Letter Sequence Approval |
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MONTHYEARML13031A6262013-03-22022 March 2013 Supplemental Information Needed for Acceptance of Requested Licensing Action Concerning Degraded Voltage Compensatory Measures (TAC Nos. MF0468 and MF0469) (NL-12-2142) Project stage: Acceptance Review ML14069A3442014-05-13013 May 2014 Issuance of Amendments to Incorporate the Schedule for Degraded Grid Voltage Modification Project stage: Approval 2013-03-22
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Category:Letter
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-24-0349, 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-24-0259, 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 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 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 ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time 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 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-24-0234, 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-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0235, 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) NL-24-0221, 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 NL-24-0123, 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 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 2024-09-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24242A1332024-08-29029 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 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 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) 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 ML23076A0502023-03-21021 March 2023 Correction of Amendment Nos. 244 and 241 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a License Controlled Document ML23054A4552023-03-16016 March 2023 Issuance of Amendment Nos. 245 and 242, Regarding LAR to Revise Technical Specification 3.4.10, Pressurizer Safety Valves, to Decrease Low Side Setpoint Tolerance LCO Value ML22308A0592022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22286A0742022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22263A2252022-11-0101 November 2022 Issuance of Amendment Nos. 243 and 240 to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure 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 ML22060A1892022-03-15015 March 2022 Correction to TS Pg 3.6.6-4 During Issuance of Amendment Nos. 225 and 222 ML22032A2432022-03-0707 March 2022 Issuance of Amendment Nos. 241 and 238 to Eliminate the Encapsulation Vessels Around the First Containment Spray and Residual Heat Removal / Low Head Safety Injection Recirculation Suction Isolation Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML22004A1322022-01-24024 January 2022 Correction of Amendment Nos. 227 and 224 Issuance of Amendments Regarding Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition (EPID L-2019-LLA-027 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 ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21137A2472021-06-30030 June 2021 Issuance of Amendment Nos. 233 and 230, Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components NL-21-0379, Southern Nuclear Operating Company - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions2021-04-27027 April 2021 Southern Nuclear Operating Company - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21095A0872021-04-19019 April 2021 Non-Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values 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 ML20224A2852020-10-13013 October 2020 Issuance of Amendment Nos. 231 and 228 to Revise Technical Specifications 3.3.1 and 3.3.7 ML20121A2832020-10-0909 October 2020 Issuance of Amendments 230 and 227 Measurement Uncertainty Recapture Power Uprate ML20196L9292020-10-0606 October 2020 Issuance of Amendment Nos. 229 and 226 Regarding Spent Fuel Pool Criticality Safety Analysis ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19175A2432019-08-23023 August 2019 Issuance of Amendments 225 and 222 Implementation of NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specification (Rmts) Guidelines, Revision 0-A ML19156A2622019-07-30030 July 2019 Issuance of Amendments 224 and 221 Performance-Based Fire Protection Alternative for Thermal Insulation Material 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 ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML18271A2072018-11-0707 November 2018 Issuance of Amendments 221 and 218 Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) 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 ML17291A7812018-03-0101 March 2018 Issuance of Amendments to Correct Non-Conservative Technical Specification 3.7.1 (CAC Nos. MF9465 and MF9466; EPID L-2017-LLA-0181) ML17261A0872018-02-28028 February 2018 Issuance of Amendments to Revise Actions of TS 5.5.17, Containment Leakage Rate Testing Program (CAC Nos. MF8844 and MF8845; EPID No. L-2016-LLA-0015) ML17271A2652017-12-20020 December 2017 Issuance of Amendments Adopting Alternative Source Term, TSTF-448, and TSTF-312 (CAC Nos. MF8861, MF8862, MF8916, MF8917, MF8918, MF8919; Epids Nos. L-2016-LLA-0017,L-2016-LLA-0018, L-2016-LLA-0019) ML17269A1662017-11-0101 November 2017 Issuance of Amendments Related to NFPA 805 Supplement (CAC Nos. MG0094 and MG0095; EPID L-2017-LLA-0261) ML17214A5462017-10-0202 October 2017 Issuance of Amendments Regarding the Adoption of TSTF-547, Revision 1, Clarification of Rod Position Requirements ML17205A0202017-09-15015 September 2017 Issuance of Amendments to Revise TS 3.8.9, Distribution Systems - Operating ML17152A2182017-06-30030 June 2017 Southern Nuclear Fleet - Issuance of Amendments Regarding the Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing (CAC Nos. MF8176 - MF8181) ML17137A0412017-06-27027 June 2017 Issuance of Amendments Regarding the Adoption of TSTF-529, Revision 4, Clarify Use and Application Rules (CAC Nos. MF8897, MF8898, MF8900-MF8902, and MF8921) ML17023A2372017-03-16016 March 2017 Issuance of Amendments Regarding the Adoption of NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors(Cac Nos. MF7460-MF7465) ML16141A1252017-03-14014 March 2017 Issuance of Amendments to Incorporate Southern Nuclear Operating Company Fleet Emergency Plan ML17034A1932017-02-16016 February 2017 Issuance of Amendments to Adopt TSTF-427 Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML16291A0302017-01-13013 January 2017 Issuance of Amendments the Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions (CAC Nos. MF7466, MF7467, MF7468, MF7469, MF7470, & MF7471) NL-16-0388, Alternative Source Term License Amendment Request2016-11-22022 November 2016 Alternative Source Term License Amendment Request ML16196A1612016-11-17017 November 2016 Issuance of Amendments Related to Technical Specification 3.3.5 ML16232A0002016-10-17017 October 2016 Issuance of Amendments Related to NFPA-805 Supplement 2024-08-29
[Table view] Category:Safety Evaluation
MONTHYEARML24242A1332024-08-29029 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 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 ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code 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) 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 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 ML23164A2072023-06-14014 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) - Draft Safety Evaluation ML23054A4552023-03-16016 March 2023 Issuance of Amendment Nos. 245 and 242, Regarding LAR to Revise Technical Specification 3.4.10, Pressurizer Safety Valves, to Decrease Low Side Setpoint Tolerance LCO Value ML22308A0592022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22286A0742022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document 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 ML22032A2432022-03-0707 March 2022 Issuance of Amendment Nos. 241 and 238 to Eliminate the Encapsulation Vessels Around the First Containment Spray and Residual Heat Removal / Low Head Safety Injection Recirculation Suction Isolation Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System 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 ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21137A2472021-06-30030 June 2021 Issuance of Amendment Nos. 233 and 230, Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality 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 ML20224A2852020-10-13013 October 2020 Issuance of Amendment Nos. 231 and 228 to Revise Technical Specifications 3.3.1 and 3.3.7 ML20121A2832020-10-0909 October 2020 Issuance of Amendments 230 and 227 Measurement Uncertainty Recapture Power Uprate ML20196L9292020-10-0606 October 2020 Issuance of Amendment Nos. 229 and 226 Regarding Spent Fuel Pool Criticality Safety Analysis ML20132A2072020-05-0808 May 2020 9 to the Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of the Plant and Chapter 2 (Part 1 of 3); Redacted Version ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19261A0142019-09-23023 September 2019 Correction to Safety Evaluation for Amendment Nos. 225 and 222 Regarding Implementation of NEI 06-09, Revision 0-A ML19175A2432019-08-23023 August 2019 Issuance of Amendments 225 and 222 Implementation of NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specification (Rmts) Guidelines, Revision 0-A ML19213A1942019-08-0808 August 2019 Relief from Impractical American Society of Mechanical Engineers Code Requirements (FNP-ISI-RR-02) ML19192A1712019-08-0202 August 2019 Relief from Inservice Impractical ASME Code Requirements (FNP-ISI-RR-03) ML19156A2622019-07-30030 July 2019 Issuance of Amendments 224 and 221 Performance-Based Fire Protection Alternative for Thermal Insulation Material 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 ML19129A2322019-07-0101 July 2019 Inservice Inspection Alternative, FNP-ISI-ALT-05-04, Regarding Examination Frequency for Tendon Anchorhead Replacement ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML18334A2282018-12-10010 December 2018 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03 ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure ML18271A2072018-11-0707 November 2018 Issuance of Amendments 221 and 218 Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) 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 ML17291A7812018-03-0101 March 2018 Issuance of Amendments to Correct Non-Conservative Technical Specification 3.7.1 (CAC Nos. MF9465 and MF9466; EPID L-2017-LLA-0181) ML17261A0872018-02-28028 February 2018 Issuance of Amendments to Revise Actions of TS 5.5.17, Containment Leakage Rate Testing Program (CAC Nos. MF8844 and MF8845; EPID No. L-2016-LLA-0015) ML18022A1072018-01-25025 January 2018 Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059) ML17354A9162017-12-28028 December 2017 Inservice Inspection Alternative FNP-ISI-ALT-05-01, Version 1, to Use ASME Code N-854 (CAC Nos. MG0107 and MF0108; EPID L-2017-LLR-0086) ML17271A2652017-12-20020 December 2017 Issuance of Amendments Adopting Alternative Source Term, TSTF-448, and TSTF-312 (CAC Nos. MF8861, MF8862, MF8916, MF8917, MF8918, MF8919; Epids Nos. L-2016-LLA-0017,L-2016-LLA-0018, L-2016-LLA-0019) ML17298A4162017-11-0101 November 2017 Relief Request FNP-ISI-ALT-22, Inservice Inspection Alternative for Code Case N-786-1 ML17269A1662017-11-0101 November 2017 Issuance of Amendments Related to NFPA 805 Supplement (CAC Nos. MG0094 and MG0095; EPID L-2017-LLA-0261) ML17214A5462017-10-0202 October 2017 Issuance of Amendments Regarding the Adoption of TSTF-547, Revision 1, Clarification of Rod Position Requirements ML17205A0202017-09-15015 September 2017 Issuance of Amendments to Revise TS 3.8.9, Distribution Systems - Operating ML17180A4392017-07-18018 July 2017 Inservice Testing Alternative for Pumps Per Code Case OMN-20 (RR-VR-01) 2024-08-29
[Table view] Category:Technical Specifications
MONTHYEARML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time 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-23-0704, 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 2024-08-27
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
- tlay. 13, .. ?014 .. *.*** Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. P. 0. Box 1295 I Bin-038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS TO INCORPORATE THE SCHEDULE FOR DEGRADED GRID VOLTAGE MODIFICATION (TAG NOS. MF0468 AND MF0469)
Dear Mr. Pierce:
By letter dated December 21, 2012, as supplemented by letter dated May 21, 2013, Southern Nuclear Operating Company (SNC) proposed to revise the Farley Nuclear Plant (FNP) Unit 1 and Unit 2 Facility Operating Licenses, to include a schedule to implement degraded voltage modifications.
The modifications would include automatic actions and thus eliminate the need for manual actions in the event of a degraded grid voltage condition.
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 194 to Renewed Facility Operating License No. NPF-2, Unit 1, and Amendment No. 190 to Renewed Facility Operating License No. NPF-8, Unit 2. A copy of the related Safety Evaluation is also enclosed.
A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. If you have any questions, please call me at 301-415-1009.
Docket Nos. 50-348 and 50-364
Enclosures:
- 1. Amendment No. 194 to NPF-2 2. Amendment No. 190 to NPF-8 3. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC. ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 194 Renewed License No. NPF-2 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment to the Joseph M. Farley Nuclear Plant, Unit 1, Renewed Facility Operating Licenses No. NPF-2, filed by Southern Nuclear Operating Company, Inc. (the licensee), dated December 21, 2012, as supplemented by letter dated May 21, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act}, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and {ii) that such activities will be conducted in compliance with the Commission's regulations;
- D. The issuance of this license amendment will not be inimical to the common defense. and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1 ' 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2:c.(2) of Renewed Facility Operating License No. NPF-2, is hereby amended to read as follows: . (2) Technical Specifications
' The Technical Specifications contained in Appendix A, as revised through Amendment No. 194, are hereby incorporated in the renewed facility operating license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications. ) 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 13, 2014 FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES 1 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC. ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. i 90 Renewed License No. NPF-8 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment to the Joseph M. Farley Nuclear Plant, Unit 2, Renewed Facility Operating Licenses No. NPF-8, filed by Southern Nuclear Operating Company, Inc. (the licensee), dated December 21, 2012, as supplemented by letter dated May 21, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 2 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-8 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 190, are hereby incorporated in the renewed facility operating license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
Attachment:
Changes to the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance:
May 13 , 2 0 14 ATTACHMENT TO LICENSE AMENDMENT NO. 194 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 AND ATTACHMENT TO LICENSE AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Renewed Facility Operating License and Appendix "A" Technical Specifications (TSs) with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove License Page: NPF-2, page 4 NPF-2, page 4 TS Page: NPF-2, Appendix C, Page 2 NPF-2, Appendix C, Page 2 License Page: NPF-8, page 3 NPF-8, page 3 TS Page: NPF-8, Appendix C, Page 2 NPF-8, Appendix C, Page 2 Farley -Unit 1 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.194, are hereby incorporated in the renewed lieense. Soutliern Nuclear shall operate the facility in accordance with the Technical Specifications.
J (3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated.
The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.
- a. Southern Nuclear shall not operate the reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation.
- b. Deleted per Amendment 13 c. Deleted per Amendment 2 d. Deleted per Amendment 2 e. Deleted per Amendment 152 Deleted per Amendment 2 f. Deleted per Amendment 158 g. Southern Nuclear shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall include: f . 1) 2) 3) 4) Identification of a sampling schedule for the critical parameters and control points for these parameters; Identification of the procedures used to quantify parameters that are critical to control points;
- Identification of process sampling points; A procedure for the recording and management of data; Renewed License No. NPF-2 Amendment No. 194 Amendment 1\lumber 146 APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-2 Additional Condition The schedule for performing new and revised Surveillance Requirements (SRs) shall be as follows: 1. For SRs that are new in this amendment the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment. . 2. For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
- 3. For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
- 4. For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.
SNC shall implement the Degraded Voltage modifications to eliminate the manual actions in lieu of automatic degraded voltage protection to assure adequate voltage to safety-related equipment during design basis events. Condition Completion Date* Concurrent with the implementation of the Improved Technical Specifications.
Unit 1 2018 Spring . Outage, U1 R28 Amendment No. 194 (2) Alabama Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facflitles," to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with the procedures and limitations set forth in this renewed license. (3) Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; * (4) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30,40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 0 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Farley-2 (1) Maximum Power Level l Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 2775 megawatts thermal. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.1 9.0 . are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
Renewed License No. NPF-8 Amendment No.190 Amendment Number 137
- APPENDIXC ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-8 Additional Condition The schedule for performing new and revised Surveillance Requirements (SRs) shall be as follows: I 1. For SRs that are new in this amendment I the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
- 2. For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
,3. For SRs that existed prior to this I amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
- 4. For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.
'SNC shall implement the Degraded Voltage , modifications to eliminate the* manual actions in : lieu of automatic degraded voltage protection to 'assure adequate voltage to safety-related
- equipment during design basis events. ' Condition Completion Date Concurrent with the implementation of the Improved Technical Specifications.
Unit 2 2017 Fall Outage, U2R25 Amendment No. 190 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 194 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY. INC. JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated December 21, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12356A470), as supplemented by letter dated May 21, 2013, (ADAMS Accession No. ML 13144A081)
Southern Nuclear Operating Company (SNC) proposed to revise the Farley Nuclear Plant (FNP) Unit 1 and Unit 2 Facility Operating Licenses (FOLs}, NPF-2 and NPF-8, respectively, to include a schedule to implement degraded voltage modifications.
The proposed License Amendment Request (LAR) would revise the FOLs, Appendix C, to specify an implementation date of Spring 2018 outage for Unit 1 and Fall 2017 outage for Unit 2 for a redesign of the current degraded voltage scheme that would eliminate the use of manual actions in the event of a degraded grid voltage condition.
The modifications will include automatic degraded voltage protection to ensure adequate voltage is available to safety-related loads so they remain operable during a degraded voltage condition.
2.0 REGULATORY EVALUATION
Degraded voltage protection assures adequate voltage to safety-related equipment during a degraded voltage condition.
SNC's project plan includes proposed modifications to degraded voltage, possible replacement of the Loss of Offsite Power (LOSP) relays, and installation of new cabinets to house the relays. The U.S. Nuclear Regulatory Commission (NRC) staff used the following regulatory requirements and guidance documents during its review of the LAR: Enclosure 3 The FNP Updated Safety Analyses Report (USAR) Section 8.1.4, states that the offsite power system and the onsite power system conform to Title 1 0 of the Code of Federal Regulations, Section 50 (1 0 CFR 50), General Design Criterion (GDC) 17 and 18. GDC 17, "Electric Power Systems," requires, in part, that an onsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety. The onsite electric power supplies and the onsite electric distribution system shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single . failure. In addition, this criterion requires provisions to minimize the probability of losing electric power from any of the remaining supplies as a result of the loss of power from the unit, the transmission network, or the onsite electric power supplies.
GDC 18, "Inspection and Testing of Electric Power Systems," requires that electric power systems important to safety be designed to permit appropriate periodic inspection and testing to demonstrate operability and functional performance.
The 10 CFR 50.55a(h)(2) "Protection Systems," that requires nuclear power plants with construction permits issued after January 1, 1971, but before May 13, 1999, to have protection systems that meet the requirements stated in either Institute of Electrical and Electronics Engineers (IEEE) Standard 279, "Criteria for Protection Systems for Nuclear Power Generating Stations," or IEEE Standard 603-1991, "Criteria for Safety Systems for Nuclear Power Generating Stations," and the correction sheet dated January 30, 1995. NRC Regulatory Guide 1.32, "Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants," describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to design, operation and testing of electric power systems in nuclear power plants. Appendix A to Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50, "General Design Criteria (GDC)," Criterion 19--Control Room. "A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents
.... Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures." 10 CFR 50.120, "Training and qualification of nuclear power plant personnel" NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition":
Chapter 13 addresses "Conduct of Operation", specific sub-chapters considered in this review were Chapters 13.2.1, "Reactor Operator Requalification Program; Reactor Operator Training", and 13.5.2.1, "Operating and Emergency Operating Procedures".
Chapter 18, provides review guidance for "Human Factors Engineering".
NUREG-1764,"Guidance for the Review of Changes to Human Actions" GL 82-33, "Supplement 1 to NUREG-0737-Requirements for Emergency Response Capability" NUREG-0700, "Human-System Interface Design Review Guidelines" Revision 2 NUREG-0711, "Human Factors Engineering Program Review Model," Revision 2 IN 97-78, "Crediting Operator Actions in Piace of Automatic Actions and Modifications of Operator Actions, Including Response Times". 3.0 TECHNICAL EVALUATION
3.1 Electrical
The staff reviewed the licensee's proposed schedule for degraded voltage modifications to improve plant voltage profile during degraded grid conditions and interim measures to support plant operation until the completion of the modifications as described in Attachment 1 of the proposed LAR. Staff Assessment As stated in the USAR, the offsite and onsite power systems at the FNP Units 1 and 2 are designed to comply with the requirements of GDCs 17 and 18, respectively.
The onsite AC power system for FNP consists of five diesel generators (DGs) with 1-2A and 1 C assigned to the load group train A, while DGs 1 B, 2B, and 2C are assigned to the load group train B. DG 2C is dedicated to station blackout (SBO) events. The five DGs have two different ratings, DGs 1-2A, 1 B, and 2B are rated at 4075 kilo Watt (kW) and DGs 1 C and 2C are rated at 2850kW. Four of the DGs 1-2A, 1 C, 1 B, and 2B are dedicated for use during design basis events and DG 2C is dedicated as the alternate ac (AAC) power source for use during a SBO event. DG 1 C with a rating of 2850kW does not have enough capacity to support accident loads required for safe shutdown of the plants. Thus this DG is selected to power the safety busses of the non-accident unit. The FNP USAR states that the existing offsite power system consists of two physically independent sources of power for each unit. There are four startup auxiliary transformers, two for each unit, that are connected to the transmission system through four separate 230 kilo Volt (kV) oil-static cables. These transformers provide a source of power for startup, shutdown, and operational requirements for both units. Under normal operating conditions, these startup transformers supply power to 4160V buses A, B, C, D, and E for Unit 1 and D and E only for Unit 2 along with 4160V emergency buses F, G, H, J, K, and L. Busses K and L are considered extensions of busses F and G. The 4160V emergency buses F, H, and K of each unit and their associated emergency loads are designated as load group train A and the corresponding 4160V emergency buses G, J, and L of each unit and their associated emergency loads are designated as load group train B. The FNP USAR states that the normal offsite power system operating voltage range for Units 1 and 2 is maintained within 101.6 percent to 104.5 percent of 230 kV. Analytical studies have been performed by FNP to demonstrate that this range can be maintained when at least one unit is on line for system voltage support. A minimum voltage of 101.6 percent is necessary for satisfactory operation of some non-safety related loads when supplied from the offsite power system. The USAR further states that system voltages for worst case single contingencies are expected to remain at or above 100 percent of 230 kV. This includes the contingency that assumes one ) Farley unit is experiencing loss-of-coolant accident (LOCA) and the other unit is tripped. The value of 100 percent assures acceptable terminal voltages, with margin, for safe shutdown equipment to perform its safety function.
Therefore, continued unit operation is acceptable in the unlikely event that system voltage is found to be less than 101.6 percent, but above 100 percent. Following a July 1976 event at Millstone involving a degraded voltage condition, the NRC staff developed generic positions on power systems for operating reactors.
- Since degradation of the offsite power system can lead to or cause the failure of redundant Class 1 E safety-related electrical equipment, the NRC required that licensees install degraded voltage protection as described in NRC letter dated June 2, 1977, "Statement of Staff Positions Relative to Emergency Power Systems for Operating Reactors" (ADAMS Legacy No. 4007002656).
The letter states that "the voltage monitors shall automatically initiate the disconnection of offsite power sources whenever the voltage setpoint and time delay limits have been exceeded." The letter further states that "the voltage monitors shall be designed to satisfy the requirements of IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations." This automatic feature ensures the adequacy of the offsite power system and the onsite distribution system and ensures that the electrical system has sufficient capacity and capability to automatically start and operate all required safety loads. Contrary to the June 2, 1977 letter, an NRC Safety Evaluation Report (SER) for FNP (ADAMS Legacy No. 951211 0043) accepted manual operator actions to compensate for degraded grid conditions.
A Component Design Bases Inspection completed on December 8, 2011 (ADAMS Accession No. ML 113530575) identified the discrepancy between the June 2, 1977 letter and the current design of FNP Units 1 and 2. The licensee stated that the LAR is a result of discussions between SNC and the NRC concerning degraded voltage protection scheme at the SNC Edwin I. Hatch plant since FNP has a similar issues. By letter dated September 29, 2011 (ADAMS Accession No; ML 112730194) staff issued its final response to an SNC Backfit Appeal regarding the Edwin I. Hatch plant. Below is an excerpt: Further, the staff concludes that the NRC change in position, from that in the 1995 SER, regarding the acceptability of relying on manual operator action to demonstrate compliance with the applicable provisions of GDC-17 and 10 CFR 50.55a(h)(2), constitutes backfitting as defined in 10 CFR 50.1 09(a)(1 ). The backfitting action is necessary for compliance with GDC-17 and 10 CFR 50.55a(h)(2) and is consistent with applicable guidance and practices in effect at the time that the NRC staff erroneously approved the use of manual actions responding to degraded grid voltage condition in 1995. Although SNC has been in compliance with its 1995 license amendment approving SNC's degraded voltage protection system configuration, SNC also has been in violation of GDC-17 and 10 CFR 50.55a(h)(2) due to the NRC'S erroneous approval of the 1995 license amendment 1* The NRC is exercising enforcement discretion for SNC's failure to comply with GDC-17 and 10 CFR 50.55a(h)(2) because SNC's failure to comply resulted from the NRC incorrectly issuing the license amendment in 1995. By letter dated December 21, 2012, (ADAMS Accession Number ML12356A472), SNC, submitted a separate LAR for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 with a schedule for implementation of plant modifications to correct the identified deficiencies.
In response to the inspection findings at FNP, the licensee initiated corrective actions to modify the plant to bring it in compliance with the stated regulations.
The implementation schedule SNC provided, by letter dated December 21, 2012, states that both Units will have automatic protection schemes installed by the spring 2018 refueling outage. In view of the extended schedule for implementation of the modifications, by letter dated March 22, 2013 (ADAMS Accession Number ML 13031 A626), the NRC staff requested additional information with respect to consequences of degraded voltage conditions and compensatory ) actions that are in place for protection of safety significant equipment.
By letter dated May 21, 2013 (ADAMS Accession Number ML 13144A081
), FNP provided responses to the staff's questions.
The staff's RAis and FNP responses are described below. 1. With regard to a potential event of emergency safety features (ESF) actuation signal during degraded voltage conditions, the staff requested details on equipment that may (a) not have adequate voltage to operate, (b) trip due to automatic protection such as overload relay actuations, (c) trip but will require manual action to reset the protective device, and, (d) degrade and may not be able to perform its required function.
The licensee's response states that based on the degraded voltage relay setting (3675V) that automc;J.tically separates the A and B train emergency buses from the grid, motors associated with Unit 2 'B' Train Spent Fuel Pool Ventilation Radiation Monitor (RE0025B) and the Unit 1 and 2 (i.e. shared) 'B' Train Control Room Radiation Monitor (RE0035B) may not operate. These motors may trip and manual actions may be necessary to actuate the safety function of the associated equipment.
The licensee response did not identify any time critical equipment required for mitigating the consequences of an event. 2. The NRC staff requested details on the grid contingencies that were evaluated to ensure the switchyard voltages remain above the voltages required for safe shutdown of the plant. In response, the licensee stated that over a five year period, the 230kV system voltage was within the desired range of 101 .6 to 104.5 percent of nominal during the vast majority of the time. In addition, the Southern Company Planning studies for current year and projected 5 years include analyses for bounding system load and generation with contingencies that include simulation of accident loads at one FNP unit and controlled shutdown of the other unit. The analyses also consider loss of the largest generating unit and loss of critical transmission elements.
Transmission system operators associated with FNP also use a state estimator real-time contingency analysis (RTCA) tool to simulate system loading conditions, actual generation, and transmission line configuration 1 ADAMS Package Accession No. ML 141 04A894
/ data. The RTCA is updated every 1 0-20 minutes and if any next contingency condition could result in a post-contingency grid voltage less than the minimum voltage required by FNP, the plant operators are informed.
The licensee has stated that the tools used for transmission system analyses, the RTCA, coupled with real time monitoring by plant operators has helped maintain the 230kV system voltage at or above the minimum requirements.
- 3. In response to a question about timely operator actions required for protection of safety related equipment, the licensee stated no operator actions are required since the overload relays would protect the only equipment (RE0025B and RE0035B) that may not have adequate voltages.
- 4. The NRC staff requested the licensee provide justification of the proposed schedule to complete the degraded grid voltage modifications, including explaining the need for implementing over two outages, rather than one outage. The licensee stated the proposed schedule is needed to support the time necessary to design the modifications, to develop the technical basis, to submit the amendment, and for NRC review and approval.
The licensee responded that implementing the modifications in one outage would require both safety related electrical 4kV buses to be removed from service and noted that limiting work to one train improves outage safety. 5. The NRC staff requested the licensee identify the compensatory actions and details of the consequences on accident analysis as a result of any delay in equipment restoration by the proposed manual actions. The compensatory actions are primarily manual operator actions contained in the licensees Degraded Grid procedures.
The licensee stated that the consequences of a degraded grid condition concurrent with an accident condition at one unit requiring safe shut down of both units can be managed with minimal manual actions .. The equipment that may malfunction due to the inherent delay associated with manual actions is protected by overcurrent relays and can be restored in a timely manner. The licensee did not identify any time critical mitigating components that may adversely impact an accident concurrent with degraded offsite power system. 6. The staff also reviewed the licensee's reasoning for the ability to monitor and predict offsite power system performance and the consequences of not automatically isolating plant safety busses during degraded voltage conditions below an acceptable level. Conclusion Based on the licensee's responses in letter dated May 21, 2013, and summarized below that:
- no time critical equipment is required to mitigate the consequences of an event; o no operator actions are required for protection of safety related equipment;
- equipment that may malfunction due to the inherent delay associated with manual actions is protected by overcurrent relays and can be restored in a timely manner;
- grid contingencies were evaluated to ensure the switchyard voltages remain above the voltages required for safe shutdown of the plant; *
- the licensee has the ability to monitor and predict offsite power system performar:tce;
- the proposed length of time requested to redesign the degraded voltage scheme and implement the degraded voltage plant modifications, The NRC staff finds the licensee's interim actions and evaluations acceptable to provide assurance of safety until the plant modifications are implemented to comply with the requirements of GDC 17 and 10 CFR 50.55a(h)(2).
The proposed amendment to the license conditions in FNP FOL Appendix C is adequate to require the completion of the plant modification.
Therefore, the staff finds the proposed license amendment acceptable.
3.2 Health
Physics and Human Performance Description of Operator Action(s) and Assessed Safety Significance When bus voltage remains less than 3850 Volts (V) for greater,than one hour, Technical Specifications (TSs) 3.3.5, D, E, and F require operators to isolate the plant from the grid and ( reduce power mode or shut down. In addition, operators are required to perform the following compensatory actions:
- Manually reset the protective device for the 'B' Train Control Room Radiation Monitor (RE0035B) motor.
- Manually reset the protective device for the 'B' Train Spent Fuel Pool Radiation Monitor (RE0025B) motor. The two compensatory actions are considered "low risk" due to the fact that failure of these actions would not cause any serious consequence, i.e., even if no actions were taken, overload relays would protect RE0025B and RE0035B motors. Human-System Interface Design Human-System Interface design, including the design of the Safety Parameter Display System will not be affected by the proposed LAR. Annunciators, alarms, controls, and displays are unchanged and operators are well-practiced in their use. Procedure Design No changes are required to the Emergency Operating Procedures.
Because the proposed interim actions are not new actions, the existing abnormal operating procedure (Procedure FNP-1/ 2-AOP-5.2) does not require any changes. The NRC staff finds the existing procedure acceptable based on its use during operator continuing training. Training Program and Simulator Design Based on the fact that the proposed actions have a long history of successful implementation, and are included in operator continuing training, the NRC staff concludes that additional training is not necessary.
Based on the above, the NRC staff finds that the training already provided is acceptable.
Conclusion Based on the statements provided by SNC, i.e., that appropriate administrative controls will be applied to procedu-res and training, and that both units have substantial in-house operating experience, the staff concludes that both the compensatory actions proposed in this LAR and the Technical Specification required actions are acceptable from the human performance point of view.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of Alabama official was notified of the proposed issuance of the amendments.
The State official had no comments.
5.0 ENVIRONMENTAL
CONSIDERATION The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined tha:t the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (78 FR 54289, September 3, 2013). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 1 0 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributors:
G.S. Matharu, NRR/EEEB Roy Mathew, NRR/EEEB George Lapinsky, NRR/AHPB Date: May 13, 2014 Mr. C. R. Pierce Regulatory Affairs Director May 13, 2014 Southern Nuclear Operating Company, Inc. P. 0. Box 1295 I Bin -038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS TO INCORPORATE THE SCHEDULE FOR DEGRADED GRID VOLTAGE MODIFICATION (TAC NOS. MF0468 AND MF0469)
Dear Mr. Pierce:
By letter dated December 21, 2012, as supplemented by letter dated May 21, 2013, Southern Nuclear Operating Company (SNC) proposed to revise the Farley Nuclear Plant (FNP) Unit 1 and Unit 2 Facility Operating Licenses, to include a schedule to implement degraded voltage modifications.
The modifications would include automatic actions and thus eliminate the need for manual actions in the event of a degraded grid voltage condition.
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 194 to Renewed Facility Operating License No. NPF-2, Unit 1, and Amendment No. 190 to Renewed Facility Operating License No. NPF-8, Unit 2. A copy of the related Safety Evaluation is also enclosed.
A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. If you have any questions, please call me at 301-415-1009.
Docket Nos. 50-348 and 50-364
Enclosures:
Sincerely, /RAJ Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1. Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 1. Amendment No. 194 to NPF-2 2. Amendment No. 190 to NPF-8 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
Public LPL2-1 R/F RidsAcrs_AcnwMaiiCTR Resource RidsNrrDoriDpr Resource SWilliams, NRR ADAMS A ccess1on N ML 14069A344 o.: OFFICE LPL2-1/PM NAME SWilliams DATE 03/13/14 OFFICE LPL2-1/BC NAME RPascarelli DATE 05/12/14 RidsNrrDssStsb Resource RidsNrrLASFigueroa Resource RidsRgn2MaiiCenter Resource RMathew, NRR RidsNrrPMSummer Resource RidsNrrDraApla Resource BGurjendra, NRR Glapinsky, NRR *8 ly memo LPL2-1/LA DE/EPNB/BC*
DRA/AHPB/BC OGC SFigueroa JZimmerman S.Weerakkody MYoung /NLO 03/12/14 03/07/14 03/13/14 05/07/14 LPL2-1/PM SWilliams 05/13/14 OFFICIAL RECORD COPY