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MONTHYEARML16256A1352016-09-0808 September 2016 License Amendment Request to Revise Facility Operating License Condition 2.C.(23) Required Completion Date Project stage: Request ML16257A5782016-09-13013 September 2016 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance Review Regarding Unit 2 Renewed Facility Operating License Condition 2.C.(23) License Amendment Request Project stage: Acceptance Review ML15329A0322017-01-23023 January 2017 Issuance of Amendment Related to Renewed Facility Operating License Condition 2.C.(23) Required Completion Date Project stage: Approval 2016-09-08
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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public 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 ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals 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 ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report 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 IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0716, 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 IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 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 IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) 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 ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter 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 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 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 2024-01-30
[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
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Justin T. Wheat Southern Nuclear Nuclear Licensing Manager Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242
& Southern Nuclear Tel 205.992.5998 Fax 205.992.7601 September 8, 2016 Docket Nos.: 50-364 NL-16-0889 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 License Amendment Request to Revise Facility Operating License Condition 2.C.(23) Required Completion Date Ladies and Gentlemen:
In accordance with 10 CFR 50.90, Southern Nuclear Operating Company (SNC) proposes to amend Renewed Facility Operating License (FOL) No. NPF-8 for Joseph M. Farley Nuclear Plant (FNP) Unit 2. This amendment corrects an understandable and unintentional mistake in the Unit 2 FOL.
Specifically, FNP Unit 2 Renewed FOL condition 2.C.(23) says in the second paragraph, The Southern Nuclear Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. Southern Nuclear shall complete these activities no later than June 25, 2017, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection." However, June 25, 2017 is the date when Unit 1 future activities to be completed prior to the period of extended operation must be completed. The corresponding date for Unit 2 is March 31, 2021, which is the date that should be shown in the license condition. to this letter provides the proposed FOL License Condition change, the basis for the proposed change, and Significant Hazards Considerations. SNC has evaluated the proposed FOL change and has determined that it does not involve a significant hazards consideration as defined in 10 CFR 50.92. to this letter provides the marked up revision to the FOL License Condition. to this letter provides the clean-typed revision to the FOL License Condition.
SNC requests approval of the proposed license amendment by December 31, 2016. The proposed changes would be implemented within 90 days of issuance of the amendment.
U.S. Nuclear Regulatory Commission NL-16-0889 Page 2 This letter contains no NRC commitments. If you have any questions, please contact John Giddens at 205.992.7924.
Mr. Justin T. VVheat states he is the Nuclear Licensing Manager for 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.
I , .. ':. t ,*
Respectfully submitted,
,J \' 1 My commission expires: /O -J' - 2o/7 JlW/JMC/lac
Enclosures:
- 1. Basis for Proposed Change
- 2. Marked-Up License Condition Change Plan
- 3. Clean-Typed License Condition Change Plan*
cc: . Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President- Farley.
Mr. M. D. Meier, Vice President - Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President - Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A Williams, NRR Project Manager - Farley Mr. P. K. Niebaum, Senior Resident Inspector - Farley
. Alabama Department of Public Health David Walter, Director, Alabama Office of Radiation Control
Joseph M. Farley Nuclear Plant - Unit 2 License Amendment Request to Revise Facility Operating License Condition 2.C.(23) Required Completion Date Enclosure 1 Basis for Proposed Change to NL-16-0889 Basis for Proposed Change Table of Contents 1.0 Summary Description 2.0 Detailed Description 3.0 Technical Evaluation 4.0 Regulatory Evaluation 4.1 No Significant Hazards Consideration Determination 4.2 Applicable Regulatory Requirements/Criteria 4.3 Conclusions 5.0 Environmental Consideration E1-1
Enclosure 1 to NL-16-0889 Basis for Proposed Change 1.0 Summary Description The proposed amendment corrects an understandable and unintentional mistake in the Facility Operating Licenses (FOL), NPF-8, for Joseph M. Farley Nuclear Plant (FNP) Unit 2.
2.0 Detailed Description This proposed License Amendment Request (LAR) corrects an understandable and unintentional mistake discovered in License Condition 2.C.(23). Specifically, the license condition states, "The Southern Nuclear Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. Southern Nuclear shall complete these activities no later than June 25, 2017, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection." However, June 25, 2017 is the date the Unit 1 future activities must be completed. For Unit 2, the correct date for this license condition is March 31, 2021, not June 25, 2017.
This LAR proposes to change the FNP FOL, License Condition 2.C.(23), to correct the date by which the future activities described in the Updated Final Safety Analysis Report supplement must be completed from June 25, 2017 to March 31, 2021.
3.0 Technical Analysis The proposed amendment contains no technical changes; all proposed changes are administrative. These changes are consistent with the intent of what the Nuclear Regulatory Commission (NRC) has already approved..
Proposed Change:
Replace the date June 25, 2017 in License Condition 2.C.(23) with the date March 31, 2021, so that sentence reads:
Southern Nuclear shall complete these activities no later than March 31. 2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRG inspection.
Basis for Change:
This is an understandable and unintentional mistake. The following points provide a basis for that assertion.
The portion of the license condition in question that needs to be corrected states, "The Southern Nuclear Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. Southern Nuclear shall complete these activities no later than June 25, 2017, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection." ,
Note that the date June 25, 2017 is the date that the previous FNP Unit 1 license, before license renewal, would have expired and the last day before the FNP Unit 1 Period of E1-2 to NL-16-0889 Basis for Proposed Change Extended Operation (PEO) begins. The comparable license condition in the FNP Unit 1 FOL is identical, including the date. Finally, note that the license condition states, " ... describes certain future activities to be completed prior to the period of extended operation. Southern Nuclear shall complete these activities no later than June 25, 2017, and ... "
For FNP Unit 1, this statement is consistent with the requirement that the activities must be completed prior to the period of extended operation because June 25, 2017 is the last day before the period of extended operation begins. However, for Unit 2, this June 25, 2017 is not consistent with the requirement because it still states the activities must be completed prior to the period of extended operation, but the last day before the period of extended operation is March 31, 2021, not June 25, 2017.
Risk Impact Discussion:
No formal risk evaluation was performed as no actual change to the plant is being made.
Defense-in-Depth/Safety Margin Discussion:
No Defense-in-Depth/Safety Margin evaluation was performed as no actual change to the plant is being made.
4.0 Regulatory Safety Analysis 4.1 Significant Hazards Consideration Southern Nuclear Operating Company (SNC) is requesting an amendment to the Joseph M. Farley N!Jclear Plant (FNP) Unit 2 Facility Operating License (FOL), License Condition 2.C.(23), to correct the date by which the future activities described in the Updated Final Safety Analysis Report supplement must be completed. The FOL was originally issued with this date, June 25, 2017, being the same date as in the similar license condition in the Unit 1 FOL, instead of the using the appropriate Unit 2 date, which is March 31, 2021.
A written evaluation of the significant hazards consideration of a proposed license amendment is required by 10 CFR 50.92. According to 10 CFR 50.92, a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
- Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- Create the possibility of a new or different kind of accident from any accident previously evaluated; or
- Involve a significant reduction in a margin of safety.
As required by 10 CFR 50.91 (a), the SNC analysis of the issue of no significant hazards consideration using the standards in 10 CFR 50.92 is presented below:
1: Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No E1-3 to NL-16-0889 Basis for Proposed Change The proposed amendment contains no technical changes; all proposed changes are administrative. These changes are consistent with the intent of what has already been approved by the Nuclear Regulatory Commission (NRC). There are no accidents affected by this change, and therefore no 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 amendment contains no technical changes; all proposed changes are administrative. These changes are consistent with the intent of what has already been approved by the Nuclear Regulatory Commission (NRC). There are no accidents affected by this change, and therefore no 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?
Response: No The proposed ame.ndment contains no technical changes; all proposed changes are administrative. These changes are consistent with the intent of what has already been approved by the Nuclear Regulatory Commission (NRC). There are no accidents affected by this change, and therefore no reduction in a margin
.of safety.
Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. SNC has evaluated the proposed amendment and determined that it involves no significant hazards consideration.
4.2 Applicable Regulatory Requirements/Criteria The proposed amendment contains no technical changes; all proposed changes are administrative. Therefore, there are no applicable regulatory requirements for these proposed changes.
- 4.3 Conclusions Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common
- defense and security or to the health and safety of the public.
E1-4 to NL-16-0889 Basis for Proposed Change 5.0 Environmental Considerations SNC has evaluated the proposed amendment and determined that the amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant
- increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9}. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
Joseph M. Farley Nuclear Plant - Unit 2 License Amendment Request to Revise Facility Operating License Condition 2.C.(23) Required Completion Date Enclosure 2 Marked-Up License Condition Change Page
(23) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50 .71(e)(4) following issuance of this renewed license.
Until that update is complete , Southern Nuclear may make changes to the programs and activities described in the supplement without prior Commission approval , provided that Southern Nuclear evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements of that section.
The Southern Nuclear Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54 .21 (d) , describes certain future activities to be completed prior to the period of extended operation . Southern Nuclear shall complete these activities no later than June 25 , 201 ?March 31. 2021 ,
and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection .
(24) Reactor Vessel Material Surveillance Capsules All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule , including spare capsules , must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion .
D. Southern Nuclear shall fully implement and mainta in in effect all provisions of the Commission-approved physical security, training and qualification , and safeguards contingency plans includ ing amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73 .55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p) . The plan , which contain Safeguards Information protected under 10 CFR 73 .21 , is entitled : "Southern Nuclear Operating Company Security Plan ,
Training and Qualification Plan , and Safeguards Contingency Plan ," and was submitted on May 15, 2006 .
Southern Nuclear shall fully implement and maintain in effect all provisions of the Commission-approved cyber security (CSP) , includ ing changes made pursuant to the authority of 10 CFR 50 .90 and 10 CFR 50 .54(p) . The Southern Nuclear CSP was approved by License Amendment No. 181 , as supplemented by a change approved by License Amendment No. 195.
E. Deleted per Amendment 144 F. Alabama Power Company shall meet the following antitrust conditions:
(1) Alabama Power Company shall recognize and accord to Alabama Electric Cooperative (AEC) the status of a competing electric utility in central and southern Alabama .
Farley - Unit 2 Renewed License No. NPF-8 Amendment No . ~
Joseph M. Farley Nuclear Plant - Unit 2 License Amendment Request to Revise Facility Operating License Condition 2.C.(23) Required Completion Date Enclosure 3 Clean-Typed License Condition Change Page
(23) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4) following issuance of this renewed license.
Until that update is complete, Southern Nuclear may make changes to the programs and activities described in the supplement without prior Commission approval, provided that Southern Nuclear evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements of that section.
The Southern Nuclear Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d}, d~scribes certain future activities to be completed prior to the period of extended. operation. Southern Nuclear shall complete these activities no later than March 31, 2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
(24) Reactor Vessel Material Surveillance Capsules All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion.
- D. Southern Nuclear shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Southern Nuclear Operating Company Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan," and was submitted on May 15, 2006.
- Southern Nuclear shall fully implement and maintain in effect all provisions of the Commission-approved cyber security (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Southern Nuclear CSP was approved by License Amendment No. 181, as supplemented by a change approved by License Amendment No. 195.
E. Deleted per Amendment 144 F. Alabama Power Company shall meet the following antitrust conditions:
(1) Alabama Power Company shall recognize and accord to Alabama Electric Cooperative (AEC) the status of a competing electric utility in central and southern Alabama.
Farley - Unit 2 Renewed License No. NPF-8 Amendment No.