2) . The surveillance requirement will continue to require the overtemperature 6. T NIS channels to be adjusted when the comparison results between the incore detector measurements and the NIS AFD reaches or exceeds the 3%
acceptance criterion. Therefore, this change is considered administrative.
CREFS Control Room Air Intake Radiation Monitors Trip Setpoint Measurement Units 10 CFR 20, Appendix D defines the derived air concentration (DAC) as the airborne concentration of a given radionuclide, which, if breathed by the reference man for a working year of 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, would result in a committed effective dose equivalent of 5 rem or a committed dose equivalent of 50 rem to any individual organ or tissue. DAC values for occupational dose are listed in Table 1, Column 3, of Appendix B to 10 CFR 20.
The predominant inhalation radionuclides released during a fuel handling accident (FHA) are Xenon (Xe) -133 and Krypton (Kr) -85 and the DAC value for each of these isotopes is 1.0E-04 1-JCi/ml, or 1.0E-04 1-JCi/cc.
The current beta scintillation detector setpoint of 800 cpm is based on the detector's Kr-85 sensitivity and is equivalent to one-tenth of the Kr-85 DAC value; i.e., 1.0E-05 1-JCi/cc.
During an FHA within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown , the inhalation radionuclide mixture released is predominantly Xe-133 and Kr-85 . During an FHA at 30 days or more following shutdown, the inhalation radio nuclide mixture released is 100% Kr-85 due to the decay of Xe-133. SNC has determined that with a control room intake isolation setpoint sensitive to Kr-85 and a release mixture of 10:1 Xe-133 to Kr-85, inhalation concentrations remain well below the associated DAC limits. Therefore, the current instrument setpoint value ensures main control room ventilation intake isolation occurs well before the control room intake concentration reaches the 10 CFR 20 occupational limit. The proposed change from 800 cpm to 1.0 X 1o-s 1-JCi/cc results in equivalent control room ventilation isolation protection and is considered administrative.
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Enclosure to NL-19-0331 Basis for Proposed Change The addition of proposed footnote (c) represents a clarification that the trip setpoint value is that value above the normal background radiation level with no adjustment for flow in the system. The addition of the clarifying footnote is consistent with the footnote associated with the trip setpoint for Function 3 of TS Tables 3.3.6-1 and 3.3.8-1 and is considered administrative.
The proposed change continues to ensure the main control room ventilation intake isolation occurs well before the intake concentration reaches the applicable 10 CFR 20 occupational limit, which is consistent with the GDC 19 and 10 CFR 50.67(b)(2)(iii) dose limit for control room personnel.
- 4. REGULATORY EVALUATION Following implementation of the proposed changes, FNP Units 1 and 2 will remain in compliance with applicable regulations and design criteria as described in the FNP UFSAR and as previously licensed and approved by the NRC.
4.1 Applicable Regulatorv Requirements/Criteria The RTS and CREFS radiation monitor designs satisfy 10 CFR 50.36 , "Technical specifications," paragraph (c)(2)(ii) , Criterion 3. A reactor trip from overtemperature Ll T and control room ventilation isolation from inlet radiation monitors are considered primary success paths to mitigate certain accidents and transients as described in Chapters 7 and 15 of the FNP UFSAR.
The proposed amendment does not delete requirements associated with the RTS or CREFS isolation instrumentation. Limiting condition for operation (LCO) 3.3 .1 and LCO 3.3.7 continue to maintain requirements associated with structures, systems, and components that are part of the primary success path and actuate to mitigate the related design basis accidents and transients. The proposed amendment does not alter the remedial actions or shutdown requirements required by 10 CFR 50.36(c)(2)(i) for RTS or CREFS isolation instrumentation.
The proposed change to the CREFS control room air intake radiation monitors isolation trip setpoint to an equivalent setpoint in units of IJCi/cc instead of cpm with the addition of a clarifying note continues to ensure adequate radiation protection is provided to permit access to and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 0.05 Sv (5 rem) total effective dose equivalent for the duration of the accident; thus, maintaining compliance with 10 CFR 50 .67(b)(2)(iii) .
The RTS and CREFS control room isolation instrumentation designs comply with the requirements of 10 CFR 50.55a(h)(2) , Protection and Safety Systems, and meet the requirements of the applicable Institute of Electrical and Electronics Engineers standard pursuant to 10 CFR 50.55a(2) , as previously licensed and approved by the NRC. The proposed amendment does not alter the design of any protection or safety system, E-4
Enclosure to NL-19-0331 Basis for Proposed Change including the RTS and CREFS isolation instrumentation. Therefore, the protection and safety system design continues to meet the requirements of 10 CFR 50.55a.
In addition , the following 10 CFR Part 50, Appendix A General Design Criteria are related to the instrumentation design:
General Design Criterion (GDC 10): Reactor design. The proposed amendment does not alter the design of the reactor core and associated coolant, control, and protection systems, including the RTS. The change deletes the unit "RTP" from the 3% deviation adjustment criterion since the correct unit is% of absolute deviation, not% of RTP.
GDC 13: Instrumentation and control. The proposed amendment does not alter the design of the instrumentation that is 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. The change deletes the unit "RTP from the 3% deviation adjustment criterion since the correct unit is % of absolute deviation, not% of RTP. The change also revises the trip setpoint in units of cpm to an equivalent setpoint in units of !JCi/cc with a clarifying note that the value is that above background level with no flow.
GDC 15: Reactor coolant system design. The proposed amendment does not alter the design of the control and protection instrumentation that is provided to assure, with sufficient margin, that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences.
GDC 19: Control room . The proposed amendment does not alter the design or impact the capability of the control room to provide a habitable location from where actions can be taken to operate the FNP units safely under normal conditions and to maintain them in a safe condition under accident conditions, including loss-of-coolant accidents. The change revises the CREFS control room ventilation isolation instrumentation trip setpoint in units of cpm to an equivalent setpoint in units of !JCi/cc with a clarifying note that the value is that above background level with no flow. Because this change is an equivalent change in units, adequate radiation protection continues to be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident to the extent previously licensed and approved by the NRC.
GDC 20: Protection system functions. The proposed amendment does not alter the design of reactivity control protection systems or instrumentation that sense accident conditions to initiate systems or components important to safety. The change deletes the unit "RTP" from the 3% deviation adjustment criterion since the correct unit is % of absolute deviation, not% of RTP. The change also revises the CREFS control room ventilation isolation instrumentation trip setpoint in units of cpm to an equivalent setpoint in units of !JCi/cc with a clarifying note that the value is that above background level with E-5
Enclosure to NL-19-0331 Basis for Proposed Change no flow. The overtemperature!::.T and control room ventilation isolation instrumentation continue to initiate a reactor trip and control room ventilation isolation, respectively; both systems are important to safety.
GDC 21: Protection system reliability and testability. The proposed amendment does not alter the design of any protection system, including the RTS and control room ventilation isolation instrumentation. Therefore, the protection system design continues to provide high functional reliability and inservice testability commensurate with the safety functions to be performed and continues to be sufficient to assure that (1) no single failure results in loss of the protection function, and (2) removal from service of any component or channel does not result in loss of the required minimum redundancy.
This change does not impact the RTS or control room ventilation isolation instrumentation design; thus, the design of these instrumentation systems continues to permit periodic testing of their funtionality when the reactor is in operation as previously licensed and approved by the NRC.
GDC 29: Protection against anticipated operational occurrences. The proposed amendment does not alter the design of any protection or reactivity control system, including the RTS and control room ventilation isolation instrumentation. Therefore, the protection and reactivity control system design continues to assure an extremely high probability of accomplishing their safety functions in the event of anticipated operational occurrences to the extent previously licensed and approved by the NRC.
4.2 Precedent None identified.
4.3 No Significant Hazards Consideration Determination Analysis Pursuant to 10 CFR 50.90, Southern Nuclear Operating Company (SNC) hereby requests an amendment to Joseph M. Farley Nuclear Plant (FNP) Unit 1 renewed facility operating license NPF-2 and Unit 2 renewed facility operating license NPF-8. The proposed amendment revises technical specification (TS) 3.3.1 , "Reactor Trip System (RTS)
Instrumentation," by deleting the unit "RTP" (rated thermal power) from the 3% deviation adjustment criterion associated with the overtemperature !::. T trip since the correct unit is
%of absolute deviation, not% of RTP. The proposed amendment also revises TS 3.3.7, "Control Room Emergency Filtration/Pressurization System (CREFS) Actuation Instrumentation," to change the control room ventilation radiation isolation trip setpoint in units of counts per minute (cpm) to an equivalent setpoint in units of microcuries per cubic centimeter (IJCi/cc) with a clarifying note that the value is that above background radiation level with no flow. The changes are considered administrative in nature with no technical impact.
SNC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92 ,
"Issuance of amendment," as discussed below:
E-6
Enclosure to NL-19-0331 Basis for Proposed Change (1) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed amendment does not affect accident initiators or precursors nor adversely alter the design assumptions, conditions, and configuration of the facility.
The proposed amendment does not alter any plant equipment or operating practices with respect to such initiators or precursors in a manner that the probability of an accident is increased.
The proposed amendment represents an administrative change and does not involve a physical change to the RTS or the CREFS actuation instrumentation, nor does it change the safety function of the instrumentation or the equipment supported by the instrumentation. The change deletes an incorrect unit of measure from the adjustment criterion associated with the overtemperature 1:::.T reactor trip and revises the measurement units of CREFS control room ventilation high radiation isolation trip setpoint with an equivalent value and a clarifying note that the value is that above background level with no flow. As a result, the proposed amendment does not alter assumptions relative to the mitigation of an accident or transient event, and therefore, the consequences of an accident are not changed.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No With respect to a new or different kind of accident, there are no proposed design changes to the RTS; nor are there any changes in the method by which safety related plant structures, systems, and components (SSCs) perform their specified safety functions. The proposed amendment will not affect the normal method of plant operation or revise any operating parameters. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced as a result of this proposed change and the failure modes and effects analyses of SSCs important to safety are not altered as a result of this proposed administrative change. The change deletes an incorrect unit of measure from the adjustment criterion associated with the overtemperature 1:::. T reactor trip and revises the measurement units of CREFS control room ventilation high radiation isolation trip setpoint with an equivalent value and a clarifying note that the value is that above background level with no flow.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated .
E-7
Enclosure to NL-19-0331 Basis for Proposed Change (3) Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No The margin of safety is related to the ability of the fission product barriers to perform their design functions during and following an accident. These barriers include the fuel cladding , the reactor coolant system, and the containment. The performance of these fission product barriers is not affected by the proposed change.
Instrumentation safety margin is established by ensuring the limiting safety system settings automatically actuate the applicable design function to correct an abnormal situation before a safety limit is exceeded. Safety analysis limits are established for RTS instrumentation functions related to those variables having significant safety functions.
The overtemperature 11T reactor trip function and the control room ventilation high radiation isolation function are not altered as a result of the proposed administrative change. The change deletes an incorrect unit of measure from the adjustment criterion associated with the overtemperature 11T reactor trip and revises the measurement units of the control room ventilation high radiation isolation trip setpoint with an equivalent value and a clarifying note that the value is that above background level with no flow.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, SNC concludes that the proposed change presents no 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.
4.4 Conclusion 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. ENVIRONMENTAL CONSIDERATION SNC has determined that the proposed change does not modify requirements with respect to installation or use of facility components located within the restricted area, as defined in 10 CFR 20, and does not change an inspection or surveillance requirement. The proposed change 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 individual or cumulative occupational E-8
Enclosure to NL-19-0331 Basis for Proposed Change radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22(c)(9). Therefore, pursuant to 10 CFR 51.22(b}, no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
- 6. REFERENCES
- 1. NRC NUREG-1431 , "Standard Technical Specifications- Westinghouse Plants, Volume 1 Specifications," Revision 4.0 (NRC Agencywide Documents Access and Management System (ADAMS) Accession No. ML12100A222).
- 2. Letter from S. A. Williams (NRC) to C. R. Pierce (SNC} , "Joseph M. Farley Nuclear Plant, Units 1 and 2- Issuance of Amendments Adopting 21 Previously NRC-approved TSTF Travelers and One Request Not Associated with TSTF Travelers (CAC Nos.
MF5317 and MF5318)," dated August 3, 2016 (NRC ADAMS Accession No. ML15233A448).
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Joseph M. Farley Nuclear Plant- Units 1 and 2 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 Attachment 1 Technical Specification Marked-up Pages
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS
---------------------------- -NOTE------------------------- ----- ---------------------
Refer to Table 3.3.1 -1 to determine which SRs apply for each RTS Function.
SURVEILLANCE FREQUENCY SR 3.3.1.1 ---------------------- ----NOTE--------------------------
Not required to be performed for source range instrumentation until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is< P-6 .
Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2 - ---------- --------------NOTE------------ -------------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is~ 15% RTP.
Compare results of calorimetric heat balance In accordance with calculation to power range channel output. Adjust the Surveillance power range channel output if calorimetric heat Frequency Control balance calculation results exceed power range Program channel output by more than +2% RTP.
SR 3.3.1.3 -------- ------- -----NOTES-----------------------------
- 1. Not required to be performed until7 days after THERMAL POWER is~ 50% RTP.
- 2. Performance of SR 3.3.1.9 satisfies this SR.
Compare results of the in core detector In accordance with measurements to Nuclear Instrumentation System the Surveillance (NIS) AFD. Adjust NIS channel if absolute difference Frequency Control is ~ 3%--R-+P. Program Farley Units 1 and 2 3.3.1-9 Amendment No. 2-W (Unit 1)
Amendment No. 4-W (Unit 2)
CREFS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)
CREFS Actuation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP SETPOINT MODES OR OTHER CHANNELS REQUIREMENTS SPECIFIED CONDITIONS
- 1. Manual Initiation 1,2,3,4, (a), (b) 2trains SR 3.3.7.6 NA
- 2. Automatic Actuation Logic 1,2,3,4 2trains SR 3.3.7.3 NA and Actuation Relays SR 3.3.7.4 SR 3.3.7.5
- 3. Control Room Radiation 1,2,3,4 SR 3.3.7.1 s ~ 1 . ox1o* 5 Control Room Air Intake (a) , (b) 2 SR 3.3.7.2 uCilcc (c)
(R-35A, B) SR 3.3.7.7
- 4. Containment Isolation - Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and Phase A requirements.
(a) During CORE ALTERATIONS.
(b) During movement of irradiated fuel assemblies.
(c) Above background with no flow.
Farley Units 1 and 2 3.3.7-4 Amendment No. 449 (Unit 1)
Amendment No. J+. (Unit 2)
Joseph M. Farley Nuclear Plant - Units 1 and 2 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 Attachment 2 Revised (Clean) Technical Specification Pages
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------------------------
Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.
SURVEILLANCE FREQUENCY SR 3.3.1.1 -----------------------NOTE-------------------------
Not required to be performed for source range instrumentation until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is< P-6.
Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2 -------------------------N 0TE--------------------------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is~ 15% RTP.
Compare results of calorimetric heat balance In accordance with calculation to power range channel output. Adjust the Surveillance power range channel output if calorimetric heat Frequency Control balance calculation results exceed power range Program channel output by more than +2% RTP.
SR 3.3.1.3 ---------------------------N0 TE S----------------------------
- 1. Not required to be performed until 7 days after THERMAL POWER is ;::: 50% RTP.
- 2. Performance of SR 3.3.1.9 satisfies this SR.
Compare results of the in core detector In accordance with measurements to Nuclear Instrumentation System the Surveillance (NIS) AFD. Adjust NIS channel if absolute difference Frequency Control is~ 3%. Program Farley Units 1 and 2 3.3.1-9 Amendment No. (Unit 1)
Amendment No. (Unit 2)
CREFS Actuation Instrumentation 3.3.7 Table 3.3 .7-1 (page 1 of 1)
CREFS Actuation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP SETPOINT MODES OR OTHER CHANNELS REQUIREMENTS SPECIFIED CONDITIONS
- 1. Manual Initiation 1,2,3,4, (a), (b) 2 trains SR 3.3.7.6 NA
- 2. Automatic Actuation Logic 1,2,3,4 2 trains SR 3.3.7.3 NA and Actuation Relays SR 3.3.7.4 SR 3.3.7.5
- 1.0 X 1o* 1-JCi/cc (c) 5
- 3. Control Room Radiation 1,2,3,4 1 SR 3.3.7.1 Control Room Air Intake (a), (b) 2 SR 3.3.7.2 (R-35A, B) SR 3.3.7.7
- 4. Containment Isolation- Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and Phase A requirements.
(a) During CORE ALTERATIONS.
(b) During movement of irradiated fuel assemblies.
(c) Above background with no flow.
Farley Units 1 and 2 3.3.7-4 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Joseph M. Farley Nuclear Plant - Units 1 and 2 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 Attachment 3 Technical Specification Bases Marked-up Pages (for information only)
RTS Instrumentation B 3.3.1 BASES SURVEILLANCE SR 3.3.1.2 (continued)
REQUIREMENTS SR 3.3.1.2 is modified by a Note. This Note clarifies that this Surveillance is required only if reactor power is ~ 15% RTP and that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are allowed for performing the first Surveillance after reaching 15% RTP. A power level of 15% RTP is chosen based on plant stability, i.e., automatic rod control capability and turbine generator synchronized to the grid.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.3.1.3 SR 3.3.1.3 compares the incore system to the NIS channel output. If the absolute difference is~ 3% ~the NIS channel is still OPERABLE, but it must be adjusted. The excore NIS channel shall be adjusted if the absolute difference between the incore and excore AFD is~3%~ .
If the NIS channel cannot be properly adjusted, the channel is declared inoperable. This Surveillance is performed to periodically verify the f(ill) input to the overtemperature .llT Function.
Two Notes modify SR 3.3.1.3. Note 1 clarifies that the Surveillance is required only if reactor power is ~ 50% RTP and that 7 days are allowed for performing the Surveillance and channel adjustment, if necessary, after reaching 50% RTP. A power level of~ 50% RTP is consistent with the requirements of SR 3.3.1.9. Note 2 allows SR 3.3.1.9 to be performed in lieu of SR 3.3.1.3, since SR 3.3.1.9 calibrates (i.e.,
requires channel adjustment) the excore channels to the incore channels, it envelopes the performance of SR 3.3.1.3.
For each operating cycle, the initial channel normalization is performed under SR 3.3.1.9. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.3.1.4 SR 3.3.1.4 is the performance of a TADOT. This test shall verify OPERABILITY by actuation of the end devices.
The RTB test shall include separate verification of the undervoltage trip via the Reactor Protection System and the local manual shunt trip (continued)
Farley Units 1 and 2 B 3.3.1-52 Revision ++
CREFS Actuation Instrumentation B 3.3.7 BASES LCO 2. Automatic Actuation Logic and Actuation Relays (continued)
The LCO requires two trains of Actuation Logic and Relays OPERABLE to ensure that no single random failure can prevent automatic actuation.
Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for ESFAS Function 3.a.2, Containment Isolation-Phase A, in LCO 3.3.2. The Actions Conditions for the CREFS portion of these Functions are different and less restrictive than those specified for their Phase A Isolation roles. If one or more of the Phase A Isolation Functions becomes inoperable in such a manner that only the CREFS Function is affected, the Conditions applicable to their Phase A Isolation Function need not be entered . The less restrictive Actions specified for inoperability of the CREFS Functions specify sufficient compensatory measures for this case.
- 3. Control Room Radiation The LCO specifies one required Control Room Air Intake Radiation Monitor in MODES 1-4 to ensure that the radiation monitoring instrumentation necessary to provide a backup initiation of control room isolation remains OPERABLE. The LCO requires two air intake radiation monitor channels OPERABLE during CORE ALTERATIONS and during movement of irradiated fuel assemblies when the radiation monitor channels provide the primary control room protection function.
For sampling systems, channel OPERABILITY involves more than OPERABILITY of channel electronics. OPERABILITY also requires correct valve lineups and sample pump operation , as well as detector OPERABILITY.The setpoint is based upon a release during a fuel handling accident in which Krvpton-85 and Xenon-133 are the predominant radionuclides. Derived air concentration (DAC) limits are listed in Table 1, Column 3 of Appendix B to 10 CFR 20 (Reference 1). The trip setpoint ensures control room ventilation intake isolation occurs well before the intake concentration reaches the 10 CFR 20 occupational limit, which is consistent with the GDC 19 and 10 CFR 50 .67(b)(2){iii) dose limit for control room personnel (References 2 and 3).
Footnote (c) clarifies that the trip setpoint value is that value above the normal background radiation level with no adjustment for flow in the system.
(continued)
Farley Units 1 and 2 B 3.3.7-3 Revision G
CREFS Actuation Instrumentation B 3.3.7 BASES LCO 4. Containment Isolation-Phase A (continued)
Refer to LCO 3.3.2, Function 3.a, for all initiating Functions and requirements except as described above in item 2, "Automatic Actuation Logic and Actuation Relays."
APPLICABILITY The CREFS Functions must be OPERABLE in MODES 1, 2, 3, 4, and the radiation monitor and manual initiation Functions must also be OPERABLE during CORE ALTERATIONS and movement of irradiated fuel assemblies to ensure a habitable environment for the control room operators. The Applicability for the CREFS actuation on the ESFAS Containment Isolation-Phase A Functions are specified in LCO 3.3.2. Refer to the Bases for LCO 3.3.2 for discussion of the Containment Isolation-Phase A Function Applicability.
ACTIONS The most common cause of channel inoperability is outright failure or drift of the bistable or process module sufficient to exceed the tolerance allowed by the unit specific calibration procedures.
Typically, the drift is found to be small and results in a delay of actuation rather than a total loss of function. This determination is generally made during the performance of a COT, when the process instrumentation is set up for adjustment to bring it within specification.
If the Trip Setpoint is less conservative than the tolerance specified by the calibration procedure, the channel must be declared inoperable immediately and the appropriate Condition entered .
A Note has been added to the ACTIONS indicating that separate Condition entry is allowed for each Function. The Conditions of this Specification may be entered independently for each Function listed in Table 3.3.7-1 in the accompanying LCO. The Completion Time(s) of the inoperable channel(s)/train(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.
Condition A applies to the actuation logic train Function of the CREFS, the radiation monitor channel Functions, and the manual channel Functions.
If one train is inoperable, or one required radiation monitor channel is inoperable in one or more Functions, 7 days are permitted to restore it to OPERABLE status. The 7 day Completion Time is the same as is allowed if one train of the mechanical portion of the system is inoperable. The basis for this Completion Time is the same as provided in LCO 3.7.10. If the channel/train cannot be restored to (continued)
Farley Units 1 and 2 B 3.3.7-4 Revision 4-8
CREFS Actuation Instrumentation B 3.3.7 BASES ACTIONS A.1 (continued)
OPERABLE status, one CREFS train must be placed in the emergency recirculation mode of operation. This accomplishes the actuation instrumentation Function and places the unit in a conservative mode of operation.
B.1.1 . B.1.2. and B.2 Condition B applies to the failure of two CREFS actuation trains, two required radiation monitor channels, or two manual initiation trains.
The first Required Action is to place one CREFS train in the emergency recirculation mode of operation immediately. This accomplishes the actuation instrumentation Function that may have been lost and places the unit in a conservative mode of operation.
The applicable Conditions and Required Actions of LCO 3.7.10 must also be entered for the CREFS train made inoperable by the inoperable actuation instrumentation. In the case of inoperable radiation monitors, one train of CREFS must be declared inoperable and the applicable Condition of LCO 3.7.10 entered . This ensures appropriate limits are placed upon train inoperability as discussed in the Bases for LCO 3.7.10.
Alternatively, both trains may be placed in the emergency recirculation mode. This ensures the CREFS function is performed even in the presence of a single failure.
C.1 and C.2 Condition C applies when the Required Action and associated Completion Time for Condition A or B have not been met and the unit is in MODE 1, 2, 3, or 4. Condition C is only applicable to those CREFS functions in Table 3.3.7-1 required OPERABLE in MODES 1-4. The unit must be brought to a MODE in which overall plant risk is reduced. To achieve this status, the unit must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Remaining within the applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 1). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference ~. the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4.
(continued)
Farley Units 1 and 2 B 3.3.7-5 Revision ~
CREFS Actuation Instrumentation B 3.3.7 BASES SURVEILLANCE SR 3.3.7.7 REQUIREMENTS (continued) The CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
REFERENCES 1. 10 CFR 20. Appendix B - Annual Limits on Intake (Alls) and Derived Air Concentrations <DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations: Concentrations for Release to Sewerage.
- 2. 10 CFR 50. Appendix A - General Design Criteria for Nuclear Power Plants.
- 3. 10 CFR 50.67, Accident source term.
4._
_ WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.
Farley Units 1 and 2 B 3.3.7-9 Revision ~