Letter Sequence Other |
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MONTHYEARML0424304632004-08-18018 August 2004 Units 1 and 2 - Technical Specification (TS) Change No. 04-03, Reactor Coolant System (RCS) and Emergency Core Cooling System (ECCS) Enhancements Project stage: Request ML0504806692005-03-0909 March 2005 License Amendments 299 and 288, RCS & ECCS Enhancements Project stage: Other ML0507303032005-03-0909 March 2005 Tech Spec Pages Amendments 299 and 288, RCS & ECCS Enhancements Project stage: Other 2004-08-18
[Table View] |
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Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request ML23254A2192023-09-11011 September 2023 Emergency Plan Implementing Procedure Revisions ML23254A0652023-09-0707 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 ML23233A0122023-08-17017 August 2023 Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement ML23233A0142023-08-15015 August 2023 Discharge Monitoring Report (Dmr), July 2023 ML23215A1212023-08-0303 August 2023 301 Exam Administrative Items (2B) Normal Release ML23215A1572023-08-0303 August 2023 Enforcement Action EA-22-129 Inspection Readiness Notification CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 2024-01-04
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML22334A0732023-02-0606 February 2023 Issuance of Amendment Nos. 363 and 357 Regarding Modification of the Approved Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22259A2042022-09-29029 September 2022 Correction to Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22210A1182022-08-24024 August 2022 Issuance of Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22108A2822022-04-27027 April 2022 Summary of Regulatory Audit Regarding the License Amendment Request to Revise TS to Adopt TSTF 505, Rev. 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML21308A4932021-11-0808 November 2021 Pre-submittal Meeting Presentation - License Amendment Request to Revise Sequoyah Operating License to Use Fire and Seismic PRA Models for 10 CFR 50.69 Risk-Informed Categorizations (EPID L-2021-LRM-0109) (Slides) ML21298A0312021-10-27027 October 2021 Issuance of Exigent Amendment No. 350 Regarding One-Time Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System, ML21245A2672021-10-27027 October 2021 NON-PROPRIETARY - Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 356 and 349 Regarding the Transition to Westinghouse Robust Fuel Assembly-2 (RFA-2) Fuel ML21084A1902021-05-0404 May 2021 Issuance of Amendment Nos. 355 and 348 Regarding Revision to Technical Specification Table 3.3.3-1, Post Accident Monitoring Instrumentation ML21021A3492021-03-0303 March 2021 Issuance of Amendment Nos. 354 and 347 Regarding Revision to Technical Specification 4.2.2, Control Rod Assemblies ML20337A0372021-02-0101 February 2021 Issuance of Amendment No. 353 Regarding Steam Generator Tube Inspection Frequency ML20350B4932021-01-25025 January 2021 Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20262H0262020-11-12012 November 2020 Issuance of Amendment Nos. 349 and 343 Regarding Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure ML20108F0492020-04-23023 April 2020 Issuance of Amendment No. 342 Exigent Amendment to Operate One Cycle with One Control Rod Removed ML19319C8312019-11-21021 November 2019 Issuance of Exigent Amendment No. 348 to Operate One Cycle with One Control Rod Removed ML19281B5542019-11-18018 November 2019 Issuance of Amendment Nos. 347 and 341 Request to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19179A1352019-09-18018 September 2019 Issuance of Amendment Nos. 346 and 340, Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19196A2212019-07-18018 July 2019 Issuance of Exigent Amendment Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable ML19058A0292019-05-0707 May 2019 Issuance of Amendments Request to Modify Essential Raw Cooling Water Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) ML18159A4612018-08-0606 August 2018 Issuance of Amendments Regarding Request to Change Emergency Plan ML18138A4522018-05-29029 May 2018 Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20 ML17289A0322017-12-22022 December 2017 Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160) ML17034A3602017-03-27027 March 2017 Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ... ML16228A0962016-10-0303 October 2016 Issuance of Amendments to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 ML16225A2762016-09-29029 September 2016 Issuance of Amendments to Revise Technical Specification for Essential Raw Cooling Water System Allowed Completion Time ML15320A2182015-11-30030 November 2015 Issuance of Amendments to Revise Technical Specification for Containment Leakage Rate Program ML15238B4602015-09-30030 September 2015 Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues ML15100A0492015-09-28028 September 2015 SQN U2 Renewed License v2 ML15100A0462015-09-28028 September 2015 SQN U1 Renewed License v2 ML12249A3942012-09-26026 September 2012 Issuance of Amendments to Revise the Technical Specification to Allow Use of Areva Advanced W17 High Thermal Performance Fuel (TS-SQN-2011-07) ML12234A3812012-09-0606 September 2012 Issuance of Amendment Regarding the Proposed Operating License and Technical Specification Changes for Unit 2 Replacement Steam Generator Project to Conduct Heavy Load Lifts ML1121605932011-06-0303 June 2011 Sequoya Retake Initial Exam 2011-301 Final Administrative Documents ML1029900742010-12-21021 December 2010 License Amendment, Issuance of Amendments to Revised Technical Specifications to Resolve an Oversight Regarding the Operability Requirements for the Intermediate Range Neutron Flux Channels (TS-09-05) ML0933104032010-01-28028 January 2010 Issuance of Amendments Regarding Upgrade of Emergency Core Cooling System Requirements Per NUREG-1431 (TS 07-05) ML0928103332009-10-19019 October 2009 License Amendment, Issuance of Amendment to Allow Use of the W* Alternate Repair Criteria for Steam Generator Tubes (TS-09-02) ML0916107192009-08-14014 August 2009 License Amendment, Issuance of Amendments Regarding Revisions to the Ice Condenser Licensing Basis (TS 08-06) ML0909303302009-06-12012 June 2009 Issuance of Amendment Regarding Removal of Main Steam Isolation Valve Closure Times (TS 08-04) ML0905601262009-04-13013 April 2009 Issuance of Amendment Regarding Eliminating the Time Limit on Purge and Vent Valve Operations and Consolidating Containment Isolation Valve Specifications ML0832602412008-12-0404 December 2008 Issuance of Amendment Regarding Technical Specifications for Reactor Coolant System (RCS) Leakage Detection Systems ML0824706282008-09-24024 September 2008 License Amendment, Issuance of Amendment Regarding Core Operating Limits Report References for Realistic Large Break Loss-Of-Coolant Accident Methodology ML0824013852008-08-29029 August 2008 Issuance of Amendments 319 and 312 Regarding Auxiliary Feedwater Start Upon Trip of Main Feedwater Pumps ML0808103532008-04-10010 April 2008 Revision of Core Operating Limits Report (COLR) References for Realistic Large Break Loca Methodology Minimum Containment Pressure 2024-01-29
[Table view] Category:Safety Evaluation
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22334A0732023-02-0606 February 2023 Issuance of Amendment Nos. 363 and 357 Regarding Modification of the Approved Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22304A1862022-12-0101 December 2022 Revised Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage ML22284A0072022-11-0707 November 2022 Authorization of Alternative Request RP-12 for Testing of Centrifugal Charging Pump 1B-B ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22272A5682022-10-12012 October 2022 Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code ML22259A2042022-09-29029 September 2022 Correction to Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22263A3752022-09-29029 September 2022 Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage ML22210A1182022-08-24024 August 2022 Issuance of Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22165A1052022-07-12012 July 2022 Issuance of Amendment Nos. 357 and 351 Regarding Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation ML22084A0012022-04-0505 April 2022 Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes ML21298A0312021-10-27027 October 2021 Issuance of Exigent Amendment No. 350 Regarding One-Time Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System, ML21245A2672021-10-27027 October 2021 NON-PROPRIETARY - Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 356 and 349 Regarding the Transition to Westinghouse Robust Fuel Assembly-2 (RFA-2) Fuel ML21266A3832021-10-0101 October 2021 Authorization of Alternative Request RP-10 for the 1B-B Motor Driven Auxiliary Feedwater Pump ML21131A1632021-05-28028 May 2021 Authorization and Safety Evaluation for Alternative Request No. 21-ISI-1 ML21084A1902021-05-0404 May 2021 Issuance of Amendment Nos. 355 and 348 Regarding Revision to Technical Specification Table 3.3.3-1, Post Accident Monitoring Instrumentation ML21021A3492021-03-0303 March 2021 Issuance of Amendment Nos. 354 and 347 Regarding Revision to Technical Specification 4.2.2, Control Rod Assemblies ML20337A0372021-02-0101 February 2021 Issuance of Amendment No. 353 Regarding Steam Generator Tube Inspection Frequency ML20350B4932021-01-25025 January 2021 Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20262H0262020-11-12012 November 2020 Issuance of Amendment Nos. 349 and 343 Regarding Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure ML20108F0492020-04-23023 April 2020 Issuance of Amendment No. 342 Exigent Amendment to Operate One Cycle with One Control Rod Removed ML19319C8312019-11-21021 November 2019 Issuance of Exigent Amendment No. 348 to Operate One Cycle with One Control Rod Removed ML19281B5542019-11-18018 November 2019 Issuance of Amendment Nos. 347 and 341 Request to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19234A0132019-09-23023 September 2019 Alternative Request 18-ISI-1 Regarding Examination of Dissimilar Metal Welds in Reactor Vessel Head ML19179A1352019-09-18018 September 2019 Issuance of Amendment Nos. 346 and 340, Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19227A1102019-08-26026 August 2019 Alternative Request for the Turbine Driven Auxiliary Feedwater Pumps 10-Year Interval Inservice Testing Program ML19196A2212019-07-18018 July 2019 Issuance of Exigent Amendment Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable ML19058A0292019-05-0707 May 2019 Issuance of Amendments Request to Modify Essential Raw Cooling Water Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) ML19010A2742019-03-18018 March 2019 Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority ML18197A3072018-08-30030 August 2018 Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4 ML18159A4612018-08-0606 August 2018 Issuance of Amendments Regarding Request to Change Emergency Plan ML18138A4522018-05-29029 May 2018 Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20 ML17289A0322017-12-22022 December 2017 Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160) ML17034A3602017-03-27027 March 2017 Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ... ML16340A0092017-03-0909 March 2017 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17059B7912017-03-0202 March 2017 Sequoyah Nuclear Plant, Units 1 and 2 - Relief from the Requirements of the American Society of Mechanical Engineer OM Code (CAC Nos. MF9305 and MF9306) ML16228A0962016-10-0303 October 2016 Issuance of Amendments to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 ML16225A2762016-09-29029 September 2016 Issuance of Amendments to Revise Technical Specification for Essential Raw Cooling Water System Allowed Completion Time ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16123A1312016-05-12012 May 2016 Relief Requests RP-01, RP-02, RP-06, RP-08, and RV-01 Related to the Inservice Testing Program, Fourth 10-Year Interval (CAC Nos. MF7099 and MF7100) ML15329A1862015-12-0404 December 2015 Request for Relief PR-07 for Alternative Inservice Pump Testing at Reference Values ML15320A2182015-11-30030 November 2015 Issuance of Amendments to Revise Technical Specification for Containment Leakage Rate Program 2024-01-29
[Table view] |
Text
March 9, 2005 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 ISSUANCE OF AMENDMENTS REGARDING REACTOR COOLANT SYSTEM AND EMERGENCY CORE COOLING SYSTEM ENHANCEMENTS (TAC NOS.
MC4199 AND MC4200)
Dear Mr. Singer:
The Commission has issued the enclosed Amendment No. 299 to Facility Operating License No. DPR-77 and Amendment No. 288 to Facility Operating License No. DPR-79 for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively. These amendments are in response to your application dated August 18, 2004 (TVA-SQN-04-03).
The amendments revise Technical Specification (TS) 3/4.4.2, Safety Valves - Shutdown, TS 3/4.4.3, Safety and Relief Valves - Operating, and TS 3/4.5.2, ECCS Subsystems - Tavg Greater Than or Equal to 350EF. TS 3/4.4.2 is eliminated because overpressure protection of the reactor coolant system does not rely upon the pressurizer safety valves during plant operation in Modes 4 and 5. TS 3/4.4.3 is revised to remove redundancy and add improvements consistent with NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants. TS 3/4.5.2 is revised by adding a note to the Limiting Condition for Operation (LCO) supporting transition to and from LCO 3.4.12, Low Temperature Overpressure Protection (LTOP) System. These changes are improvements to the current SQN TSs and are consistent with the safety analyses and NUREG-1431, Revision 3.
K. Singer March 9, 2005 A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. Amendment No. 299 to License No. DPR-77
- 2. Amendment No. 288 to License No. DPR-79
- 3. Safety Evaluation cc w/enclosures: See next page
K. Singer A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. Amendment No. 299 to License No. DPR-77
- 2. Amendment No. 288 to License No. DPR-79
- 3. Safety Evaluation cc w/enclosures: See next page DISTRIBUTION:
PUBLIC PDII-2 R/F KDesai DCoe TBoyce OGC ACRS GHill (2) MMarshall DLPM DPR BClayton DPickett SCahill, R2 CHarbuck EHackett Package No.: ML050480671 TS: ML050730303 ADAMS ACCESSION NO.: ML050480669 *No Legal Objection NRR-058 OFFICE PM:LPD2-2 LA:LPD2-2 SC:SRXB SC:IROB OGC SC:LPD2-2 NAME DPickett BClayton DCoe TBoyce Tsmith NLO w/ edits MMarshall DATE 02 / 24 /05 02 / 24 /05 02 / 14 /05 03/ 4 /05 03 / 7 /05 03 / 09 /05 OFFICIAL RECORD COPY
Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Paul L. Pace, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority ATTN: James D. Smith 6A Lookout Place Sequoyah Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Larry S. Bryant, General Manager Nuclear Engineering Mr. David A. Kulisek, Plant Manager Tennessee Valley Authority Sequoyah Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Soddy Daisy, TN 37384-2000 Mr. Randy Douet Senior Resident Inspector Site Vice President Sequoyah Nuclear Plant Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road P.O. Box 2000 Soddy Daisy, TN 37379 Soddy Daisy, TN 37384-2000 Mr. Lawrence E. Nanney, Director General Counsel Division of Radiological Health Tennessee Valley Authority Dept. of Environment & Conservation ET 11A Third Floor, L and C Annex 400 West Summit Hill Drive 401 Church Street Knoxville, TN 37902 Nashville, TN 37243-1532 Mr. John C. Fornicola, Manager County Mayor Nuclear Assurance and Licensing Hamilton County Courthouse Tennessee Valley Authority Chattanooga, TN 37402-2801 6A Lookout Place 1101 Market Street Ms. Ann P. Harris Chattanooga, TN 37402-2801 341 Swing Loop Road Rockwood, Tennessee 37854 Mr. Fredrick C. Mashburn Senior Program Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 299 License No. DPR-77
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Tennessee Valley Authority (the licensee) dated August 18, 2004, 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 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.
- 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 Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 299, are hereby incorporated in the license. The licensee 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 by May 15, 2005.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Michael L. Marshall, Jr., Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 299 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT VI VI 3/4 4-3 3/4 4-3 3/4 4-4 3/4 4-4 3/4 4-4a 3/4 4-4a 3/4 5-4 3/4 5-4
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 288 License No. DPR-79
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Tennessee Valley Authority (the licensee) dated August 18, 2004, 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 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.
- 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 Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 288, are hereby incorporated in the license. The licensee 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 by the completion of the 2005 Sequoyah Unit 2 Cycle 13 Refueling Outage.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Michael L. Marshall, Jr., Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 288 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT VI VI 3/4 4-6 3/4 4-6 3/4 4-7 3/4 4-7 3/4 4-8 3/4 4-8 3/4 5-4 3/4 5-4
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 288 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 299 TO FACILITY OPERATING LICENSE NO. DPR-79 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328
1.0 INTRODUCTION
By application dated August 18, 2004 (Agencywide Documents Access and Management Systems Accession No. ML042430463), the Tennessee Valley Authority (the licensee) proposed amendments to the Technical Specifications (TSs) for Sequoyah Nuclear Plant (SQN)
Units 1 and 2.
The proposed TS changes will revise TS 3/4.4.2, Safety Valves - Shutdown, 3/4.4.3, Safety and Relief Valves - Operating, and 3/4.5.2, ECCS [Emergency Core Cooling System]
Subsystems - Tavg Greater Than or Equal to 350 EF. TS 3/4.4.2 will be eliminated because overpressure protection of the reactor coolant system does not rely upon the pressurizer safety valves during plant operation in Modes 4 and 5. TS 3/4.4.3 will be revised to remove redundancy and add improvements consistent with NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants. TS 3/4.5.2 will be revised by adding a note to the Limiting Condition for Operation (LCO) supporting transition to and from LCO 3.4.12, Low Temperature Overpressure Protection (LTOP) System. These changes are improvements to the current SQN TSs and are consistent with the safety analyses and NUREG-1431, Revision 3.
2.0 REGULATORY EVALUATION
The Commissions regulatory requirements related to the contents of TSs are set forth in Title 10, Code of Federal Regulations (10 CFR) Section 50.36, which ensures that the TS-specified LCO is consistent with assumed values of the initial conditions in the licensees safety analyses. In accordance with 10 CFR 50.36, the NRC staff and the Nuclear Steam System Supplier Owners Groups developed improved standard technical specifications which meets 10 CFR 50.36(c)(2)(ii) and 10 CFR 50.36(c)(3) requirements. The licensee is using the NRC staff approved NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants.
General Design Criterion (GDC) 15, Reactor Coolant System Design, of Appendix A, General Design Criteria, to 10 CFR Part 50, provides design considerations for the reactor coolant system (RCS). TS 3/4.4.2 and TS 3/4.4.3 involve the RCS.
GDC 35, Emergency Core Cooling, of Appendix A to 10 CFR Part 50, provides design considerations for the ECCS. TS 3/4.5.2 involves the ECCS.
3.0 TECHNICAL EVALUATION
3.1 TS 3/4.4.2, Safety Valves - Shutdown Each SQN unit is equipped with three safety valves and two power operated relief valves (PORVs) which are connected to the pressurizer and provide overpressure protection, in conjunction with the reactor protection system for the RCS. TS 3/4.4.3, Safety and Relief Valves - Operating, requires that the pressurizer safety valves be operable during Modes 1, 2, and 3 with a lift setting of 2485 psig, +/- 3 percent. This ensures that RCS overpressure protection is provided during power operation. The pressurizer PORVs provide protection during the lower Modes of operation (Modes 4, 5, and 6) as part of the LTOP. The proposed changes are as follows:
TS 3/4.4.2, Safety Valves - Shutdown, is proposed to be deleted from the SQN TSs. The LCO currently states : A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2485 psig +/- 3 %. This TS is applicable to lower Modes of operation (Modes 4 and 5).
TS 3/4.4.3.1 requires that safety valves be operable during Modes 1, 2, and 3 with a lift setting of 2485 psig, +/- 3 percent. Below Mode 3, the RCS temperature is below 350 oF and the RCS pressure is significantly lower than the safety valve setpoint. The pressurizer safety valves are not credited for overpressure protection during Modes 4 and 5. For SQN, the pressure temperature limits report provides LTOP arming temperature of 350 oF. This temperature coincides with the Mode 3/Mode 4 transition temperature. The SQN LTOP system is armed during plant shutdown immediately following entry into Mode 4 when RCS temperature reaches less than 350 oF. The LTOP system is enabled and designed to protect the RCS from any overpressure condition during low temperature plant conditions. TS 3/4.4.12, Low Temperature Over Pressure Protection (LTOP) System, governs the operability requirements for the LTOP system during Modes 4, 5, and Mode 6 with the reactor vessel head on. Thus, RCS overpressure protection will be maintained during the lower Modes of operation and, therefore, there is no need to require one pressurizer safety valve to be OPERABLE during Modes 4 and 5. Therefore, the proposed change to delete TS 3/4.4.2 is acceptable.
3.2 TS 3/4.4.3, Safety and Relief Valves - Operating 3.2.1 TS 3.4.3.1, Safety Valves - Operating The proposed change revises the current action requirements to incorporate improved standard TS action requirements. The current Action statement for TS 3.4.3.1 is as follows:
With one pressurizer code safety valve inoperable, either restore the inoperable valve to operable status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The licensee proposes to revise the Action statement to become:
a) With one pressurizer safety valve inoperable, restore the inoperable valve to OPERABLE within 15 minutes.
b) With two or more pressurizer safety valves inoperable or with ACTION (a) above not completed within 15 minutes, be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in MODE 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The staff finds the proposed change acceptable because it provides better clarity and it will be consistent with NUREG-1431, Revision 3 requirements.
3.2.2 TS 3.4.3.2, Relief Valves - Operating TS 3.4.3.2 demonstrates operability of the PORVs during Modes 1, 2, and 3. Surveillance Requirement (SR) 4.4.3.2.1.a requires performance of a channel calibration of PORV actuation circuitry once every 18 months. However, SR 4.4.12.1.b (from TS 3/4.4.12, which is applicable in Modes 4, 5, and 6) also requires performance of a channel calibration of PORV actuation circuitry once every 18 months. In order to eliminate duplicity, the licensee has proposed to delete SR 4.4.3.2.1.a. The staff agrees that PORV actuation circuitry will be ensured through performance of SR 4.4.12.1.b. Therefore, the staff finds it acceptable to eliminate SR 4.4.3.2.1.a.
3.3. TS 3/4.5.2, ECCS Subsystems - Tavg Greater Than or Equal to 350 oF The proposed change will add a standard notation from NUREG-1431, Revision 3, to this LCO which states as follows:
In MODE 3, ECCS pumps may be made incapable of injecting to support transition into or from the APPLICABILITY of LCO 3.4.12, Low Temperature Overpressure Protection (LTOP)
System, for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or until the temperature of all RCS cold legs exceed LTOP arming temperature specified in the pressure temperature limits report (PTLR) plus 25 oF, whichever comes first.
For SQN, LTOP arming temperature is near the Mode 3 boundary temperature of 350 oF.
TS 3/4.4.12- LTOP, requires that certain ECCS pumps be rendered incapable of injecting at and below the LTOP arming temperature. When RCS temperature is at or near the Mode 3 boundary temperature, time is needed to make the pumps incapable of injecting prior to entering the LTOP applicability, and provide time to restore the inoperable pumps to operable status on exiting the LTOP applicability. The 4-hour time allowance is based on a reasonable time for the operator to perform this task under controlled plant conditions. The temperature 375 oF is based on a 25 oF margin above the 350 oF LTOP arming temperature. This provision is intended to minimize the chances of a cold overpressurization event.
This notation is consistent with the NUREG-1431, Revision 3. The staff finds the proposed change reasonable and necessary for operational flexibility. Therefore, the staff finds the proposed change acceptable.
3.4 Summary The NRC staff has reviewed the proposed TS changes and finds these changes in compliance with 10 CFR 50.36 criteria. Also these TS changes are consistent with the safety analyses and conform to NUREG-1431, Revision 3 guidelines. We find these changes are an improvement to the SQN TSs. The NRC staff concludes that the proposed TS changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that 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 (69 FR 64991). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 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) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: K. Desai Dated: March 9, 2005