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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
MONTHYEARIR 05000348/20240032024-11-13013 November 2024 Integrated Inspection Report 05000348/2024003, 05000364/2024003 and 07200042/2024001 IR 05000348/20244032024-11-13013 November 2024 – Security Baseline Inspection Report 05000348/2024403 & 05000364/2024403 NL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit 2024-09-05
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value NL-21-0925, Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2021-12-22022 December 2021 Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves NL-21-0989, License Amendment Request to Relocate Augmented Piping Inspection Program Details2021-12-22022 December 2021 License Amendment Request to Relocate Augmented Piping Inspection Program Details NL-21-1017, License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure2021-12-13013 December 2021 License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure NL-21-0930, Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-10-21021 October 2021 Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements NL-21-0658, Joseph Farley, Units 1 and 2, Vogtle, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for for Steam Generator Tube Inspections2021-09-17017 September 2021 Joseph Farley, Units 1 and 2, Vogtle, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for for Steam Generator Tube Inspections NL-21-0613, Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, .2021-06-30030 June 2021 Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, . NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications2021-06-22022 June 2021 License Amendment Request to Remove Table of Contents from Technical Specifications NL-21-0042, Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System2021-06-0909 June 2021 Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System NL-21-0065, License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls2021-03-25025 March 2021 License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls NL-20-0949, License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 22020-10-30030 October 2020 License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2 ML20224A4642020-08-11011 August 2020 Southern Nuclear Operating Co, Inc - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions NL-19-0226, 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 Positions2020-06-30030 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 ML20192A1402020-06-30030 June 2020 Southern Nuclear Operating Co., Inc. - License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions NL-20-0275, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2020-05-29029 May 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues NL-19-0331, License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors2019-12-12012 December 2019 License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors NL-19-0963, Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process2019-12-11011 December 2019 Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process NL-19-1063, Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition2019-12-10010 December 2019 Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-19-0771, Risk Informed Technical Specification Information Only Bases Changes2019-06-27027 June 2019 Risk Informed Technical Specification Information Only Bases Changes NL-18-0668, Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2018-12-14014 December 2018 Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material NL-18-1189, Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-4712018-11-29029 November 2018 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-471 ML18226A0942018-08-0909 August 2018 Edwin I. Hatch, Units 1 and 2; and Vogtle, Units 1 and 2 - License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-shift Staff Tables NL-18-0039, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ...2018-07-27027 July 2018 License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ... NL-18-0733, Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information2018-06-0707 June 2018 Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures NL-17-0190, Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidate Line Item Improvement Process2017-12-21021 December 2017 Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidate Line Item Improvement Process NL-17-0611, Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow2017-12-21021 December 2017 Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow NL-17-1088, Submittal of License Amendment Request, Relocation of the Emergency Operations Facility2017-08-30030 August 2017 Submittal of License Amendment Request, Relocation of the Emergency Operations Facility NL-16-2384, Non-Voluntary License Amendment Request to Correct Non-Conservative Technical Specification 3.7.12017-03-22022 March 2017 Non-Voluntary License Amendment Request to Correct Non-Conservative Technical Specification 3.7.1 ML15329A0322017-01-23023 January 2017 Issuance of Amendment Related to Renewed Facility Operating License Condition 2.C.(23) Required Completion Date ML16340A0052016-12-0101 December 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Rev 4, Clarify Use and Application Rules. 2024-09-04
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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.