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MONTHYEARML20282A3452020-11-19019 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 Project stage: Approval 2020-11-19
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24032A0202024-01-31031 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 ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) 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 ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-069, 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 IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public 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) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan 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 ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation 2024-02-01
[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 ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) ML23116A2472023-05-23023 May 2023 Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 ML23101A1102023-05-16016 May 2023 Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) ML23073A2902023-05-0202 May 2023 Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times 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 ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary 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 ML22327A0182022-12-0101 December 2022 Correction of Error Incurred During Issuance of License Amendment No. 322 ML22273A1032022-11-22022 November 2022 Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification ML22220A2602022-11-21021 November 2022 Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A ML22257A0512022-11-0404 November 2022 Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A 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 ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps 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 ML22138A3252022-06-24024 June 2022 Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis ML22014A2062022-05-0404 May 2022 Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors 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 ML22020A2282022-03-16016 March 2022 Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2 ML21347A9672022-02-0101 February 2022 Correction of Errors Incurred During Issuance of the Initial Facility Operating License, and Issuance of License Amendment Nos. 6, 21, and 39 ML21306A2872022-01-25025 January 2022 Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement ML21334A2952022-01-18018 January 2022 Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement ML21334A3892022-01-12012 January 2022 Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis ML21271A1372021-12-16016 December 2021 Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level 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) ML21189A3072021-11-0303 November 2021 Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 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 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, ML21158A2842021-09-17017 September 2021 Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21173A1772021-07-27027 July 2021 Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21153A0492021-07-26026 July 2021 Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510 ML21161A2392021-06-24024 June 2021 Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria ML21148A1002021-06-17017 June 2021 Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology ML21099A2462021-05-14014 May 2021 Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21078A4842021-05-0505 May 2021 Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications 2024-01-03
[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 ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23116A2472023-05-23023 May 2023 Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control ML23101A1102023-05-16016 May 2023 Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) ML23073A2902023-05-0202 May 2023 Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times 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 ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage 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 ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary 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 ML22273A1032022-11-22022 November 2022 Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification ML22220A2602022-11-21021 November 2022 Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22293A4082022-11-14014 November 2022 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML22284A0072022-11-0707 November 2022 Authorization of Alternative Request RP-12 for Testing of Centrifugal Charging Pump 1B-B ML22257A0512022-11-0404 November 2022 Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A 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 ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train 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 ML22138A3252022-06-24024 June 2022 Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis ML22014A2062022-05-0404 May 2022 Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors 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 ML22070A0022022-03-28028 March 2022 Review of the Fall 2021 Mid Cycle Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Report ML22020A2282022-03-16016 March 2022 Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2 ML21306A2872022-01-25025 January 2022 Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement ML21334A2952022-01-18018 January 2022 Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21334A3892022-01-12012 January 2022 Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis ML21271A1372021-12-16016 December 2021 Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level ML21189A3072021-11-0303 November 2021 Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 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 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, ML21266A3832021-10-0101 October 2021 Authorization of Alternative Request RP-10 for the 1B-B Motor Driven Auxiliary Feedwater Pump 2024-01-03
[Table view] Category:Technical Specifications
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 CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) 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 ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary 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 ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) WBL-22-017, Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2022-03-22022 March 2022 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21158A2842021-09-17017 September 2021 Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21099A2462021-05-14014 May 2021 Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21078A4842021-05-0505 May 2021 Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications 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 ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 ML21015A0342021-03-0909 March 2021 Issuance of Amendment No. 144 Regarding 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 ML21034A1692021-02-26026 February 2021 Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology ML20232C6222021-02-11011 February 2021 Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037 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 ML20226A4442020-10-21021 October 2020 Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate ML20273A0432020-09-29029 September 2020 Plants Unit 1 and 2 - Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual ML20190A1052020-08-11011 August 2020 Correction to Amendment No. 319 Regarding Revisions to Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation ML20156A0182020-08-10010 August 2020 Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific2020-03-0202 March 2020 Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specificat ML20028F7332020-02-28028 February 2020 Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML19276E5572019-12-0909 December 2019 Issuance of Amendment Nos. 130 and 33 Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML19238A0052019-11-26026 November 2019 Issuance of Amendment Nos. 129 and 32 Regarding Changes to Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9 ML19319C8312019-11-21021 November 2019 Issuance of Exigent Amendment No. 348 to Operate One Cycle with One Control Rod Removed CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)2019-09-30030 September 2019 Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2019-08-29029 August 2019 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19112A0042019-07-25025 July 2019 Issuance of Amendment Nos. 127 and 30 Regarding the Use of Optimized Zirlo Fuel Rod Cladding ML19098A7742019-06-0707 June 2019 Issuance of Amendments Regarding Technical Specifications Changes Pertaining to 120-Volt Alternating Current Vital Buses ML18255A1562018-10-30030 October 2018 Issuance of Amendment to Modify Technical Specification 3.3.1 Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) ML18079A0292018-06-26026 June 2018 Issuance of Amendments Regarding Adoption of TSTF-547, Clarification of Rod Position Requirements (CAC Nos. MF8912and MF8913; EPID L-2016-LLA-0034) ML17311A7862017-12-0707 December 2017 Issuance of Amendment Regarding Ventilation Filter Testing Program (CAC No. MF9584; EPID L-2017-LLA-0207) 2024-01-09
[Table view] |
Text
November 19, 2020 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3; SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2; WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 313, 336, 296, 350, 344, 138, AND 44 RE: REVISE EMERGENCY PLAN ON-SHIFT EMERGENCY MEDICAL TECHNICIAN AND ON-SITE AMBULANCE REQUIREMENTS (EPID L-2020-LLA-0175)
Dear Mr. Barstow:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 313, 336, and 296 to Renewed Facility Operating Licenses Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant, Units 1, 2, and 3, respectively; Amendment Nos. 350 and 344 to Renewed Facility Operating License Nos. DPR-77 and DPR-79 for the Sequoyah Nuclear Plant, Units 1 and 2, respectively; Amendment Nos. 138 and 44 to Facility Operating License Nos. NPF-90 and NPF-96 for the Watts Bar Nuclear Plant, Units 1 and 2, respectively. These amendments are in response to your application dated July 31, 2020.
The amendments revise the Radiological Emergency Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3; Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2; to change the requirement from having an on-shift emergency medical technician to a requirement for an on-shift emergency medical professional. Additionally, the amendments remove the requirement for an on-site ambulance at each site.
J. Barstow A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Michael J. Wentzel, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, 50-391,72-034, 72-052, and 72-1048
Enclosures:
- 1. Amendment No. 313 to DPR-33
- 2. Amendment No. 336 to DPR-52
- 3. Amendment No. 296 to DPR-68
- 4. Amendment No. 350 to DPR-77
- 5. Amendment No. 344 to DPR-79
- 6. Amendment No. 138 to NPF-90
- 7. Amendment No. 44 to NPF-96
- 8. Safety Evaluation cc: Listserv
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 313 Renewed License No. DPR-33
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA), dated July 31, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, by Amendment No. 313, Renewed Facility Operating License No. DPR-33 is hereby amended to authorize revision to the TVA Radiological Emergency Plan, as set forth in TVAs application dated July 31, 2020, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Mirela Mirela Gavrilas Date: 2020.11.19 Gavrilas 17:07:16 -05'00' Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: November 19, 2020
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 336 Renewed License No. DPR-52
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA), dated July 31, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 2
- 2. Accordingly, by Amendment No. 336, Renewed Facility Operating License No. DPR-52 is hereby amended to authorize revision to the TVA Radiological Emergency Plan, as set forth in TVAs application dated July 31, 2020, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Mirela Mirela Gavrilas Date: 2020.11.19 Gavrilas 17:07:45 -05'00' Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: November 19, 2020
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 296 Renewed License No. DPR-68
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA), dated July 31, 2020, 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 Title 10 of the Code of Federal Regulations (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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 3
- 2. Accordingly, by Amendment No. 296, Renewed Facility Operating License No. DPR-33 is hereby amended to authorize revision to the TVA Radiological Emergency Plan, as set forth in TVAs application dated July 31, 2020, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Mirela Mirela Gavrilas Date: 2020.11.19 Gavrilas 17:08:12 -05'00' Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: November 19, 2020
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 350 Renewed License No. DPR-77
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA), dated July 31, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 4
- 2. Accordingly, by Amendment No. 350, Renewed Facility Operating License No. DPR-77 is hereby amended to authorize revision to the TVA Radiological Emergency Plan, as set forth in TVAs application dated July 31, 2020, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Mirela Mirela Gavrilas Date: 2020.11.19 Gavrilas 17:08:38 -05'00' Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: November 19, 2020
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 344 Renewed License No. DPR-79
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA), dated July 31, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 5
- 2. Accordingly, by Amendment No. 344, Renewed Facility Operating License No. DPR-79 is hereby amended to authorize revision to the TVA Radiological Emergency Plan, as set forth in TVAs application dated July 31, 2020, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Mirela Mirela Gavrilas Date: 2020.11.19 Gavrilas 17:09:06 -05'00' Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: November 19, 2020
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 138 License No. NPF-90
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA), dated July 31, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 6
- 2. Accordingly, by Amendment No. 138, Facility Operating License No. NPF-90 is hereby amended to authorize revision to the TVA Radiological Emergency Plan, as set forth in TVAs application dated July 31, 2020, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Mirela Mirela Gavrilas Date: 2020.11.19 Gavrilas 17:09:33 -05'00' Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: November 19, 2020
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 WATTS BAR NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF-96
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA), dated July 31, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
Enclosure 7
- 2. Accordingly, by Amendment No. 44, Facility Operating License No. NPF-96 is hereby amended to authorize revision to the TVA Radiological Emergency Plan, as set forth in TVAs application dated July 31, 2020, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Mirela Mirela Gavrilas Date: 2020.11.19 Gavrilas 17:10:00 -05'00' Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: November 19, 2020
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 313 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 33 AMENDMENT NO. 336 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 52 AMENDMENT NO. 296 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 68 AMENDMENT NO. 350 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-77 AMENDMENT NO. 344 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-79 AMENDMENT NO. 138 TO FACILITY OPERATING LICENSE NO. NPF-90 AMENDMENT NO. 44 TO FACILITY OPERATING LICENSE NO. NPF-96 BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 TENNESSEE VALLEY AUTHORITY DOCKET NOS. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, 50-391,72-034, 72-052, AND 72-1048
1.0 INTRODUCTION
By letter dated July 31, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20213C730), the Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Browns Ferry); Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah); and Watts Bar Nuclear Plant, Units 1 and 2 (Watts Bar). The requested changes would revise the Radiological Emergency Plan (REP) for Browns Ferry, Sequoyah, and Watts Bar by changing the emergency response organization at each of the sites to require an on-shift emergency medical professional rather than an on-shift emergency medical technician (EMT) and would remove the requirement for an on-site TVA ambulance at each site.
2.0 REGULATORY EVALUATION
The regulatory requirements and guidance on which the U.S. Nuclear Regulatory Commission (NRC, Commission) staff based its review are provided below.
Enclosure 8
2.1 Regulatory Requirements The planning standards in Section 50.47(b) of Title 10 of the Code of Federal Regulations (10 CFR) establish the requirements that the on-site and offsite emergency response plans must meet for the NRC staff to make a finding that there is reasonable assurance that the licensee can, and will, take adequate protective measures in the event of a radiological emergency. Specifically, on-shift and augmented emergency response organization staffing is addressed under the following planning standards:
10 CFR 50.47(b) states, in part:
The onsite and, except as provided in paragraph (d) of this section, offsite emergency response plans for nuclear power reactors must meet the following standards 10 CFR 50.47(b)(2) states:
On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.
10 CFR 50.47(b)(12) states:
Arrangements are made for medical services for contaminated injured individuals.
10 CFR 50.47(b)(14) states:
Periodic exercises are (will be) conducted to evaluate major portions of emergency response capabilities, periodic drills are (will be) conducted to develop and maintain key skills, and deficiencies identified as a result of exercises or drills are (will be) corrected.
10 CFR 50.47(b)(15) states:
Radiological emergency response training is provided to those who may be called on to assist in an emergency.
In addition,Section IV.E.6 of Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities, to 10 CFR states that adequate provisions shall be made and described for emergency facilities and equipment, including for the following:
Arrangements for transportation of contaminated injured individuals from the site to specifically identified treatment facilities outside the site boundary.
2.2 Guidance Regulatory Guide 1.101, Revision 2, Emergency Planning and Preparedness for Nuclear Power Reactors (ADAMS Accession No. ML090440294), provides guidance on methods acceptable to the NRC staff for implementing specific parts of the NRCs regulations.
Regulatory Guide 1.101 endorses Revision 1 to NUREG-0654/FEMA-REP-1 (NUREG-0654),
Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (ADAMS Accession No. ML040420012),
which provides specific acceptance criteria for complying with the standards set forth in 10 CFR 50.47(b). These criteria provide a basis for the NRC licensees and State and local governments to develop acceptable radiological emergency plans and to improve emergency preparedness.
NUREG-0654, Revision 1,Section II, Planning Standards and Evaluation Criteria, Evaluation Criterion II.B.9 states, in part:
The licensee shall provide for transportation and treatment of injured personnel who may also be contaminated.
NUREG-0654, Revision 1, Evaluation Criteria II.L.2 and II.L.4, address planning standard 10 CFR 50.47(b)(12). Evaluation Criterion II.L.2 states, [e]ach licensee shall provide for on-site first aid capability. Evaluation Criterion II.L.4 states, in part:
Each organization shall arrange for transporting victims of radiological accidents to medical support facilities.
NUREG-0654, Revision 1, Evaluation Criterion II.N.2.c, addresses the planning standard in 10 CFR 50.47(b)(14). Evaluation Criterion II.N.2.c states, in part:
A medical emergency drill involving a simulated contaminated individual which contains provisions for participation by the local support services agencies (i.e., ambulance and offsite medical treatment facility) shall be conducted annually.
NUREG-0654, Revision 1, Evaluation Criteria II.O.1.a, II.O.3, and II.O.4.h, address planning standard 10 CFR 50.47(b)(15). Evaluation Criterion II.O.1.a states, [e]ach facility to which the plant applies shall provide site-specific emergency response training for those offsite emergency organizations who may be called upon to provide assistance in the event of an emergency.
Evaluation Criterion II.O.3 states, [t]raining for individuals assigned to licensee first aid teams shall include courses equivalent to Red Cross Multi-Media. Evaluation Criterion II.O.4.h states, in part:
specialized initial training and periodic retraining programs (including the scope, nature and frequency) shall be provided in the following categories:
- h. Medical support personnel
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed emergency plan changes, as described in the application dated July 31, 2020. The staffs technical evaluation is detailed below.
3.1 Background
TVA stated that the fire brigade at the TVA sites includes medical response personnel whose training has been at the EMT level. TVA further stated that the fire brigade is in the process of reorganizing from being a separately staffed entity to an Operations and Maintenance Department staffed function and that training for the reorganized fire brigade will not require an EMT qualification for medical response. This is contrary to what is specified in the current TVA REP, which specifies using personnel with EMT qualifications.
TVA further stated that the reason for maintaining on-shift EMTs and an on-site ambulance originated from the sites emergency response capabilities during the development of the TVA fleet REP in the mid-1980s. Some of the TVA nuclear plants were geographically isolated from the general population with local volunteer-only fire departments and some volunteer emergency medical service (EMS) agencies that were significantly delayed in responding, if at all. It was recognized that the best approach was to provide internal staffing so treatment and transport could begin from the site, rather than wait for an offsite response to the site. In addition to the geographical isolation of some of the sites, TVA stated that there was also a concern from multiple ambulance providers about their personnel entering the TVA plants to provide care to contaminated personnel because of being generally unfamiliar with radiological hazards. Furthermore, at that time, these providers were also concerned about transporting a contaminated patient. Certain EMS agencies did not want to risk transporting a patient in an ambulance only to remove it from service due to radiological contamination, as many did not have a reserve unit available. During this time period, the State required minimum staffing of an ambulance consisting of one EMT and one ambulance driver. In response, TVA opted to train all on-shift medical personnel to a minimum of EMT and to have an ambulance on-site to transport contaminated patients to the local hospital.
TVA stated that it has since partnered more closely with local ground and air medical EMS agencies. Local emergency management agencies have also robustly increased their response area and capabilities. As a result of being provided additional information, education, and training concerning contaminated patients, including on how to handle and treat patients to prevent the spread of contamination, EMS agencies are now more agreeable to provide transportation partnerships. Therefore, TVA stated that there is no longer a need to employ the strategy of using an on-site ambulance (manned by an EMT) to transport contaminated patients to medical facilities.
3.2 Evaluation The TVA REP consists of a generic plan that addresses organizational responsibilities, capabilities, actions, and guidelines for TVA during a radiological emergency, and three plant-specific appendices containing the site-specific information.
Replace the Position of EMT with an Emergency Medical Professional TVA proposes an administrative change to Section 17.0, Definitions and Abbreviations, of the TVA REP by inserting the terms emergency medical responder and emergency medical technician into a new definition of a new term emergency medical professional.
Additionally, TVA is proposing to replace a dedicated EMT on-shift with an on-shift emergency medical professional. This emergency medical professional is defined as an individual certified under a recognized TVA system to provide emergency and related services to victims of illness or injury, which can be either an emergency medical responder, an EMT, an advanced EMT, or a paramedic.
TVA further states that other shift watch positions meet the evaluation criteria (addressed below), such as Assistant Unit Operator Fire Brigade Members, who are assigned the Advanced Fire Brigade Member curricula under the Fire Operations Transition Initiative. The curricula include First Aid training (which includes administering cardiopulmonary resuscitation, use of the automated external defibrillator, and understanding bloodborne pathogens).
The planning basis in NUREG-0654, Evaluation Criterion II.L.2, addresses planning standard 10 CFR 50.47(b)(12). Evaluation Criterion II.L.2 specifies that each licensee shall provide for on-site first aid capability. The proposed TVA REP, who would replace the requirement for an on-shift EMT with a requirement for an emergency medical responder, would maintain the sites capability to provide on-site first aid to contaminated injured individuals. The proposed REP, therefore, would continue to conform with NUREG-0654, Evaluation Criterion II.L.2.
The planning basis in NUREG-0654, Evaluation Criterion II.O.3, addresses planning standard 10 CFR 50.47(b)(15). Evaluation Criterion II.O.3 specifies the type of training to be provided to licensee first aid team members who may be called on to assist in an emergency as: Training for individuals assigned to licensee first aid teams shall include courses equivalent to Red Cross Multi-Media. The proposed TVA REP would maintain the same level of training to licensee first aid team members, and therefore, would continue to conform with NUREG-0654, Evaluation Criterion II.O.3.
Removal of the Requirement for an On-site TVA Ambulance The planning basis in NUREG-0654, Evaluation Criterion II.B.9, addresses the planning standard 10 CFR 50.47(b)(2). Evaluation Criterion II.B.9 specifies that provisions be made for transportation and treatment of injured personnel who may also be contaminated. Additionally,Section IV.E.6 of Appendix E to 10 CFR Part 50 requires arrangements for transportation of contaminated injured individuals from the site to specifically identified treatment facilities outside the site boundary. The local and backup hospitals have not changed and have current letters of agreement for support. The proposed TVA REP maintains provisions for transportation and treatment of injured personnel who may also be contaminated, and therefore, continues to conform with Evaluation Criterion II.B.9.
The planning basis in NUREG-0654, Evaluation Criterion II.L.4, addresses the planning standard 10 CFR 50.47(b)(12). Evaluation Criterion II.L.4 specifies that arrangements be made for transporting victims of a radiological accident to medical support facilities. TVA proposes to remove the requirement for an on-site ambulance at each of the three nuclear sites. TVA states that the principal use of the on-site ambulance is to store medical supplies and equipment in addition to its availability as a means of transporting an injured contaminated individual from the
sites Protected Area to the Owner-Controlled Area. Once the injured contaminated individual is in the Owner-Controlled Area, the individual would be transferred to offsite ambulance services, as required. TVA further states that current procedures for the nuclear sites already contain direction to request offsite response from the facilities with which TVA has transportation agreements and to coordinate this offsite response with Nuclear Security for escort into the Protected Area. This existing protocol makes unnecessary the strategy of using an on-site ambulance at the TVA fleet sites. In addition, response equipment for contaminated individuals is already staged at each of the nuclear facility sites. TVA explained that the current usage of the on-site ambulance as an alternate First Aid Station has been maintained as a backup to the staged response equipment and can continue to be used as such. As the proposed TVA REP maintains provisions for transporting victims of radiological accidents to medical support facilities, the proposed REP continues to conform with the applicable guidance in NUREG-0654, Evaluation Criterion II.L4.
Additionally, TVA proposes to remove from the TVA REP the requirement to have an ambulance radio. The primary mechanism for communication with the local hospitals will remain by telephone with radio communication as the backup method for the TVA fleet sites.
Backup radio communications remain available through site portable radios as identified in the TVA Emergency Plan Implementing Procedures. The proposed TVA REP, therefore, maintains the same provisions for primary and backup communications with the local hospitals.
The planning basis in NUREG-0654, Evaluation Criterion II.N.2.c, addresses the planning standard 10 CFR 50.47(b)(14). Evaluation Criterion II.N.2.c specifies provisions for conducting an annual medical emergency drill. The current TVA REP requires participation by either a TVA or agreement ambulance, in addition to participation by each agreement hospital. TVA proposes an administrative change for the removal of the TVA ambulance at each of the sites from the criteria for these types of drills. The revised TVA REP would still provide for a medical emergency drill involving a simulated contaminated/injured individual with participation by an agreement ambulance and each agreement hospital each calendar year for each plant. As the proposed TVA REP maintains the provisions for a medical emergency drill involving a simulated contaminated/injured individual with participation by an agreement ambulance and each agreement hospital each calendar year for each plant, the proposed REP continues to conform with the guidance in NUREG-0654, Evaluation Criterion II.N.2.c.
The planning bases in NUREG-0654, Evaluation Criteria II.O.1.a and II.O.4.h, address the planning standard 10 CFR 50.47(b)(15). Evaluation Criteria II.O.1.a and II.O.4.h specify, respectively, that radiological emergency response training is to be provided by the licensee for those who may be called on to assist in an emergency and that training shall be provided to medical support personnel. TVA states that the proposed TVA REP provides training for the offsite medical and emergency response personnel and that the training will continue to include the procedures for notification, basic radiation protection, and the personnels expected roles.
For those local service support organizations that will enter the TVA sites, training will continue to include site access procedures and authorization. In addition, the TVA REP training program at each of the sites will remain in place for medical support personnel. As the proposed TVA REP maintains the provisions for radiological emergency response training provided by the licensee for those who may be called on to assist in an emergency, the proposed REP continues to conform with the guidance in Evaluation Criteria II.O.1.a and II.O.4.h.
3.3 Technical Conclusion For the reasons outlined above, the NRC staff finds that the proposed emergency plan changes meet the referenced planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, and provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Therefore, the NRC staff concludes that the licensees proposed changes to the TVA REP in its application dated July 31, 2020, are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Alabama and Tennessee State officials were notified of the proposed issuance of the amendments on October 7, 2020. The State officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change the site emergency plan. The amendments relate, in part, to changes in recordkeeping, reporting, or administrative procedures or requirements. The amendments also relate, in part, to changing requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. 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, published in the Federal Register on September 8, 2020, that the amendments involve no significant hazards consideration, and there has been no public comment on this finding (85 FR 55508). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). 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 Commissions 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 Contributor: E. Robinson, NSIR Date: November 19, 2020
ML20282A345 *by e-mail OFFICE NRR/DORL/LPLII-2/PM* NRR/DORL/LPLII-2/LA* NSIR/DPR/RLB/BC*
NAME MWentzel BAbeywickrama JAnderson DATE 10/07/2020 10/20/2020 10/06/2020 OFFICE OGC - NLO* NRR/DORL/LPLII-2/BC* NRR/DORL/D*
NAME CCarson UShoop CErlanger DATE 10/20/2020 10/26/2020 10/27/2020 OFFICE NRR/D* NRR/DORL/LPLII-2/PM*
NAME HNieh (MGavrilas for) MWentzel DATE 11/19/2020 11/19/2020