|
---|
Category:Letter type:NL
MONTHYEARNL-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-23-0716, 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-23-0713, 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-23-0704, 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 NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only 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-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0884, Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-1012022-11-17017 November 2022 Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-101 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-22-0756, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02022-09-30030 September 2022 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 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-22-0608, Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers2022-08-17017 August 2022 Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers NL-22-0552, Inservice Inspection Program Owner'S Activity Report for Outage 2R282022-07-28028 July 2022 Inservice Inspection Program Owner'S Activity Report for Outage 2R28 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical2022-05-10010 May 2022 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 2024-01-11
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNL-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 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 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-15-2310, Supplemental License Amendment Request to Revise Existing Facility Operating License Commitments Regarding NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plant2016-04-25025 April 2016 Supplemental License Amendment Request to Revise Existing Facility Operating License Commitments Regarding NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plant 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 ML16071A1872016-03-0303 March 2016 Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 6 of 8 ML16071A1322016-03-0303 March 2016 Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 2 of 4 ML16071A1502016-03-0303 March 2016 Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 6 ML16071A1742016-03-0303 March 2016 Enclosure 5: Vogtle Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 4 of 4 2023-08-22
[Table view] |
Text
Mark J. Ajluni, P.E. Soutbem Nuclear Nuclear Lice nsing Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 SOUTHERN ' \
December 21, 2012 COMPANY Docket Nos.: 50-348 NL-12-2142 50-364 U. S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Facility Operating License Amendment Request for Degraded Voltage Protection Modification Schedule Ladies and Gentlemen:
In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Southern Nuclear Operating Company (SNC) proposes to revise the Farley Nuclear Plant (FNP) Unit 1 and Unit 2 Facility Operating Licenses (FOL), NPF-2 and NPF-8.
On December 19, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued an NRC Component Design Bases Inspection (CDBI) Report to FNP (Reference 1 of Enclosure 1). The report included details of an Unresolved Item (URI 2011010-10, "Administrative Controls in lieu of Automatic Actions for Degraded Voltage Protection") regarding the licensee's use of administrative controls in lieu of automatic degraded voltage protection to assure adequate voltage to safety related equipment during design basis events. Based on this URI, a design modification will be implemented to remove dependence on manual operator action. The proposed FOL amendment would incorporate the Degraded Voltage Protection modification scheduled completion dates.
This FOl change is also a result of discussions between SNC and the NRC staff concerning the degraded voltage protection scheme at Plant Hatch and the use of administrative controls for degraded conditions, since FNP has a similar issue.
This FOl change documents SNC's commitment to redesign the current degraded voltage protection scheme to eliminate the use of administrative controls at FNP.
A discussion of the proposed FOl change, the basis for the change, and Significant Hazards Considerations are provided in Enclosure 1. Enclosures 2 and 3 provide the marked up FOl and clean typed pages of the FOl, respectively, for FNP. SNC has evaluated the proposed FOl change and has
u.s. Nuclear Regulatory Commission NL-12-2142 Page 2 determined that it does not involve a significant hazards consideration as defined in 10 CFR 50.92.
In accordance with 10 CFR 50.91, SNC is notifying the State of Alabama of this License Amendment Request by transmitting a copy of this letter and enclosures to the designated State Official.
SNC requests approval of the proposed license amendments by June 30, 2013.
The proposed changes will be implemented within 60 days of issuance of the amendment.
Mr. M. J. Ajluni states he is Nuclear Licensing Director of SNC, is authorized to execute this oath on behalf of SNC 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 contact Doug McKinney at (205) 992-5982.
Respectfully submitted, ~....
M. J. Ajluni Nuclear Licensing Director
\ Notary Public My commission expires: 11- z. -z 0 13 MJAlJMC
Enclosures:
- 1. Basis for Proposed Changes
- 2. FNP Facility Operating License Markup Pages
- 3. FNP Facility Operating License Clean Typed Pages cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. A. Lynch, Vice President - Farley Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RTYPE: CFA04.054
U.S. Nuclear Regulatory Commission NL-1 3
Mr. V. M. McCree, Regional Administrator Ms. E. A. Brown, NRR Project Manager - Farley Mr. J. R. Sowa, Resident Inspector - Farley Mr. P.K. Niebaum, Senior Resident Inspector Farley
Joseph M. Farley Nuclear Plant, Units 1 and 2 Facility Operating License Amendment Request for Degraded Voltage Protection Modification Schedule Enclosure 1 Basis for Proposed Changes to Nl-12-2142 Basis for Proposed Changes
- 1. Summary Description This evaluation supports a to amend Facility Operating Licenses, NPF-2 and NPF-8, for Joseph M. Farley Nuclear Plant (FI\IP) Unit 1 and Unit 2, respectively.
The proposed License Amendment Request (LAR) would revise the FNP Facility Operating Licenses (FOL), Appendix C, to Southern Nuclear Operating Company (SNC) to fully implement and maintain in effect Degraded Voltage Protection modification schedule.
- 2. Detailed Description This LAR includes a proposed change to to implement a Degraded Voltage Protection modification. a Nuclear Regulatory Commission (NRC)
Component Design Basis Inspection (CDBI) report on December 1 2011 (Reference 1), FNP received an Unresolved Item regarding the use of administrative controls in lieu of automatic degraded voltage protection to assure adequate voltage to safety-related equipment during design basis events.
SNC's project plan includes proposed modifications to Degraded Voltage (DVRs), possible replacement of the Loss of Offsite Power (LOSP) relays, and installation of new cabinets to house the relays. The modifications will ensure sufficient voltage is available to ensure safety-related loads will remain operable during a degraded voltage condition. A proposed schedule for implementation of the Degraded Voltage Protection modifications is provided in the Technical Evaluation SNC to NRC letter dated September 28, 2012 provided a modification schedule and stated a request change would be submitted by December 31,201 This change to FNP FOLs will ensure modifications are completed, as scheduled, in a timely and efficient manner.
- 3. Technical Evaluation Successful operation of the required functions of the Safety Features (ESF) is dependent upon the availability of adequate power sources for energizing the various components such as pump motors, motor operated valves, and associated control components. Offsite power is the preferred source of power for the 4160V emergency buses which power the required components. The Loss of Power (LOP) protection instrumentation monitors voltage on the F and G 4160V buses. Each electrical train has independent LOP instrumentation and relay actuation logic for detecting degraded grid or loss of voltage conditions, and initiating an LOP emergency diesel generator (EDG) start signal.
There are three LOP protection instrumentation actuation levels. An alarm sounds at a set point that is no less than 3850V, on detection of degraded voltage. At no than 3675V a LOP signal is generated for sustained degraded grid voltage. At no less than 3255V a LOP signal is generated for near instantaneous loss of voltage conditions.
Actuation of the degraded grid or of voltage will automatically disconnect the 4160V emergency from the offsite power source.
E1 -1 to NL-12-2142 Basis for Proposed Changes An administrative limit is established at a voltage level between the degraded grid voltage alarm allowable value and the automatic degraded grid voltage actuation upper allowable value. In the voltage range between the administrative limit and the degraded grid voltage actuation trip setpoint, a few ESF components may not have automatic protection from inadequate voltage. The manual actions provide the primary means of protecting these few ESF components from a sustained, slightly low voltage condition and all components from unnecessary automatic disconnection from the preferred offsite power source.
Based on an Unresolved Item from an NRC CDBI report, FNP's current Degraded Voltage Protection System requires upgrades because the system currently relies upon administrative controls to assure adequate voltage to safety-related equipment during design basis events. FNP automatic degraded voltage protection scheme employs automatic setpoints that are too low to assure operability of all safety-related electrical equipment in case of a sustained degraded grid voltage condition and instead relies on administrative controls to assure adequate voltage to safety-related equipment during an accident.
The electrical distribution system for each unit is capable of providing sufficient margin between the minimum expected bus voltage and the voltage level required by the loads, but will require a new DVR set point. The design of the existing DVRs does not allow resolution of this issue through set point adjustment.
The proposed modifications include replacement of DVRs, replacement of the LOSP relays, and installation of new cabinets to house the relays. This project will ensure sufficient voltage is available to ensure safety-related loads will remain operable during a degraded voltage condition.
Work scope and schedule are as follows:
2013 January Planning Starts 2013 July Design Starts 2015 January Complete Design and Begin Implementation Preparation 2015 January Submit Technical Specification Amendments 2016 January Issuance of Technical Specification -Amendments 2016 U2R24 U2 Spring Outage - Unit 2 Design Implementation Starts 2016 U1 R27 U1 Fall Outage - Unit 1 Design Implementation Starts 2017 U2R25 U2 Fall Outage - Unit 2 Completion 2018 U1 R28 U1 Spring Outage - Unit 1 Completion The implementation schedule above is slightly different from the schedule provided in the SNC letter to the NRC dated September 28,2012 due to further fine-tuning of the plan; however, the completion dates have not changed. This schedule allows time for detailed design completion and time to develop the engineering basis for the technical specification (TS) amendment request. This timeframe also accounts for coordination of outage activities. Two outages are necessary to complete the modifications on each unit based on FNP's philosophy that limits electrical modifications to one electrical train per outage. Non critical path work activities performed at power are not included in the above schedule.
The implementation schedule and proposed completion dates do not pose a threat to safety due to current administrative controls that will remain in place until the completion of the modifications and TS amendments occur.
E1 -2 to NL-12-2142 Basis for Proposed Changes This lAR includes the proposed change to FNP FOls, Appendix C. A marked up copy of FNP FOls reflecting the proposed changes are provided in Enclosure 2. A clean typed copy of FNP FOls with changes incorporated is provided in Enclosure 3.
- 4. Regulatory Evaluation 4.1 No Significant Hazards Consideration Determination Southern Nuclear Operating Company (SNC) is requesting an amendment to the Farley Nuclear Plant (FNP) Facility Operating Licenses (FOl), Appendix C, to include a Degraded Voltage Protection modification schedule. This modification is in response to an NRC Unresolved Item regarding the use of administrative controls in lieu of automatic degraded voltage protection to assure adequate voltage to safety related equipment during design basis events.
SNC has evaluated whether 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:
- 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 the FNP FOl that incorporates the Degraded Voltage Protection modification implementation schedule is administrative in nature. This proposed change does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested or inspected.
Therefore, this 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.
The proposed change to the FNP FOl that incorporates the Degraded Voltage Protection modification implementation schedule is administrative in nature. This proposed change does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested or inspected.
Therefore, this proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
E1 -3 to NL-12-2142 Basis for Proposed Changes
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
Plant safety margins are established through limiting conditions for operation, limiting safety system settings, and safety limits specified in the technical specifications. The proposed change to the FNP FOL is administrative in nature.
Because there is no change to these established safety margins as a result of this change, the proposed change does not involve a significant reduction in a margin of safety.
Therefore, the proposed change does not involve a significant reduction in 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.
4.2 Applicable Regulatory Requirements/Criteria This license amendment request is submitted to ensure compliance with applicable provisions of 10 CFR 50.55a(h)(2) and 10 CFR Part 50, Appendix A, General Design Criterion 17 - Electric Power Systems.
4.3 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the NRC'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 Considerations SNC has evaluated the proposed amendment and determined that the amendment does not involve (1) a significant hazards consideration, (2) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (3) 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 the 10 CFR 51.22(b), an environmental assessment of the proposed amendment is not required.
- 6. References
- 1. Letter from Rebecca Nease, U.S. Nuclear Regulatory Commission, to T.A. Lynch, SNC Farley Nuclear Plant, "Joseph M. Farley Nuclear Plant, NRC Component Design Bases E1-4 to NL-12-2142 Basis for Proposed Changes Inspection - Inspection Report 05000348/2011010 and 05000364/2011010," dated December 19, 2011.
- 2. Letter from M.J. Ajluni, SNC, to NRC, "Joseph M. Farley Nuclear Plant - Units 1 and 2 Administrative Controls in Lieu of Automatic Actions for Degraded Grid Protection Implementation Schedule," dated September 28, 2012.
E1 -5
Joseph M. Farley Nuclear Plant, Units 1 and 2 Facility Operating License Amendment Request for Degraded Voltage Protection Modification Schedule Enclosure 2 FNP Facility Operating License Markup Pages
APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-2 Amendment Condition Completion Number Additional Condition Date 146 The schedule for performing new and revised Concurrent with Surveillance Requirements (SRs) shall be as the implementation of follows: the Improved Technical
- 1. For SRs that are new in this amendment Specifications.
the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
- 2. For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
SNC shall implement the
- 3. For SRs that existed prior to this Degraded Voltage modifications to amendment that have modified eliminate the manual actions in acceptance criteria, the first performance lieu of automatic degraded voltage is due at the end of the first surveillance protection to assure adequate interval that began on the date the voltage to safety-related surveillance was last performed prior to equipment during design basis the implementation of this amendment.
events.
- 4. For SRs that existed prior to this amendment whose intervals of Unit 1 2018 Spring performance are being extended, the first Outage, U1 R28 extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.
-2 Amendment No. +4e
APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-8 Amendment Condition Completion Number Additional Condition Date 137 The schedule for performing new and revised Concurrent with the Surveillance Requirements (SRs) shall be as implementation of follows: the Improved Technical
- 1. For SRs that are new in this amendment Specifications.
the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
- 2. For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment. SNC shall implement the Degraded Voltage modifications to
- 3. For SRs that existed prior to this eliminate the manual actions in amendment that have modified lieu of automatic degraded voltage acceptance criteria, the first performance protection to assure adequate is due at the end of the first surveillance voltage to safety-related interval that began on the date the equipment during design basis surveillance was last performed prior to the implementation of this amendment. events.
- 4. For SRs that existed prior to this amendment whose intervals of performance are being extended, the first Unit 2 2017 Fall extended surveillance interval begins Outage, U2R25 upon completion of the last surveillance performed prior to implementation of this amendment.
Amendment No. +37
Joseph M. Farley Nuclear Plant, Units 1 and 2 Facility Operating License Amendment Request for Degraded Voltage Protection Modification Schedule Enclosure 3 FNP Facility Operating License Clean Typed Pages
APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-2 Amendment Condition Completion I\lumber Additional Condition Date 146 The schedule for performing new and revised Concu rrent with Surveillance Requirements (SRs) shall be as the implementation of follows: the Improved Technical
- 1. For SRs that are new in this amendment the Specifications.
first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
- 2. For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
- 3. For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
- 4. For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.
SNC shall implement the Degraded Voltage Unit 1 2018 Spring modifications to eliminate the manual actions in Outage, U1 R28 lieu of automatic degraded voltage protection to assure adequate voltage to safety-related equipment during design basis events.
-2 Amendment No.
APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-8 Amendment Condition Completion Number Additional Condition Date 137 The schedule for performing new and revised Concurrent with the Surveillance Requirements (SRs) shall be as implementation of follows: the Improved Technical
- 1. For SRs that are new in this amendment Specifications.
the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
- 2. For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
- 3. For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
- 4. For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.
SNC shall implement the Degraded Voltage Unit 2 2017 Fall modifications to eliminate the manual actions in Outage, U2R25 lieu of automatic degraded voltage protection to assure adequate voltage to safety-related equipment during design basis events.
Amendment No.