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Category:Letter
MONTHYEARIR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual 2024-09-03
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator2024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup 05000260/LER-2024-001-01, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-04-17017 April 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000259/LER-2024-001, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-04-11011 April 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure 05000260/LER-2024-001, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-02-16016 February 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000259/LER-2023-003, Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage2024-01-29029 January 2024 Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage 05000259/LER-2022-002-01, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator2023-10-12012 October 2023 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator 05000260/LER-2023-001-01, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure2023-09-18018 September 2023 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure 05000260/LER-2023-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2023-08-0404 August 2023 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2022-003-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure2023-07-31031 July 2023 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure 05000259/LER-2023-002, Full Reactor Scram Due to an Oscillation Power Range Monitor (OPRM) Confirmation Density Algorithm (CDA) Trip2023-07-17017 July 2023 Full Reactor Scram Due to an Oscillation Power Range Monitor (OPRM) Confirmation Density Algorithm (CDA) Trip 05000259/LER-2023-001-01, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm2023-06-13013 June 2023 High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm 05000260/LER-2023-001, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line2023-04-19019 April 2023 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line 05000259/LER-2023-001, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm2023-03-27027 March 2023 High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm 05000259/LER-1922-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2023-02-0606 February 2023 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2022-003, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2023-01-31031 January 2023 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line 05000296/LER-2022-002, Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate2022-12-19019 December 2022 Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate 05000259/LER-2022-002, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator2022-09-12012 September 2022 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator 05000296/LER-2022-001, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2022-07-11011 July 2022 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2021-001-01, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay2022-07-0606 July 2022 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay 05000259/LER-2022-001, From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2022-03-16016 March 2022 From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line 05000259/LER-2021-001, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay2021-11-22022 November 2021 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay ML20160A0232020-06-0404 June 2020 SR 2020-001-00 for Browns Ferry Nuclear Plant (Bfn),Inoperable Oscillating Power Range Monitor (OPRM) Instrumentation 05000296/LER-2017-0022017-12-29029 December 2017 4kV Shutdown Board Potential Transformer Primary Fuses Do Not Coordinate with Secondary Fuses, LER 17-002-00 for Browns Ferry Nuclear Plant, Unit 3 Regarding 4kV Shutdown Board Potential Transformer Primary Fuses Do Not Coordinate with Secondary Fuses 05000296/LER-2017-0012017-10-31031 October 2017 Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications, LER 17-001-00 for Browns Ferry Nuclear Plant, Unit 3, Regarding Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications 05000260/LER-2017-0042017-07-0707 July 2017 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints, LER 17-004-00 for Browns Ferry, Unit 2, Regarding Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000260/LER-2017-0032017-05-30030 May 2017 Manual Reactor Scram Initiated During Startup Due to Multiple Rods Inserting, LER 17-003-00 for Browns Ferry Nuclear Plant, Unit 2 Regarding Manual Reactor Scram Initiated During Startup Due to Multiple Rods Inserting 05000259/LER-2017-0022017-04-27027 April 2017 Unauthorized Firearm Introduced into the Protected Area, LER 17-002-00 for Browns Ferry, Unit 1, Regarding Unauthorized Firearm Introduced into the Protected Area 05000260/LER-2017-0022017-04-24024 April 2017 Inoperable Primary Containment Isolation Valve Resulting in Condition Prohibited by Technical Specifications, LER 17-002-00 for Browns Ferry, Unit 2, Regarding Inoperable Primary Containment Isolation Valve Resulting in Condition Prohibited by Technical Specifications 05000260/LER-2017-0012017-04-14014 April 2017 High Pressure Coolant Injection Safety System Functional Failure Due to a Blown Fuse, LER 17-001-00 for Browns Ferry, Unit 2, Regarding High Pressure Coolant Injection Safety System Functional Failure Due to a Blown Fuse 05000259/LER-2016-0022016-09-19019 September 2016 High Pressure Coolant Injection Safety System Functional Failure due to Inoperability of Primary Containment Isolation Valve, LER 16-002-00 for Browns Ferry, Unit 1, Regarding High Pressure Coolant Injection Safety System Functional Failure Due to Inoperability of Primary Containment Isolation Valve 05000260/LER-2016-0022016-09-13013 September 2016 High Pressure Coolant Injection System Failure Due To Stuck Contactor, LER 16-002-00 for Browns Ferry Nuclear Plant, Unit 2, Regarding High Pressure Coolant Injection System Failure Due To Stuck Contactor 05000260/LER-2016-0012016-08-16016 August 2016 High Pressure Coolant Injection Safety System Functional Failure due to a Blown Fuse and a Failed Relay, LER 16-001-00 for Browns Ferry, Unit 2, Regarding High Pressure Coolant Injection Safety System Functional Failure Due to a Blown Fuse and a Failed Relay 05000296/LER-2016-0062016-08-0505 August 2016 1 OF 8, LER 16-006-00 for Browns Ferry Nuclear Plant, Unit 3, Regarding High Pressure Coolant Injection System Found to be Inoperable During Testing 05000259/LER-2016-0012016-06-21021 June 2016 Failure of 4kV Shutdown Board Normal Feeder Breaker Results in Actuations of Emergency Diesel Generators and Containment Isolation Valves, LER 16-001-00 for Browns Ferry, Unit 1, Regarding Failure of 4kV Shutdown Board Normal Feeder Breaker Results in Actuations of Emergency Diesel Generators and Containment Isolation Valves 05000296/LER-2016-0052016-06-17017 June 2016 Automatic Depressurization System Valve Inoperability Exceeded Technical Specification Limits, LER 16-005-00 for Browns Ferry, Unit 3, Regarding Automatic Depressurization System Valve Inoperability Exceeded Technical Specification Limits 05000296/LER-2016-0042016-06-0606 June 2016 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints, LER 16-004-00 for Browns Ferry, Unit 3, Regarding Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2016-0032016-04-25025 April 2016 Main Steam Isolation Valve Leaking in Excess of Technical Specification Requirements, LER 16-003-00 for Browns Ferry Nuclear Plant Unit 3 Regarding Main Steam Isolation Valve Leaking in Excess of Technical Specification Requirements 05000296/LER-2016-0022016-04-22022 April 2016 Improperly Installed Switch Results in Condition Prohibited by Technical Specifications, LER 16-002-00 for Browns Ferry Nuclear Plant, Unit 3, Regarding Improperly Installed Switch Results in Condition Prohibited by Technical Specifications 05000296/LER-2016-0012016-03-21021 March 2016 Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications and Safety System Functional Failure, LER 16-001-00 for Browns Ferry, Unit 3, Regarding Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications and Safety System Functional Failure 05000260/LER-2015-0022016-03-17017 March 2016 High Pressure Coolant Injection System Inoperable due to Manual Isolation of Steam Leak I, LER 15-002-01 for Browns Ferry, Unit 2, Regarding High Pressure Coolant Injection System Inoperable Due to Manual Isolation of Steam Leak ML1108400352011-03-22022 March 2011 Letter Re Licensee Event Report Which Occurred on December 22, 2010, Concerning Low Pressure Coolant Injection Operability, TVA Expects to Submit a Revised LER by April 15, 2011 ML1015505752010-04-0707 April 2010 Event Notification for Browns Ferry on Spill of Water Containing Tritium ML1015505632008-01-10010 January 2008 Event Notification for Browns Ferry on Offsite Notification - Spill of Water Containing Tritium 2024-07-08
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: OREILLY J P ORG: FOX H S DOCDATE: 05/04/78 NRC TN VALLEY AUTH DATE RCVD: 05/ii/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR i ENCL i FORWARDING LlCENSEE EVENT REPT (RO 50-296/78-0i0) ON 04/09/78 CONCERNING RBM CHANNELS BECAME CONTINUOUSLY BYPASSED... ALL ROD MOVEMENT WAS TERMINATED.... W/ATT.
PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER INITIAL: X JM DlSTRIBUTOR INITIAL:Q~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002>
FOR ACTION: BR CHIEF LEA .
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 MN c '197S Itll,II@II(Ogrffl g~[ tropIr" Mr. James P. O'Reilly, Dirac r U.S. Nuclear Regulato Comnission Cp Office of Inspection and Enforcement C~
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-,296 -
- BROGANS PERRY NUCLEAR FACILITY OPERATING LXCENSE OCCURRENCE REPORT BPRO-50-296/7810
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Crs The enclosed report provides details concerning both RBM channels which became continttously bypassed during power ascension. This report is submitted in accordance with Browns Perry unit 3 Technical Specification 6.7.2.a.(2).
Very truly yours, TENNESSEE VALLEY AUTHORXTY H. S. Pox Director of. Power Production Enclosure (3) cc {Enclosure):
Director (3)
Office of Management Information and Program Control U.S. Nuclear Regulatory Co ssion Washington, DC ,20555 Director (40)
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REPORTABLE OCCURRENCE REPORT Report Number : BFRO<<'50-296/7810 Report Date : May 2, 1978 Occurrence Date: April 9, 1978 Facility Browns Ferry Nuclear Plant Unit 3 Identification of Occurrence Operator observation of RBM recorders downscale and RBM bypass lights on.
Conditions Prior to Occurrence Normal operation at 77-percent power, during ascension to full load.
Descri tion of Occurrence Both RBM channels became continuously bypassed. Review of potential reportable occurrence report revealed report should have been a prompt report as required by Technical Specification 6.7.2.a.(2).
, Desi nation of A arent Cause of Occurrence Maintained voltage on edge rod selected bus. Misinterpretation of the technical specifications.
Anal sis of Occurrence Contact 5-6 of rod select relay KXB for CRD 38-03 stuck closed.
Corrective Action Replacement of defective relay. Discussed meaning of technical specification with plant staff.
Failure Data No previous failures.
JGD: SGS 5/A/78
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