LER-1981-021, /03L-0:on 810507,HPCI Gland Seal Condenser Upper Head Gasket Began Leaking During Automatic Reactor Shutdown Sys Initiation.Caused by Head Gasket Stretched Out of Place Due to Overpressurization of Condenser Tube Side |
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| 2601981021R03 - NRC Website |
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EVENT OESCRIPTiON AND PROSA8LE CONSEQUEvCES h PTTI,l During automatic reactor shutdown. when the HPCI system was initiated. the HPCI PTT1 I gland seal condenser upper head gasket began leaking. The HPCI was removed l
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l o I 41 i from service to replace the gasket.
(T.S. 3.5.E.1)
There was no' danger to the I
l o i s i I health or safety of the public. Redundant systems were available and operable.
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CAUSE OESCRIPTION AND CORRECTIVE ACT!ONS h l l i l ;j l overpressurization of the tube side of the HPCI gland seal condenser caused the i
LLLiJ lhend casket to stretch out of place.
The casket was roolaced. Graham Manufactur h 1 1
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'1%nnessee */ alley Authority Form BF-17 Browns Fr.rry Nuclear Plant BF 15.2 0/24/81 LER SUPPLEMENTAL INFORMATION B FRO 260_/ ni n9, Technical Specification Involved 3.5.r:1.(2)
Reported Under Technical Specification _6.7.2.b (2)
Date of Occurrence s/7/81 Time of Occurrence __2306 Unit 2
~
Identification and Description of Occurrence:
Unit 2 HPCI was removed frcm service to replace HPCI gland seal condenser head gasket.
Conditions Prior to Occurrence:
Unit i refueling outage Unit 2 at 59%
Unit 3 at 55%
Action specified in the Technical Specification Surveillance Requirements met due to irnperable equipment. Describe.
Requirements of T.S. 3.5.E.1.(2) were met.
Apparent Cause of Occurrence:
Overpressurizing tube side of HPCI gland seal condenser.
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
Replaced upper head gasket. Instrumentation will be installed to monitor piping pressures to determine cause of overpressurization.
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Failure Data:
BFRO-50-260/76016W, 74017W, 74024W; 296/81019.
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60 61 DOCKET NUM8ER 68 69 EVENT D ATE 74 75 REPORT DATE 80 EVENT OESCRIPTION AND PROBA8LE CONSEQUENCES h I
W,1 During automatic reactor shutdown. when the HPCI system was initiated. the HPCI g i gland saal condenser upper head gasket began leaking. The HPCI was removed l
IoI41 i from service to replace the gasket.
(T.S. 3.5.E.1)
There was no danner to the I
lois! l health or safety of the public. Redundant systems were available and operable.
1 I o is i I Previous similar' events: BFRO-50-260/74016W. 74017W. 74024W; 296/ Rim o_
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M 33 40 el 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Iiloi l Overpressarization of the tube side of the HPCI cland seal condenser cause-i the l
LLJ.>J lhead casket to stretch out of place.
The easket was reolaced. Graham Manuf acturirur I ICompany neoprene gasket; pressure. 150 psi, normal operating pressure, 60 psi.
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'Tannessee Valley Authority Form BF-17 Browns Ftrry Nuclear Plant BF 15.2 3/24/81 LER SUPPLEMENTAL INFORMATION B FRO 260,/
2, n,3 Technical Specification Involved 3.5.E.1.(2)
Reported Under Technical Specification _6.7.2'.b (2)
Date of Occurrence s/7/81 Time of Occurrence J06 Unit 2
Identificein and Description of Occurrence:
Unit 2 HPCI was removed from service to replace HPCI gland seal condenser head gasket.
Cc,nditions Prior to Occurrence:
Unit I refueling outage Unit 2 at 59%
Unit 3 at 55%
Action specified in the Technical Specification Surveillance Requirements met due to irnyerable equipment. Describe.
Requirements of T.S. 3.5.E.1.(2) were met.
Apparent Ca'Ase of Occurrence:
Overpressurizing tube side of HPCI gland seal condenser.
l i
Analysis of Occurrence:
l There was no danger to the health or safety of the public, no release of l
activity, no damage to the plant or equipment, and no resulting significant chain of events.
Corrective Action
Replaced upper head gask.ac.
Instrumentation will be installed to monitor piping pressures to determine cause of overpressurization.
l Failure Data:
l B FRO-50-260/ 76016'n', 74017W, 74024W; 296/g1019, l
- Reten tion : 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. 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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