LER-1981-019, During Shutdown,When HPCI Sys Initiated,Upper & Lower HPCI Gland Seal Condenser Head Gaskets Were Blown.Caused by Overpressurization of Tube Side of HPCI Gland Seal Condenser.Gaskets Replaced |
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| 2961981019R03 - NRC Website |
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UPDATE REPORT--PRE 7IOUS REPORT DATE 5/15/81 LICENSEE EVENT REPORT w
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~4 60 68 OOCK E T NUM8E R (wl 63 EVENT DATE 14 75 REPOR T D ATE 15 0 6VEN T DESCRIPTION AND PROB ABLE CONSEQUENCES h [n1.'l l During automatic reactor shutdown, when the HPCI system was initiated. the unoer I
gg l and lower HPCI gland seal condenser head gaskets were blown. The HPCI was removed I
i n I.i l l from service to replace the gaskets. There was no danger to the health or safety i
I g o j., i l of the public. Redundant systems were operable. Previous similar events: B FRO l l g l 260/74016W, 74017W, 74024W, and 74028W.
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40 di 42 43 44 47 CAUSC DESCRIPTION AND CORRECTIVE ACTIONS h I i I o ! LOverpressurization of the tube side of the HPCI stland seal condenser caused the l
((_TJ Lgaskets to stretch out of place. Caskets were replaced. Graham Manufacturine I
,,i j l Company neoprene gasket; pressure class, 150 psi (design); normal operating pressure, I i,i q l 60 psi.
Special test will be initiated to monitor piping pressures to determine 1
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Tennessee Valley Authority Form BF-17 Erowns Ferry Nuclear Plant BF 15.2 3/24/81 LER SUPPLEMENTAL INFORMATION BFRO 296 / 81019 R1 Technical Specification Involved 3.5.E.l(2)
Reported Under Technical Specification 6.7.2.b.2 Date of Occurrence 4/23/81 Time of Occurrence 0830 Unit 3
Identification and Description of Occurrence:
Unit 3 HPCI inoperable to replace gland seal condenser gaskets.
Conditiens Prior to Occurrence:
Unit i refueling outage Unit 2 at 99%
Unit 3 scram due to low reactor water level.
Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.
Requirements of T.S. 3.5.E.1(2) were met.
l t pparent Cause of Occurrence:
Overpressurizing gland seal condenser (tube side).
Analysis of Occurrence:
l There was no danger to the health or safety of the public, no release of activity.
l no damage to the plant or equipment, and no resulting significant chain of events.
l l
Corrective Action
Replaced head gaskets. Instrumentation will be installed to monitor piping pressures to determine cause of overpressurization.
Failure Data:
BFRO-50-260/74016W, 74017W, 74024W, and 74028W.
- Retention : Period - Lifetime; Responsibility - Document Control Supervisor i
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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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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. 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