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Category:Licensee Event Report (LER)
MONTHYEARML20160A0232020-06-0404 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
ML18283B3261978-09-29029 September 1978
LER 1978-205-01 for Browns Ferry, Unit 3 Four Main Steam Isolation Valves Which Exceeded the Leakage Limits of Technical Specification 4.7.A.2.i While Performing Local Leak Rate Testing During Refueling
ML18283B3391978-07-25025 July 1978
Licensee Event Report Concerning Excessive Drywell Floor Drain Leak Rate Observed During Normal Operation
ML18283B3411978-07-18018 July 1978
Licensee Event Report Concerning an Abnormal Indication on a 4-kV Standby Power Circuit Breaker During Normal Operation
ML18283B3401978-07-18018 July 1978
Licensee Event Report Concerning an Outboard Main Steam Isolation Valve, Which Closed Faster than Allowed by Technical Specifications
ML18283B3421978-05-31031 May 1978
Licensee Event Report Concerning MSIV 1-38 Which Closed in 1 Second Exceeding Limiting Condition of Operation
ML18283A9901978-05-30030 May 1978
LER 1978-010-00 for Browns Ferry Nuclear Plant, Unit 2, Relief Valve on Standby Liquid Control Pump B Opened at 900 Psig (Which Is Lower than Designed Setting of 1425 +/- 75 Psig as Designated by Tech Spec 4.4.A.2.A) During Surveillance Tes
ML18283A9911978-05-0909 May 1978
LER 1978-008-00 for Browns Ferry Nuclear Plant, Unit 2, Reactor Building Ventilation Radiation Monitoring Channel Failed During Refueling Outage
ML18283A9941978-05-0505 May 1978
LER 1978-009-00 for Browns Ferry Nuclear Plant, Unit 2, Local Leak Rate Tests of All Containment Isolation Valves Where Leak Rate Exceeded Allowable Leak Rate of 60 Percent of La Per 24 Hours or 707.1 Scfh
ML18283A9921978-05-0505 May 1978
LER 1978-006-00 for Browns Ferry Nuclear Plant, Unit 2, Check Valve 2-73-603 in High-Pressure Coolant Injection System Was Found in Open Position During Maintenance Inspection After Failing Local Leak Rate Test
ML18283B4001978-05-0101 May 1978
LER 1978-010-00 for Browns Ferry Nuclear Plant, Unit 3, Both RBM Channels Which Became Continuously Bypassed During Power Ascension
ML18283B4011978-04-28028 April 1978
LER 1978-009-00 for Browns Ferry Nuclear Plant, Unit 3, Smoke Alarm Which Would Not Clear & Was Received for Preaction Sprinkler Zone in Reactor Building During Normal Operation
ML18283B4021978-04-28028 April 1978
LER 1978-008-00 for Browns Ferry Nuclear Plant, Unit 3, Relief Valve 3-1-31 Which Failed to Reseat Until Reactor Pressure Reached 280 Psig During Reactor Scram
ML18283B4041978-04-24024 April 1978
LER 1978-001-00 for Browns Ferry Nuclear Plant, Unit 3, Torus Oxygen Sensor O2M-76-42, Found to Be Erratic & Did Not Meet Requirements of Tech Spec 4.7.II During Normal Operation, Which Is Superseding Previous Letter of 2/8/1978
ML18283B4031978-04-24024 April 1978
LER 1978-006-00 for Browns Ferry Nuclear Plant, Unit 3, Electrical Connector Carrying Thermocouple Circuits Monitoring Primary Containment Atmospheric Temperature Not Included as Part of Modification Which Qualified Connector Assemblies for
ML18283B4051978-04-0404 April 1978
LER 1978-005-00 for Browns Ferry Nuclear Plant, Unit 3, Six CRD Accumulator Level Switches Which Would Not Alarm with Level Increases During Plant Operation While Performing Electrical Maintenance Instruction 50
ML18283B4061978-03-30030 March 1978
LER 1977-012-00 for Browns Ferry Nuclear Plant, Unit 3, Temperature Transients Which Were Experienced with Six Charcoal Adsorber Beds in Offgas System During Normal Operation, Which Is Supplementing Previous Letter of 7/29/1977
ML18283A9951978-03-29029 March 1978
LER 1978-005-00 for Browns Ferry Nuclear Plant, Unit 2, Unidentified Coolant Leakage in Drywall Was Found to Be 9.5 Gpm & Exceeded 5 Gpm Limit of Technical Specification 3.6.C.1. During Normal Operation
ML18283B4091978-03-28028 March 1978
LER 1978-004-00 for Browns Ferry Nuclear Plant, Unit 3, Three of Five Test Specimens Failed During Simulated LOCA Conditions & During Qualification Testing of Bendix Electrical Connectors Identical to Those Used in Primary Containment
ML18283B4101978-03-22022 March 1978
LER 1977-005-00 for Browns Ferry Nuclear Plant, Unit 3, RPS MG Set a Which Continued Running & MG Set B Output Breaker Which Did Not Trip During Startup Test STI-31, Which Is Supplementing Previous Letter of 3/24/1977
ML18283B4111978-03-10010 March 1978
LER 1978-003-00 for Browns Ferry Nuclear Plant, Unit 3, Valve FCV 3-74-52 Was Found Inoperable During Performance of Surveillance Instruction 4.5.B.1.C
ML18283A9961978-02-28028 February 1978
LER 1978-004-00 for Browns Ferry Nuclear Plant, Unit 2, Relief Valve 2-1-5 Opened and Failed to Reseat During Steady State Operation
ML18283B4141978-02-28028 February 1978
LER 1978-002-00 for Browns Ferry Nuclear Plant, Unit 3, Bendix Connectors of Type Used Inside Primary Containment Have Failed a Post-Aging Environmental Test at Wyle Laboratory Testing Facility
ML18283A9971978-02-15015 February 1978
LER 1978-003-00 for Browns Ferry Nuclear Plant, Unit 2, Relief Valve 2-1-41 Opened and Failed to Reseat During Steady State Operation
ML18283B0001978-02-13013 February 1978
LER 1978-002-00 for Browns Ferry Nuclear Plant, Unit 2, Reactor Pressure Switch PS-68-95 Not Functioning as Required by Tech Spec Table 4.2.B During Normal Operation While Performing Surveillance Instruction ST 4.2.B-7
ML18283A9991978-02-0606 February 1978
LER 1978-001-00 for Browns Ferry Nuclear Plant, Unit 2, Surveillance Samples Were Taken from Charcoal in Unit 2 Primary Containment Purge System Following Maintenance Outage
ML18283B4161978-02-0606 February 1978
LER 1978-001-00 for Browns Ferry Nuclear Plant, Unit 3, Torus Oxygen Sensor O2M-76-42 Found to Be Erratic & Did Not Meet Requirements of Technical Specification 4.7.H During Normal Operation
ML18283B4071977-10-0505 October 1977
LER 1977-012-00 for Browns Ferry Nuclear Plant, Unit 3, Temperature Transients Were Experienced with Six Charcoal Adsorber Beds in Offgas System
ML18283B4171977-09-26026 September 1977
LER 1977-017-00 for Browns Ferry Nuclear Plant, Unit 3, Primary Containment Isolation Valve 3-FCV-77-2A on Drywell Floor Drain Sump Pump Discharge Line Would Not Operate as Required by Tech Spec 3.7.D.L During Routine Operability Checks
2020-06-04
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Text
U,S, NUCLEAR REGULATOR V CohIMISSION DOCKET NUMB . A N fIC FOIIM I2.70)
FILE NUMOFA
~ .. blBC DISTRIBl3TION FoA ART 50 DOCKET MATERIAL XNCIDENT REPORT TQic FROM: DATE OF DOCUMENT Tennessee Valley Authority 4/12/77 Mr. Norman C. Moseley Chattanooga, Tennessee DATE RECEIVED H. ST Fox 4/21/77 RRLETTE A ONOTORIZED PROP INPUT FOAM NUMBER OF COPIFS RECEIVED HOA IG liVAL Qcor v DLSCRIPTION UNCLASSIFIED ENCLOSU RE f MFA<<O I Ltr trans the following: Licensee Event Report (RO. 50-296/776) on 3/14/77 concerning drywell high piessure. switc PS-64-56A 'exceeding tech spec limit of F 00 psig by 0 04 psi 6~ ~ ~ ~ ~ ~
i gII,)<ewI.EMEtt iPLANT NAME: II ~
I IBr'owns Ferry Unit No. 3 tm mI (fan/ON NOTE: XF 1ERSONNEL EXPOSURE XS INVOLVED SEND DIRECTLY TO KREGER/Jo COLLINS FOR ACTION/INFORMAT ION BRANCH CHIEF:
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 April 12, 1977 Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., Suite 1217 Atlanta, Georgia 30303
Dear Mr. Moseley:
- Remlatory TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNXT 3 DOCKET NO ~ 50>>296 - PACILITY OPERATING LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/776 The enclosed report is to provide details concerning drywell high pressure switch PS-64-56A that exceeded technical specification limit of 2.00 psig by 0.04 psi 6 during normal operation. This report is submitted in accordance with Browns Perry Technical Specifications Section 6. This event occurred on Browns Ferry unit 3.
Very truly yours, TE SSEE VALLEY AUTHORITY H. S. Fox Director of Power Production Enclosure (3)
CC (Enclosure):
Director (3)
Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (40)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Opportunity Employer >>IIX-o ib 0
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'ICENSEE L!CENSE NA!)sE LICENSE NUMBEA TYPE TYPE JJLLB.~RP 3 0 0 0 0 0 0 0 0 0 4 1 1 1 1
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14 15 25 26 30 31 32 AEPGAT'EPORI CATEGOAY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT C'tE I Ioagcotrt h l, 0 0 0 4 7 8 57 58 59 60 61 68 69 74 75 60 EVENT OESCTIIPTION
[pape LDuring normal operation, dr well hi h ressure switch 'PS-64-56A exceeded technical 7 0 J 60 tocoI Laaccfffc ati onlinit of 2.00 si b 0.04 si 6. Redundant switches were o arabia.
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re ali 00'0 4 Switch was 7 8 9 BFRO-50-296/776 7 8 9 80 SS
'7 0 o PAME 80 SfsttM CAUSE CDMPDIJENT COMPONENT CODE CODE COMPONENt CODE SUPPUEA MANUF ACT UPOI VQIATGN t00j7 Lll+A F. I N S T R U 3 8 7 8 9 10 11 12 17 43 44 47 48 CAUSC OESCRIPTION Qp 8 Static-0-Ring model 12N-AA4 'pressure switch drifted above setpoint. Switch was 7 0 9 80
~0 9 ) recalibrated, functionally tempted, and 'returned to service.
7 0 9 eo Q~g 7 89 FAClUIY METHOD OF S I AIUS POWEA OTHER StATUS DISCOVERY DISCOVERY DESCRIPTION Q~l E ~0 NA Surveillance Testing 7 8 9 10 12 13 44 45 46 ec FDPM OF ACIIVITY CONTENT RELEASED OF AfLEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Qg ~7. z NA NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Pjs Ioaoo J 2 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q~~j ~oo o NA 7 8 9 11 12 80 OFFSITE CONSEClJENCFS Q~g NA 7 89 LOSS OR OAMAGE TO FACILITY TYPE OESCAIPTIOIJ NA Qg z 7 89 10 PUBLICITY NA NA 7 8
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