LER-1981-037, /03L-0:on 810723,containment Atmosphere Monitor Dihydrogen Dioxygen Analyzer B Sample Return Valves Could Not Be Energized.Caused by Failed Solenoid Assembly FSV-76-67 Due to Shorted Bridge Rectifier & Coil |
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| 2961981037R03 - NRC Website |
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.I Durina nonnal operation. containment atmosphere monitor (CAM) H,,0,, analyzer o 2 (TTT1 l sample return valveis could not be energized. See T.S. 3.7.H.2.
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lVl0l3l0lg 34 35 36 37 40 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h solenoid assembly FSV-76-67 failed l l__LO_) l Valcore Engineerina Corporation model V52630-529-1 ITTT1 I to ocerate due to a shorted bridge rectifier and coil. In addition, a voltage supplyi It I>I l wire was found loose due to a broken screw head. The solenoid assembly was replaced l See attached for l
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BF 15.2 6/04-81 LER SUPPLEMENTAL INFORMATION BFRO-50-296/81037-Technical Specification Involved 3.7.H.2.
Reported Under Technical Specification
- 6. 7. 2.b. 2
- Date due NRC: 8/22/81 Date of Occurrence 7/23/81 Time of Occurrence: 0815 Unit 3
Identification and Description of Occurrence:
During normal operation, containment atmosphere monitor (CAM) H,0 analyzer 2
B sample return valves could not be energized. The solenoid le&d wire and relays R2, R5, and 86-76-92A were damaged.
Conditions Prior to Occurrence:
Unit 1 in refueling outage Unit 2 at 99%.
Unit 3 at 100%.
Action Specified in the Technical Specification Surveillance Requirements met
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due to inoperable equipment. Describe.
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None Solenoid coils assembly for FSV-76-67 failed to operate Apparent Cause of' Occurrence:
due to a shorted bridge rectifier and coil. A voltage supply wire was found loose due to a broken screw head. Inadequate design information lead to improper flex conduit connections at FSV-76-67 which allowed the solenoid assembly to be exposed to torus j
environment, permitting corrosion. Corrosion on bridge rectifier failure possibly prevented dissipation of heat and contributed to rectifier f ailure. Screw was probably
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overtorqued by manufacturer.
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 signi-ficant chain of events.
Corrective Action
Replaced FSV-76-67 solenoid assembly and relays R2, R5 and 86-76-92A. Flex conduit connections for FSV-76-63, 76-65, and 76-67 sealed by Flex connector at body end of taping with Scotch 70 and covered with Scotch 33+.
SI 4.7.D.l.B-1(A) and 4.7.H. were saccessfully completed.
FSV-76-67 was replaced.
valves inside the drywell on unit 3 will be checked during the next opportunity H0 22 Consideration is being given to moving these valves outside the for drywell entry.
torus and drywell.
the torus flex connectors will be replaced during the next refueling At a minimum, These valves are outside the torus and drywell on units 1 and 3.
outage.
Failure Data:
None t
Period -- Lifetime; Responsibility - Document Control Supervisor 4
Retention:
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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. 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