LER-1981-015, /03L-0:on 810428,during Refueling Outage,Air Monitor 1-RM-90-250 for Reactor Turbine Bldg Ventilation Found Inoperable Due to Instrument Indicating Downscale. Caused by Failed Detector High Voltage.Voltage Repaired |
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| 2591981015R03 - NRC Website |
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CON'T 60 61 OOCKET NU'ABER 68 69 EVENT DATE 74 75 REPCRT DATE 80
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5 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h for the reactor /
I I o i 2 l I During refueling outage, continuous air monitor (1-RM-90-250)
Jturbine building ventilation was declared inoperable due to instrument indicating l
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JJ CAUGE DESCRIPTION AND CORRECTIVE ACTIONS h Ii).iIl Detector high voltage failed, causing the continuous air monitor to indicate down-l The NMC detector high voltage of I
Ii)ij l scale. The Chemical Lab started samplins; program.
CAM, NMC Model AM-331 BF was repaired, functionally tested, and returned to service l
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kynnessee Vality Authority Form BF-17 BF 15.2 Browns Ferry Nuclear Plant 3/24/81 LER SUPPLEMENTAL INFORMATION BFRO 259 / 81015 Technical Specification Involved 3.8.B.8 and 3.8.B.6 Reported Under Technical Specification 6.7.2.b(2)
Date of Occurrence 4/28/81 Time of Occurrence 2245 Unit 1
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Identification and Description of Occurrence:
- - Continuous air monitor (1-RM-90-250) for the reactor / turbine building ventilation inoperable.
Cond? ions 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.
Chemical Lab took readings every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Instrument mechanics working on continuous air monitor.
.1pparent Cause of Occurrence:
Moisture in the sample line.
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.
Corrgetive Action:
Started sampling program. Repaired, functionally tested, and ?:eturned continuous air monitor to service.
Failure Data:
3 FRO-50-259/8071, 8079, 8110; 260/78020, 78022; 296/76014W.
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- Retention : Period - Lifetime; Responsibility - Document Control Supervisor
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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. 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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. 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