LER-1981-018, /03L-0:on 810504,during Refueling,While Performing Automatic Depressurization Sys Timer Calibr,Relay 2E-K35 Was Operating in 126,exceeding Tech Spec Limits.Caused by Normal Aging & Use.Relay Was Recalibr |
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60 61 DOCKET NUMBER 68 89 EVENT DATE 14 7S REPORT UATE 80 EVENT DESCRIPTir,N AND PROB ABLE CONSEQUENCES h IoI2i l During refueling, shile performing ADS timer calibration, relay 2E-K35 was found l
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T.S. Table 3.2.B requires operation in 120+- seconds.,
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Tennessee Valley Authority Form BF-17 Brm.ns Ferry Nuclear Plant BF 15.2 3/24/81 LER SUPPLEMENTAL INFORMATION BFRO 259 / 81018 Technical Specification Involved Table 3.2.B Reported Under Techrical Specification 6.7.2.b(2)
Date of Occurrence 5/4i al Time of Occurrence 0000 Unit -
1 Identification and Description of Occurrence:
ADS timer relay was found to operate in 126 seconds, exceeding T.S. table 3.2.B requirement of 120 + 5 seconds.
Conditions Prior to Occurrence:
Unit I refueling outage.
Unit 2 at 99%.
Unit 3 at 10d%.
Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.
None required.
.A,yparent Cau_se of Occurrence:
Relay 2E-K35 was out of calibration due to normal aging and use.
Analysis of Occurrence:
There was no danger to the health or safety of.the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.
Corrective Action
Relay was recalibrated and satisfactorily tested.
Failure Data:
BFR0 50-259/8007, 8013; 260/8044.
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H 60 68 OOCKET NUM8ER 68 69 EVENT OATE 74 75 REPORT DATE 80 EVENT OESCRIPTION AND PROBA8LE CONSEQUENCES h l o l c i l During refueling, while performing ADS timer calibration, relay 2E-K35 was found I
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Te:nnesser Valley Authority Form BF-17 Brm.ns Ferry Nuclear Plant BF 15.2 3/24/81 LER SUPPLEMENTAL INFORMATION BFRO 259 / 81018 Technical Specification Involved Table 3.2.B Reported Under Technical Specification 6.7.2.b(2)
Date of Occurrence 5/4/81 Time of Occurrence 0000 Unit 1
Identification and Description of Occurrence:
1 ADS timer relay was found-to operate in 126 seconds, exceeding T.S. table 3.2.B requirement of 120 t 5 seconds.
Conditions Prior to Occurrence:
Unit I refueling outage.
Unit 2 at 99%.
Unit 3 at 100%.
Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.
None required.
Aj, parent Cause of Occurrence:
l Relay 2E-K35 was out of calibration due to normal aging and use.
Analysis of Occurrence.
There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant
[
chain of events.
Corrective Action
l Relay was recalibrated and satisfactorily tested.
1 Failure Data:
BFR0 50.'59/8007, 8013; 260/8044.
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| 05000260/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000260/LER-1981-001-01, /01T-0:on 810102,scram Discharge Vol Level Switch 2-LS-85-45A Found Inoperable & -C & -D Found Offscale.Caused by One Robert Shaw Switch Model SL-305-EI-X Sticking & Setpoint Drift.Stuck Switches Float Chamber Back Flushed | /01T-0:on 810102,scram Discharge Vol Level Switch 2-LS-85-45A Found Inoperable & -C & -D Found Offscale.Caused by One Robert Shaw Switch Model SL-305-EI-X Sticking & Setpoint Drift.Stuck Switches Float Chamber Back Flushed | | | 05000259/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000296/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000296/LER-1981-001-03, /03L-0:on 810106,both Smoke Detectors in Reactor Bldg Fixed Spray Zone Were Inoperable.Caused by Loose Screw in Terminal Block.Screw Replaced | /03L-0:on 810106,both Smoke Detectors in Reactor Bldg Fixed Spray Zone Were Inoperable.Caused by Loose Screw in Terminal Block.Screw Replaced | | | 05000259/LER-1981-001-03, /03L-0:on 810105,core Spray Sparger to Reactor Pressure Vessel D/P Switch 1-PDIS-75-28 Found Set Above Tech Spec Limit.Caused by Barton Model 288 Setpoint Drift.Switch Replaced W/New Switch on 810115 | /03L-0:on 810105,core Spray Sparger to Reactor Pressure Vessel D/P Switch 1-PDIS-75-28 Found Set Above Tech Spec Limit.Caused by Barton Model 288 Setpoint Drift.Switch Replaced W/New Switch on 810115 | | | 05000260/LER-1981-002-03, /03L-0:on 810102,scram Discharge Instrument Vol Rod Block Level Switch 2-LS-85-45E Found Set at 27 Gallons. Alarm Switch 2-LS-85-45F Found Inoperable.Caused by Drift of Robertshaw Model SL-305-EI-X.Switch Recalibr | /03L-0:on 810102,scram Discharge Instrument Vol Rod Block Level Switch 2-LS-85-45E Found Set at 27 Gallons. Alarm Switch 2-LS-85-45F Found Inoperable.Caused by Drift of Robertshaw Model SL-305-EI-X.Switch Recalibr | | | 05000296/LER-1981-002-03, /03L-0:on 810104,excess Flow Check Valves in B3 & B7 Instrument Lines to Panel 25-7 Would Not Restrict Flow Properly.Cause Not Stated.Internals Changed & SI 4.7.D.1.d Successfully Completed | /03L-0:on 810104,excess Flow Check Valves in B3 & B7 Instrument Lines to Panel 25-7 Would Not Restrict Flow Properly.Cause Not Stated.Internals Changed & SI 4.7.D.1.d Successfully Completed | | | 05000259/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000259/LER-1981-002-03, /03L-0:on 810114,smoke Detector in Relay Room Alarmed & Would Not Clear.Caused by Detector Sensitivity Increasing Due to Normal,Natural Aging.Detector Replaced & Tested | /03L-0:on 810114,smoke Detector in Relay Room Alarmed & Would Not Clear.Caused by Detector Sensitivity Increasing Due to Normal,Natural Aging.Detector Replaced & Tested | | | 05000296/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000260/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000260/LER-1981-003-03, /03L-0:on 810112,core Spray Pump Discharge Pressure Switch 2-PS-75-16 Found Outside Tech Spec Limits. Caused by Setpoint Drift.Switch Recalibr & Replaced | /03L-0:on 810112,core Spray Pump Discharge Pressure Switch 2-PS-75-16 Found Outside Tech Spec Limits. Caused by Setpoint Drift.Switch Recalibr & Replaced | | | 05000259/LER-1981-003-01, /01T-0:on 810124,Div of Engineering Notified That 1-inch Vent Line on Unit 1 Scram Discharge Vol Not Seismically Qualified.Caused by Piping Configuration Not Conforming to Design Requirements | /01T-0:on 810124,Div of Engineering Notified That 1-inch Vent Line on Unit 1 Scram Discharge Vol Not Seismically Qualified.Caused by Piping Configuration Not Conforming to Design Requirements | | | 05000259/LER-1981-003, Forwards LER 81-003/01T-0 | Forwards LER 81-003/01T-0 | | | 05000260/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000296/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000296/LER-1981-003-03, /03L-0:on 810107,during Refueling Outage,Fuel Pool Cooling Sys Auto Isolated When Power Was Removed.Fuel Pool Sampling Not Performed on 8-h Schedule.Caused by Personnel Error.Personnel Reinstructed | /03L-0:on 810107,during Refueling Outage,Fuel Pool Cooling Sys Auto Isolated When Power Was Removed.Fuel Pool Sampling Not Performed on 8-h Schedule.Caused by Personnel Error.Personnel Reinstructed | | | 05000260/LER-1981-004-01, /01T-0:on 810119,reactor Water Level Switches LIS-3-203A Switch 1 & LIS-3-A,B,C,D Switch 2 Found Outside Tech Specs.Caused by Drift Due to Air Impact Drilling Next to Switch Panel.Switches Recalibr | /01T-0:on 810119,reactor Water Level Switches LIS-3-203A Switch 1 & LIS-3-A,B,C,D Switch 2 Found Outside Tech Specs.Caused by Drift Due to Air Impact Drilling Next to Switch Panel.Switches Recalibr | | | 05000296/LER-1981-004-03, Diesel Generator 3A & Breaker 1836 Tripped from Generator Overspeed During Testing.Caused by Vs Relay on Speed Sensing Panel Energizing at Less than 870 Rpm,Closing Breaker 1836 | Diesel Generator 3A & Breaker 1836 Tripped from Generator Overspeed During Testing.Caused by Vs Relay on Speed Sensing Panel Energizing at Less than 870 Rpm,Closing Breaker 1836 | | | 05000296/LER-1981-004, Forwards Updated LER 81-004/03X-1 | Forwards Updated LER 81-004/03X-1 | | | 05000259/LER-1981-004, Forwards Updated LER 81-004/03L-1 | Forwards Updated LER 81-004/03L-1 | | | 05000259/LER-1981-004-03, Standby Gas Treatment Sys Train C Relative Humidity Heaters Declared Inoperable.Caused by Dwyer Photohelic Pressure Switch/Gage Circuit Hh & Ite Imperial Relay Contact Block Malfunction | Standby Gas Treatment Sys Train C Relative Humidity Heaters Declared Inoperable.Caused by Dwyer Photohelic Pressure Switch/Gage Circuit Hh & Ite Imperial Relay Contact Block Malfunction | | | 05000260/LER-1981-005-03, /03L-0:on 810119,core Max Fraction of Limiting Power Density Exceeded Limit for One Node in Core.Caused by Operation Close to Limit in Conjunction W/Minor (Normal) Perturbation in Monitored Parameters.Power Reduced Slightly | /03L-0:on 810119,core Max Fraction of Limiting Power Density Exceeded Limit for One Node in Core.Caused by Operation Close to Limit in Conjunction W/Minor (Normal) Perturbation in Monitored Parameters.Power Reduced Slightly | | | 05000259/LER-1981-005-04, /04T-0:on 810131,hydrogen Ion Concentration of Reservoir Near Plant Found in Excess of Allowable Discharge Limit.Probably Caused by Upstream Source.Discharge of Spent Regenerants Stopped & Monitoring Program Established | /04T-0:on 810131,hydrogen Ion Concentration of Reservoir Near Plant Found in Excess of Allowable Discharge Limit.Probably Caused by Upstream Source.Discharge of Spent Regenerants Stopped & Monitoring Program Established | | | 05000296/LER-1981-005-03, /03L-0:on 810127,containment Atmosphere Hydrogen analyzer,3-H2M-76-94,removed from Svc.Caused by Maint on Sensing Line at 3-FIC-76-94,Model 1350,due to Water Collection.Water Removed & Lines Returned to Svc | /03L-0:on 810127,containment Atmosphere Hydrogen analyzer,3-H2M-76-94,removed from Svc.Caused by Maint on Sensing Line at 3-FIC-76-94,Model 1350,due to Water Collection.Water Removed & Lines Returned to Svc | | | 05000296/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000260/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000259/LER-1981-005, Forwards LER 81-005/04T-0 | Forwards LER 81-005/04T-0 | | | 05000259/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000259/LER-1981-006-03, /03L-0:on 810211,while Performing SI 4.2.B-57,RHR Area Cooling Fan Temp Switch 1-TS-64-68 Failed to Operate. Caused by Switch T675A1540 Failure.Switch Replaced,Calibr & 4.2.B-57 Completed | /03L-0:on 810211,while Performing SI 4.2.B-57,RHR Area Cooling Fan Temp Switch 1-TS-64-68 Failed to Operate. Caused by Switch T675A1540 Failure.Switch Replaced,Calibr & 4.2.B-57 Completed | | | 05000296/LER-1981-006-03, /03L-0:on 810128,containment Atmosphere Hydrogen Analyzer Removed from Svc.Caused by Maint on Sensing Lines Due to Effect of Water Accumulation on Model 76-01A625 Timer.Water Removed & Monitor Returned to Svc | /03L-0:on 810128,containment Atmosphere Hydrogen Analyzer Removed from Svc.Caused by Maint on Sensing Lines Due to Effect of Water Accumulation on Model 76-01A625 Timer.Water Removed & Monitor Returned to Svc | | | 05000296/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000260/LER-1981-006-03, /03L-0:on 810121,core Max Fraction of Limiting Power Density Exceeded Limit.Caused by Power Increase in Conjunction W/Inoperable Process Computer.Power Reduced & Control Rod Pattern Adjustment Made on 810123 | /03L-0:on 810121,core Max Fraction of Limiting Power Density Exceeded Limit.Caused by Power Increase in Conjunction W/Inoperable Process Computer.Power Reduced & Control Rod Pattern Adjustment Made on 810123 | | | 05000260/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000260/LER-1981-007-03, /03L-0:on 810129,during Power Increases,Tech Spec Limit of 13.33 Kw/Ft for Linear Heat Generation Rate Exceeded in One Node.Node Reached 13.77 Kw/Ft.Caused by Xenon Transient Resulting from Increased Core Power | /03L-0:on 810129,during Power Increases,Tech Spec Limit of 13.33 Kw/Ft for Linear Heat Generation Rate Exceeded in One Node.Node Reached 13.77 Kw/Ft.Caused by Xenon Transient Resulting from Increased Core Power | | | 05000260/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000259/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000259/LER-1981-007-03, /03L-0:on 810210,during Fire Door Insp,Fire Door Damper (Door 472) Not Closed.Caused by Paint Buildup in Operating Mechanism.Damper Closed & Other Dampers Inspected. Procedure for Insp & Preventive Maint Will Be Written | /03L-0:on 810210,during Fire Door Insp,Fire Door Damper (Door 472) Not Closed.Caused by Paint Buildup in Operating Mechanism.Damper Closed & Other Dampers Inspected. Procedure for Insp & Preventive Maint Will Be Written | | | 05000296/LER-1981-007-03, /03L-0:on 810202,setpoint for 3-PS-1-76 Below Tech Specs Limit.Caused by B2TA12SS Setpoint Drift.Switch Recalibr & Verified.Switch to Be Replaced W/Analog Trip Sys by DCR 1398 | /03L-0:on 810202,setpoint for 3-PS-1-76 Below Tech Specs Limit.Caused by B2TA12SS Setpoint Drift.Switch Recalibr & Verified.Switch to Be Replaced W/Analog Trip Sys by DCR 1398 | | | 05000296/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000260/LER-1981-008-03, /03L-0:on 810220,reactor Core Isolation Cooler Turbine Trip & Throttle Valve Closed & Would Not Reopen. Caused by Overload Heater Relay.Relay Replaced | /03L-0:on 810220,reactor Core Isolation Cooler Turbine Trip & Throttle Valve Closed & Would Not Reopen. Caused by Overload Heater Relay.Relay Replaced | | | 05000259/LER-1981-008-01, /01T-0:on 810226,secondary Containment Integrity Lost When Exterior Equipment Access Door 229 & Interior Personnel Door 228 Opened Simultaneously.Caused by Lack of Interlocks Between Doors.Interlocks to Be Installed | /01T-0:on 810226,secondary Containment Integrity Lost When Exterior Equipment Access Door 229 & Interior Personnel Door 228 Opened Simultaneously.Caused by Lack of Interlocks Between Doors.Interlocks to Be Installed | | | 05000296/LER-1981-008-03, /03L-0:on 810202,RHR Pump Found Inoperable.Caused by Loose Pump 3D Breaker Trip Adjustment Nut & Adjustment Change,Causing Breaker to Trip Free on Attempting to Close. Breaker Replaced.Adjustment Locknut Tightness Checks Add | /03L-0:on 810202,RHR Pump Found Inoperable.Caused by Loose Pump 3D Breaker Trip Adjustment Nut & Adjustment Change,Causing Breaker to Trip Free on Attempting to Close. Breaker Replaced.Adjustment Locknut Tightness Checks Added | | | 05000296/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000259/LER-1981-008, Forwards LER 81-008/01T-0 | Forwards LER 81-008/01T-0 | | | 05000260/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000296/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000259/LER-1981-009, Forwards LER 81-009/01T-0 | Forwards LER 81-009/01T-0 | | | 05000260/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | |
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