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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] Category:Technical Specifications
MONTHYEARML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves NL-22-0091, Correction of Technical Specification Typographical Omission2022-02-24024 February 2022 Correction of Technical Specification Typographical Omission ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML20303A1192020-12-11011 December 2020 Issuance of Amendment Nos. 232 and 229 Regarding Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19071A1382019-07-16016 July 2019 Issuance of Amendments 223 and 220 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations TSTF-51 and TSTF-471 ML18151A1742018-06-27027 June 2018 Issuance of Amendment Nos. 219 and 216, Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable ML17333A0792017-12-0606 December 2017 Reissue of Corrected Technical Specification Page 3.6.6-3 NL-17-1974, Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package2017-11-21021 November 2017 Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package NL-17-1067, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-06-0808 June 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request ML17034A1932017-02-16016 February 2017 Issuance of Amendments to Adopt TSTF-427 Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML16232A0002016-10-17017 October 2016 Issuance of Amendments Related to NFPA-805 Supplement ML16272A1892016-10-0303 October 2016 Correction to Amendment Nos. 203 (Unit 1) and 199 (Unit 2) ML15289A2272016-06-10010 June 2016 Issuance of Amendments Related to TSTF-432-A, Revision 1 ML16083A2652016-05-17017 May 2016 Issuance of Amendments to Revise Technical Specification 3.4.14 NL-16-0034, License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding2016-03-16016 March 2016 License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding NL-15-1956, Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions2016-03-14014 March 2016 Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions NL-15-2062, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 22015-11-25025 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 2 NL-15-0722, Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request2015-11-20020 November 2015 Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request ML15180A3342015-08-0303 August 2015 Issuance of Amendments ML15083A0982015-06-0202 June 2015 Issuance of Amendments (TAC Nos. MF4828, MF4829, MF4889, and MF4890) ML14308A0482015-03-10010 March 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) NL-15-0188, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52015-02-13013 February 2015 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 NL-14-0115, Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52014-09-17017 September 2014 Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 ML14155A3022014-08-15015 August 2014 Issuance of Amendment Regarding Minimum Condensate Storage Tank Level Technical Specifications ML14069A3442014-05-13013 May 2014 Issuance of Amendments to Incorporate the Schedule for Degraded Grid Voltage Modification NL-12-0867, License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank2012-08-20020 August 2012 License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank NL-12-0868, Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report2012-08-15015 August 2012 Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report NL-12-1226, License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report2012-08-14014 August 2012 License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report NL-12-1552, Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating2012-07-23023 July 2012 Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating NL-12-0403, Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST)2012-02-28028 February 2012 Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST) NL-11-0299, Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.42012-01-18018 January 2012 Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.4 NL-10-0272, License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated..2010-10-29029 October 2010 License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated.. NL-09-1676, Request to Revise Technical Specification 3.7.8, Service Water System (Sws).2009-10-21021 October 2009 Request to Revise Technical Specification 3.7.8, Service Water System (Sws). NL-09-1622, Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (Sws).2009-10-0808 October 2009 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (Sws). NL-09-1861, License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report2009-09-15015 September 2009 License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report ML0917706642009-09-0404 September 2009 Southern Nuclear Operating Company Plants, License Amendments, Regarding Elimination of Working Hour Restrictions from Technical Specifications ML0827300082008-09-29029 September 2008 Tech Spec Pages for Amendment Nos. 178 and 171 Revised TS for Limiting Condition for Operation 3.9.3, Containment Penetrations. NL-08-0832, Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications.2008-06-12012 June 2008 Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications. ML0818202472008-05-23023 May 2008 Updated Final Safety Analysis Report, Revision 21, Technical Specifications Bases NL-06-2801, Technical Specification Amendment Request, Containment Leakage Rate Testing Program2007-11-0505 November 2007 Technical Specification Amendment Request, Containment Leakage Rate Testing Program NL-07-1079, Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization2007-07-17017 July 2007 Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization ML0719804822007-07-16016 July 2007 Tech Spec Pages for Amendments 175 and 168 Regarding Technical Specification Changes to Reflect Change in Organizational Structure 2023-08-24
[Table view] |
Text
Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Alabama 35201-1295 Te 205.992.5000 SOUTHERN'\
COMPANY October 8, 2009 Energy to SenJi:' Vimr World' Docket Nos.: 50-364 NL-09-1622 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Unit 2 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, "Service Water System (SWS)"
Ladies and Gentlemen:
Pursuant to 10 CFR 50.90 and 10 CFR 50.91 (a)(5), Southern Nuclear Operating Company (SNC), hereby requests an emergency amendment to Joseph M.
Farley Nuclear Plant (FNP) Unit 2 Technical Specifications (TS). The proposed one-time change to the TS contained herein revises Limiting Condition for Operation (LCO) 3.7.8, "Service Water System (SWS)," Action A Completion Time from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to a one-time 6-day Completion Time to allow replacement of two of the FNP Unit 2 SWS Train A seismic support ring assemblies. The proposed change is applicable to Unit 2 only. The Train A pumps were removed from service on October 6, 2009, at 0818 CST hours, to perform inspection of the seismic support ring assemblies. During the inspection, it was noted that the pumps' seismic support ring assemblies were in an unsatisfactory condition, caused by loose mounting bolts. Disassembly and replacement of these underwater seismic support ring assemblies involve a number of major steps, including diver coordination and fabrication of replacement seismic support rings and mounting plates. Although the FNP plant staff had foreseen the need for potential repair and/or replacement of the seismic support ring assemblies and had contingences in place to effect repairs as necessary, the extent of the repairs require additional time beyond the 72-hour Completion Time.
A discussion of the proposed Technical Specifications change and the basis for the emergency Technical Specification and Significant Hazards Considerations are provided in Enclosure 1. SNC has evaluated the proposed TS change and has determined that it does not involve a significant hazards consideration as defined in 10 CFR 50.92. The basis for that determination is provided in Enclosure 1. SNC has also determined that operation with the proposed change will not result in a significant increase in the amount of effluents that may be
U. S. Nuclear Regulatory Commission NL-09-1622 Page 2 released offsite nor a significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed change. The basis for that determination is also provided in Enclosure 1. The marked-up and clean typed TS pages are provided in Enclosures 3 and 4, respectively. Enclosure 2 provides Unit 1 and 2 seismic support ring assembly drawings.
To avoid an unnecessary plant shutdown over a seismic qualification issue that has a clear success path for full restoration of qualification, SNC requests that the proposed TS change be reviewed and approved by 0800 CST hours on October 9, 2009. The proposed extended FNP Unit 2 Completion Time wilt expire upon returning the Unit 2 SWS Train A to operable status or on October 12, 2009 at 0818 CST, whichever occurs first.
An inspection witt be performed of FNP Unit 1 SWS seismic support ring assemblies as soon as possible, but no later than November 20, 2009. This inspection schedule will allow time for planning, arrangement for divers, ensure personnel safety, obtain design and material for potential repairs, and to schedule manpower with consideration of 10 CFR 26 requirements.
Mr. M. J. Ajluni states he is Nuclear Licensing Manager of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
This letter contains NRC commitments (see Enclosure 5). If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY M. J. Ajluni Nuclear Licensing Manager
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Sworn to and subscribed before me this ~ day of Qc.:JQ b.tvt. , 2009.
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U. S. Nuclear Regulatory Commission NL-09-1622 Page 3 MJAlTDH/phr : Description of the Proposed Change : Drawings - Unit 1 and Unit 2 Seismic Support Ring Assembly : Marked-Up Technical Specifications Page : Clean Typed Technical Specifications Page : Commitment Table cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R Johnson, Vice President - Farley Ms. P. M. Marino, Vice President - Engineering RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. L A Reyes, Regional Administrator Mr. R E. Martin, NRR Project Manager - Farley Mr. E. L Crowe, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Joseph M. Farley Nuclear Plant Unit 2 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, "Service Water System (SWS)"
Enclosure 1 Description of the Proposed Change
Joseph M. Farley Nuclear Plant Unit 2 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, "Service Water System (SWS)"
Enclosure 1 Description of the Proposed Change Table of Contents 1.0 Introduction
2.0 Background
3.0 Need for Technical Specification Change 4.0 Description of Proposed Change 4.1 Proposed Change
4.2 System Description
4.3 Basis for the Technical Specification Change 5.0 Qualitative Assessment 6.0 Regulatory Safety Analysis 6.1 No Significant Hazards Consideration 6.2 Environmental Assessment 7.0 Conclusion
Enclosure 1 Description of the Proposed Change 1.0 Introduction Pursuant to 10 CFR 50.90 and 10 CFR 50.91(a)(5), Southern Nuclear Operating Company (SNC), hereby requests an emergency amendment to Joseph M. Farley Nuclear Plant (FNP)
Unit 2 Technical Specifications (TS). The proposed change to the TS contained herein revises Limiting Condition for Operation (LCO) 3.7.8, "Service Water System (SWS)," Action A Completion Time from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to a one-time 6-day Completion Time to allow repair/replacement of the FNP Unit 2 SWS Train A seismic support ring assemblies. The proposed change is applicable to Unit 2 only and should be processed as an emergency change to prevent an unscheduled shutdown of FNP Unit 2.
The proposed change qualifies for categorical exclusion from an environmental assessment as set forth in 10 CFR 51.22(c)(9). Therefore, no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed change.
2.0 Background
On August 02, 2009, while swapping SWS pumps (start of 2E/secure of 2C) in preparation for the train swap (Train 8 to Train A), plant personnel heard sounds that resulted in a decision to secure the 2E SWS Pump shortly after being started. As soon as the 2E pump was secured, the sound stopped. Investigation indicated that the seismic support ring assembly for the 2E SWS Pump was no longer capturing the pump column. Inspection of the underwater seismic support ring assembly indicated the lower two of the four wall plate bolts were degraded and missing the nuts. The upper two bolts were degraded but still had nuts. It was determined that if the two remaining wall plate bolts were able to be torqued to 150 ft-Ibs and the vertical bolts that attached the seismic ring to the wall plate were torqued to 250 ft-Ibs, the seismic support ring assembly would be able to perform its design function. All remaining bolting met the torque requirements. A Prompt Determination of Operability was completed to show that the 2E SWS Pump seismic support ring assembly was operable but degraded.
Additional inspections were performed to address extent of condition of the degraded seismic support ring assembly on the 2E SWS Pump and to evaluate the condition of the other Unit 2 assemblies. An inspection on September 29, 2009 revealed that the 2E SWS pump seismic support ring assembly was not in an operable condition and the base plate was replaced. After the 2E SWS plate was replaced, the inspections resumed. Two of the four 20 SWS Pump seismic support ring assembly horizontal wall bolt nuts were found to be loose. After the nuts were torqued, the final inspection result for the 20 pump seismic support ring assernbly was satisfactory. It should be noted that while the unacceptable 2E plate had only two intact bolts/nuts, the acceptable 20 plate had four intact bolts/nuts. As an interim action, until the bolting can be permanently corrected, inspection of the 20 pump seismic support ring assembly bolting will be performed after the Train A repairs and every 30 days. This commitment to perform inspections is included in the Commitment Table (Enclosure 5).
On October 06,2009 at 0818 CST hours, the Unit 2 SWS Train A was removed from service for inspection. The 2C, 28, and 2A SWS Pump seismic support ring assemblies' base plates were found to need replacement due to the inability to establish torque of 150 ft-Ibs on the nuts of the horizontal bolting.
Page 1 of 6
Enclosure 1 Description of the Proposed Change Disassembly and replacement of these underwater seismic support ring assemblies involve a number of major steps, including diver coordination and fabrication of a replacement seismic support ring and mounting plate that could force the maintenance schedule to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The required major steps are listed below:
- 1. Fabrication of a replacement seismic support ring and mounting plate.
- 2. Diver coordination.
- 3. Underwater drilling for new anchor bolting.
- 4. Inspection.
- 5. Release tagout and realign system.
- 6. Verify pump operation.
Although the FNP staff had foreseen the need for potential repair/replacement of the seismic support ring assemblies and had contingences in place to effect repairs as necessary, the extent of the repairs requires additional time beyond the 72-hour Completion Time. Underwater drilling into concrete and the striking of rebar is the chief reason for the additional time. The exact location of the rebar was not known. The Unit 2 Completion Time will expire on October 09,2009 at 0818 CST.
To return the Unit 2 SWS Train A to OPERABLE status, replacement of seismic support ring assemblies must be completed for two of the three pumps. A one-time, 6-day Unit 2 Completion Time for TS 3.7.8, Action A, to allow the SWS Train A to be inoperable is requested to permit the replacement of seismic support ring assemblies and return SWS Train A to service. The proposed extended Completion Time will expire upon returning the SWS Train A to OPERABLE status, or on October 12,2009 at 0818 CST, whichever occurs first. This one time emergency TS change will prevent an unnecessary shutdown of FNP Unit 2.
3.0 Need for Technical Specification Change The proposed one-time change to the FNP Unit 2 Completion Time of TS 3.7.8, Action A, is needed to avoid the unnecessary shutdown of the plant to complete Unit 2 SWS Train A seismic support ring assembly replacement activities. The SWS is required for all modes of plant operation, and a plant shutdown would not eliminate the need for SWS operation. The likelihood of an impact to the equipment in question, for an additional 72-hour duration, due to a seismic event is very low and would remain, regardless of unit shutdown. The change averts known risks from complex and infrequent plant shutdown and startup evolutions that would unnecessarily challenge plant systems. It should be noted that except during tag out for repair, the Train A pumps are available to supply service water to essential plant loads. In addition, maintaining the plant at power allows for normal core cooling and provides for back-up cooling by way of the Turbine Driven Auxiliary Feedwater System. If unit shutdown is initiated, these system capabilities will be lost, placing full reliance on the degraded SWS.
Page 2 of 6
Enclosure 1 Description of the Proposed Change 4.0 Description of Proposed Change 4.1 Proposed Change Add a note to allow a one time change to TS LCO 3.7.8 Action A Completion Time to extend from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 6 days.
4.2 System Description
The SWS provides a heat sink for the removal of process and operating heat from safety related components during a Design Basis Accident (DBA) andlor transient. During normal operation, and a normal shutdown, the SWS also provides this function for various safety related and non-safety related components. The principal safety related function of the SWS is the removal of decay heat from the reactor via the Component Cooling Water System.
The SWS consists of two separate, 100% capacity, safety related, cooling water trains.
Each train consists of two 50% capacity pumps, one shared 50% capacity spare pump, piping, valving, and instrumentation. Train A contains SWS Pumps A and B, and Train B contains SWS Pumps D and E. SWS Pump C is a swing pump.
Four pumps are normally in operation on each unit, with one (swing) pump not in service. In the event of failure of a pump, plant operators must align the swing pump to the train containing the failed pump, maintaining two pumps per train.
While there are no indications of seismic support ring assembly issues for Unit 1, the Unit 1 assemblies will be inspected following any necessary replacement of Unit 2 assemblies.
The Unit 1 design is considered more robust than Unit 2. Drawings are provided in Enclosure 2. Some of the design feature differences between the Unit 1 and Unit 2 seismic support ring assemblies are listed below:
Unit 1
- A single weldment that is well stiffened and attached to the wall with 8 each 1 inch diameter cast-in-place "J-bolt."
- The wall mounting plate is 1-inch thick.
Unit 2
- A two-piece design that attaches to the wall with 4 each 3/4-inch diameter grouted-in-place threaded rods.
- The wall mounting plate is 5/8 inches thick.
Page 3 of 6
Enclosure 1 Description of the Proposed Change 4.3 Basis for the Technical Specification Change Technical Specification (TS) 3.7.8, "Service Water System (SWS)" requires two SWS trains to be operable. The SWS is capable of delivering cooling water during all modes of plant operation to all equipment required to function under accident conditions. All safety-related portions of the SWS, including the service water intake structure and pumps, are Seismic Category I and meet the single-failure criteria. Because the SWS operates continuously during normal plant operation, its availability is apparent to plant operators. The loss of any single component will not render the system incapable of supplying sufficient SWS flowrates. The proposed one-time Completion Time change from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 6 days for the Unit 2 SWS Train A to be inoperable to permit replacement is based upon the assumed operability of SWS Train B and the SWS Pump C (swing pump). The TS LCO 3.7.8 Action A of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is for a broad range of design basis accidents, the 72-hour Completion Time extension is associated with seismic events only. In addition, as previously noted, the Train B SWS pump seismic support ring assemblies were inspected and found to be acceptable.
The SWS Train A pumps are capable of performing their intended function in the absence of a seismic event and are available except when tagged out to effect repairs.
The likelihood of a seismic event at FNP, during an additional 72-hour Completion Time, is remote.
5.0 Qualitative Assessment This qualitative assessment is for a one time LCO extension for SWS Train A only during the repair period of the SWS 2B Pump seismic support ring assembly. TS 3.7.8 requires two operable SWS trains, consisting of two pumps per train. The following are reasons for the acceptability of the 72-hou r extension of the Completion Time for LCO 3.7.8 Action A:
- SWS Pump 2A is capable of auto start and performing its intended function in the absence of a seismic event.
- The likelihood of a seismic event at FNP, during an additional 72-hour Completion Time, is remote.
- Train A of the SWS is available. The seismic support ring assembly for Pump 2C is assumed to have been replaced and that the pump is operable. Pump 2A is available for non-seismic event operation.
- Train B of the SWS is operable. The seismic support ring assembly for Pump 2E has been replaced and the assembly for Pump 2D has been inspected and found acceptable.
- Following restoration of Train A, an additional inspection will be performed for the Pump 2D seismic support ring assembly and will be re-inspected every 30 days until repair/replacement.
- The TS LCO 3.7.8 Action A is for a broad range of design basis accidents. The 72-hour Completion Time extension is associated with seismic events only.
- For the condition of an unrestrained pump column potentially damaging an adjacent pump column during a postulated seismic event, engineering has concluded it is not credible that the unrestrained column could contact an adjacent column.
Page 4 of 6
Enclosure 1 Description of the Proposed Change
- Maintaining the plant at power allows for normal core cooling and provides for back-up cooling by way of the Turbine Driven Auxiliary Feedwater System. Shutting down places full reliance for core cooling on the degraded SWS.
- During the extended Completion Time period, additional safety related equipment will not be voluntarily removed from service.
- During the extended Completion Time period, switchyard activities affecting transmission will be restricted.
The above description is the intended plan, but conditions may necessitate a change in sequence of pump restoration in order to obtain an operational SWS Train A. The plan will ensure that, for Train A, one pump is operational and one pump is available prior to entering the extended completion time. Unit 1 SWS seismic support ring assemblies will be inspected following restoration of Unit 2 SWS Train A.
6.0 Regulatory Safety Analysis 6.1 No Significant Hazards Consideration The proposed change will provide a one-time revision to the FNP Unit 2 Completion Time of TS 3.7.8, Action A, to allow an inoperable Unit 2 Train A service water for 6 days. The extended Completion Time will permit replacement of two seismic support ring assemblies for Train A.
- 1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change does not alter any plant equipment or operating practices in such a manner that the probability of an accident is increased. The proposed changes will not alter assumptions relative to the mitigation of an accident or transient event. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not involve any physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Based on the operability of the remaining SWS train, the proposed change ensures that the accident analysis assumptions continue to be met. The system's design and operation are not affected by the proposed changes. The safety analysiS acceptance criteria are not altered by the proposed changes.
Page 5 of 6
Enclosure 1 Description of the Proposed Change Therefore, the proposed change does not involve a significant reduction in the 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.
6.2 Environmental Assessment This amendment request meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) as follows:
(i) The amendment involves no significant hazards consideration.
As described above, the proposed change involves no significant hazards consideration.
(ii) There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
The proposed change does not involve the installation of any new equipment or the modification of any equipment that may affect the types or amounts of effluents that may be released offsite. Therefore, there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
(iii) There is no significant increase in individual or cumulative occupation radiation exposure.
The proposed change does not involve plant physical changes or introduce any new mode of plant operation. Therefore, there is no significant increase in individual or cumulative occupational radiation exposure.
Based on the above, SNC concludes that the proposed change meets the criteria specified in 10 CFR 51.22 for a categorical exclusion from the requirements of 10 CFR 51.22 relative to requiring a specific environmental assessment by the Commission.
7.0 Conclusion The proposed change will provide a one-time revision to the FNP Unit 2 Completion Time of TS 3.7.8, Action A, to allow an inoperable Unit 2 Train A service water for 6 days. The extended Completion Time will permit replacement of the Unit 2 pump seismic support ring assembly.
The Plant Review Board reviewed the proposed change to the Technical Specifications and concluded that it does not involve a significant hazard consideration and will not endanger the health and safety of the public.
Page 6 of 6
Joseph M. Farley Nuclear Plant Unit 2 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, "Service Water System (SWS)"
Enclosure 2 Drawings - Unit 1 and Unit 2 Seismic Support Ring Assembly
Enclosure 2 Drawing - Unit 1 Seismic Support Ring Assembly Date: 10/6/2009 Time: 04:19:37 PM ,
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Joseph M. Farley Nuclear Plant Unit 2 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, "Service Water System (SWS)"
Enclosure 3 Marked-Up Technical Specifications Page
SWS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water System (SWS)
LCO 3.7.8 Two SWS trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SWS train A.1 -----------NOTES-----------
inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources-Operating," for emergency diesel generator made inoperable by SWS.
- 2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops MODE 4,"
for residual heat removal loops made inoperable by SWS.
Restore SWS train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
B. One SWS automatic B. 1 Restore both inoperable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> turbine building isolation turbine building isolation valve inoperable in each valves to OPERABLE SWS train. status.
Farley Units 1 and 2 3.7.8-5 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Joseph M. Farley Nuclear Plant Unit 2 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, "Service Water System (SWS)"
Enclosure 4 Clean Typed Technical Specifications Page
SWS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water System (SWS)
LCO 3.7.8 Two SWS trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SWS train A.1 -----------NOTES-----------
inoperable. 3. Enter applicable Conditions and Required Actions of LCO 3.8.1, nAC Sources-Operating," for emergency diesel generator made inoperable by SWS.
- 4. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops MODE 4,"
for residual heat removal loops made inoperable by SWS.
Restore SWS train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
B. One SWS automatic B.1 Restore both inoperable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> turbine building isolation turbine building isolation valve inoperable in each valves to OPERABLE SWS train. status.
Farley Units 1 and 2 3.7.8-7 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Joseph M. Farley Nuclear Plant Unit 2 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, "Service Water System (SWS)"
Enclosure 5 Commitment Table
Enclosure 5 Commitment Table
! Type Scheduled Commitment One-Time Continuing Completion Date Action Compliance (If Required)
Inspection of the Service Water System 20 pump seismic ring assembly bolting will be performed X following completion of the Train A repairs.
Inspection ends when Service Water Inspection of the Service Water System 20 pump
- System 20 pump seismic ring X seismic ring assembly bolting will be performed assembly bolting every 30 days.
can be permanently corrected.
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The Unit 1 SWS seismic support ring No later than X
assemblies will be inspected. November 20, 2009 I
Page 1 of 1