LER-1980-100, /03L-0:on 801125,RCS Leakage Exceeded Tech Spec Limit.Caused by Faulty Seal Water Injection Filters & Drain Valves.Valves Replaced |
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| 3341980100R03 - NRC Website |
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A liinidentifled Reactnr Coolant System leakace exceeded the Technien1 Specification (TS)
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At 172s hours, the excessive Icak was identified, reduced, l 1 o 151 l and neasured. At 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br />, the measured unidentifted leakace was determined to bel g lwithin the TS limit. The health and safety of the public was not jeopardized since l l
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The valves were tightened closed to reduce Icakage and a temocrarv[
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1 Attachment To LER 80-100/03L Beaver Valley Power Station Duquesne Light Company Docket No. 50-334 Sequence Of Events At 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on November 25, 1980, with the reactor operating at about 46 percent, Operating Sutveillance Test (OST) l'.6.2, Reictor Coolant System Water Inventory Balance, was completed with a measured unidentified leakage of 1.16 gpm.
During the performance of this test, the Reactor Coolant System Tavg decreased by 2*F and pressurizer level decreased by 1.5%.
This means that the operator must use graphs to determine a correction factor, thus possibly adding error to the calculation.
At that time, the operator requested a sample of the steam generators for activity. At 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br />, Chemistry personnel reported that all three steam generators were less than MDA.
At 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, a second water inventory was completed, this time with Tavg held constant and pressurizer level decreasing by only 1%.
Unidentified leakage was calculated to be,2.29 gpm.
At 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br />, Radiation Control personnel reported that air samples taken from the Auxiliary Building 752 f t.
level revealed'the presence of Rb88 of about 27%
of MPC. At 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, preparations for plant shutdown were initiated to comply with Technical Specification 3.4.6.2.
At 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br />, normal charging and letdown were isolated and excess letdown was placed in service in an attempt to isolate a possible leak in the charging or letdown lines.
In the meantime, an operator was sent to check the seal injection filter area with a sonic detector. The seal return filter was bypassed and isolated at 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br />.
At 1725 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.563625e-4 months <br />, the operator at the seal injection filters reported that the sonic detector indicated leakage past the 4B filter drain valve, ICH-309. At that time, the drain piping downstream of the valve was cut and the leakage was measured, using a container, at 1.06 gpm.
Temporary tubing was then installed to direct the leakage to the auxiliary building sump.
At 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br />, the RCS water inventory balance indicated an unidentified leakage of 1.4 gpm. Taking into account the measured 1.06 gpm filter leakage, the actual unidentified leakage was 0.34 gpm.
At 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br />, the line downstream of the 4A seal injection filter drain valve, ICH-308, was cut and the valve was found to be leaking at a rate of approximately 50 ml/ min.
Maintenance Work Requests 802067 and 802070 were written for 1CH-309 and ICH-308, respectively.
The valves are being replaced with identical new valves.
In addition, a series valve is being installed as a backup. A design change is planned to replace these valves (no longer available) with acceptable substitutes.
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| 05000334/LER-1980-001-01, /01T-1:on 870626,discovered That Suction Piping on Vacuum Pump Not Adequately Supported for Seismic Event. Caused by Inaccurate Computer Code Used.Seismically Inadequate Piping Isolated & Support Added | /01T-1:on 870626,discovered That Suction Piping on Vacuum Pump Not Adequately Supported for Seismic Event. Caused by Inaccurate Computer Code Used.Seismically Inadequate Piping Isolated & Support Added | | | 05000334/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000334/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000334/LER-1980-002-01, /01T-0:on 800117,during Operational Mode 5,w/RCS Temp at 100 F & Atmospheric Pressure & RCS Level mid-loop W/ RHR Flow at 1,700 Gpm,Reactor Vessel Vent Educator Was in Svc,Causing Negative Pressure | /01T-0:on 800117,during Operational Mode 5,w/RCS Temp at 100 F & Atmospheric Pressure & RCS Level mid-loop W/ RHR Flow at 1,700 Gpm,Reactor Vessel Vent Educator Was in Svc,Causing Negative Pressure | | | 05000334/LER-1980-003-01, /01T-0:on 800124,overstress Condition Was Confirmed to Exist During Postulated Seismic Event W/Pipe Support H-95 on Component Cooling Water Sys Line CC-323. Caused by Use of Incorrect Method of Pipe Stress Analysis | /01T-0:on 800124,overstress Condition Was Confirmed to Exist During Postulated Seismic Event W/Pipe Support H-95 on Component Cooling Water Sys Line CC-323. Caused by Use of Incorrect Method of Pipe Stress Analysis | | | 05000334/LER-1980-004-03, /03L-0:on 800123,radiation Monitor Setpoints Less Conservative than Those Required in Mode 6 During Refueling Operations.Caused by Personnel Error.Reactor Vessel Head Studs Detensioned | /03L-0:on 800123,radiation Monitor Setpoints Less Conservative than Those Required in Mode 6 During Refueling Operations.Caused by Personnel Error.Reactor Vessel Head Studs Detensioned | | | 05000334/LER-1980-005-03, /03L-0:on 800112,decontamination Proceedings Were in Progress When Waste Water Tank Filled.Operator Instructed to Do Valving in Area Was Not Familiar W/Tech Specs & Failed to Have Radiation Technician or Ratemeter Available | /03L-0:on 800112,decontamination Proceedings Were in Progress When Waste Water Tank Filled.Operator Instructed to Do Valving in Area Was Not Familiar W/Tech Specs & Failed to Have Radiation Technician or Ratemeter Available | | | 05000334/LER-1980-006-04, /04T-0:on 800130,tritium Activity in Quarterly Grab Samples Collected in Oh River Near Facility Discharge During Fourth quarter,1979 Exceeded ETS But Below 10CFR20 Limits | /04T-0:on 800130,tritium Activity in Quarterly Grab Samples Collected in Oh River Near Facility Discharge During Fourth quarter,1979 Exceeded ETS But Below 10CFR20 Limits | | | 05000334/LER-1980-007-01, Er 80-007/01T-0:on 800121,during Reload After Defueling, Main Filter Banks Found Not in Svc.Caused by Procedural Inadequacy Because None of Refueling Checklists Indicated Tech Spec Change That Required Flow | Er 80-007/01T-0:on 800121,during Reload After Defueling, Main Filter Banks Found Not in Svc.Caused by Procedural Inadequacy Because None of Refueling Checklists Indicated Tech Spec Change That Required Flow | | | 05000334/LER-1980-008, Forwards LER 80-008/01T-1 | Forwards LER 80-008/01T-1 | | | 05000334/LER-1980-008-01, /01T-1:on 800225,during in-plant Insp,Potential Overstress Condition of Cable Spreading Room Floor Indicated Due to Postulated Seismic Loading.Caused by Utilizing Underside of Floor to Higher Degree than Original Design | /01T-1:on 800225,during in-plant Insp,Potential Overstress Condition of Cable Spreading Room Floor Indicated Due to Postulated Seismic Loading.Caused by Utilizing Underside of Floor to Higher Degree than Original Design | | | 05000334/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000334/LER-1980-009-03, /03L-0:on 800201,loss of Power Occurred on 138 Kv Bus 1.Emergency Diesel Generator 1 auto-started on Loss of Offsite Power to 4160-volt 1A Station Svc Transformer.Caused by Faulty Backup Relay Timer | /03L-0:on 800201,loss of Power Occurred on 138 Kv Bus 1.Emergency Diesel Generator 1 auto-started on Loss of Offsite Power to 4160-volt 1A Station Svc Transformer.Caused by Faulty Backup Relay Timer | | | 05000334/LER-1980-010-03, /03L-0:on 800131,refueling Team Was Given Go Ahead for Core Alterations.Fifteen Minutes Later,Inservice Boric Acid Transfer Pump CH-P-2B Tripped on Thermal Overload. Probably Caused by Faulty Blender Controls Shifting Speed | /03L-0:on 800131,refueling Team Was Given Go Ahead for Core Alterations.Fifteen Minutes Later,Inservice Boric Acid Transfer Pump CH-P-2B Tripped on Thermal Overload. Probably Caused by Faulty Blender Controls Shifting Speed | | | 05000334/LER-1980-011-03, /03L-0:on 800226,during Boron Injection Flow Path Verification,Operator Stroked MOV-SI-869A Connecting Charge Sys Fill Header to RCS Hot Leg Piping.Valve Opened & Linestarter Tripped.Caused by Burnt Motor in MOV-SI-869A | /03L-0:on 800226,during Boron Injection Flow Path Verification,Operator Stroked MOV-SI-869A Connecting Charge Sys Fill Header to RCS Hot Leg Piping.Valve Opened & Linestarter Tripped.Caused by Burnt Motor in MOV-SI-869A | | | 05000334/LER-1980-012-01, /01T-0:on 800312,emergency Shutdown Panel Auxiliary Feedwater Flow Instrumentation Readings Were Deleted from Surveillance Testing.Caused by Meter Reading Zero in Standby | /01T-0:on 800312,emergency Shutdown Panel Auxiliary Feedwater Flow Instrumentation Readings Were Deleted from Surveillance Testing.Caused by Meter Reading Zero in Standby | | | 05000334/LER-1980-013-04, /04T-0:on 800302,during Maint Surveillance,Cooling Tower Blowdown Temp Indicator Found Out of Calibr.Caused by Instrument Drift.Instrument Recalibr | /04T-0:on 800302,during Maint Surveillance,Cooling Tower Blowdown Temp Indicator Found Out of Calibr.Caused by Instrument Drift.Instrument Recalibr | | | 05000334/LER-1980-013, Forwards LER 80-013/04T-0 | Forwards LER 80-013/04T-0 | | | 05000334/LER-1980-014-04, /04T-0:800307,during Radiation Monitor Surveillance Test,Liquid Waste Effluent Monitor Did Not Alarm & Discharge Valve Did Not Close.Caused by Loose Relay & Solder Joints in Wiring.Deficiencies Corrected | /04T-0:800307,during Radiation Monitor Surveillance Test,Liquid Waste Effluent Monitor Did Not Alarm & Discharge Valve Did Not Close.Caused by Loose Relay & Solder Joints in Wiring.Deficiencies Corrected | | | 05000334/LER-1980-015-04, /04T-0:800308,during Radiation Monitor Surveillance Test,Component Cooling Water Radiation Monitor high-high Level Alarm Did Not Function.Caused by Alarm Potentiometer Out of Adjustment | /04T-0:800308,during Radiation Monitor Surveillance Test,Component Cooling Water Radiation Monitor high-high Level Alarm Did Not Function.Caused by Alarm Potentiometer Out of Adjustment | | | 05000334/LER-1980-016-03, /03L-0:on 800311,while Testing Battery Charger 2, Ac Input Breaker Tripped.Caused by Loose Control Wiring. Loose Wires Resoldered | /03L-0:on 800311,while Testing Battery Charger 2, Ac Input Breaker Tripped.Caused by Loose Control Wiring. Loose Wires Resoldered | | | 05000334/LER-1980-017-01, /01T-0:on 800326,reanalysis of Seismic Pipe Stress of Main Steam Piping Inside Valve House for OBE long-term Criteria Showed,For Some Conditions,Allowable Stress Level May Be Exceeded in Headers for Main Steam Relief Valves | /01T-0:on 800326,reanalysis of Seismic Pipe Stress of Main Steam Piping Inside Valve House for OBE long-term Criteria Showed,For Some Conditions,Allowable Stress Level May Be Exceeded in Headers for Main Steam Relief Valves | | | 05000334/LER-1980-017, Updated LER 80-017/01T-1:on 800326,reanalysis of Piping & Supports for Main Steam Sys Outside Containment Revealed Design Deficiencies If All Five Safety Relief Valves Opened on Any Manifold.Caused by Load Resulting from Open V | Updated LER 80-017/01T-1:on 800326,reanalysis of Piping & Supports for Main Steam Sys Outside Containment Revealed Design Deficiencies If All Five Safety Relief Valves Opened on Any Manifold.Caused by Load Resulting from Open Valves | | | 05000334/LER-1980-018-01, /01T-0:on 800326,plant Operators Were Testing Temporary Fire Pump When Section of Fire Main Failed.Caused by Piping Failure.Failed Section of Piping Replaced | /01T-0:on 800326,plant Operators Were Testing Temporary Fire Pump When Section of Fire Main Failed.Caused by Piping Failure.Failed Section of Piping Replaced | | | 05000334/LER-1980-019-03, /03L-0:on 800310,while Steam Flushing,Crack Found in Channel Head of Liquid Waste Evaporator Bottoms Heat Exchanger.Caused by Equipment Failure,Probably Due to Chloride Stress Corrosion.Sleeve Welded Over Channel Head | /03L-0:on 800310,while Steam Flushing,Crack Found in Channel Head of Liquid Waste Evaporator Bottoms Heat Exchanger.Caused by Equipment Failure,Probably Due to Chloride Stress Corrosion.Sleeve Welded Over Channel Head | | | 05000334/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000334/LER-1980-020-03, /03L-0:on 800329,during Operations to Increase Level in RCS Loops,Vol Control Tank Outlet MOV-CH-115C Found Closed.Vol Control Tank Level Indicated Normally.Caused by Bad Fuse Holder for Level Bistable.Fuse Holder Replaced | /03L-0:on 800329,during Operations to Increase Level in RCS Loops,Vol Control Tank Outlet MOV-CH-115C Found Closed.Vol Control Tank Level Indicated Normally.Caused by Bad Fuse Holder for Level Bistable.Fuse Holder Replaced | | | 05000334/LER-1980-021, Has Been Cancelled | Has Been Cancelled | | | 05000334/LER-1980-022, Forwards LER 80-022/01T-0 | Forwards LER 80-022/01T-0 | | | 05000334/LER-1980-022-01, /01T-0:on 800408,while Attempting to Increase RHR Flow to Tech Spec Value Required for Dilution,Total Loss of Flow Was Experienced.Caused by Pump Not Being Vented When Flow Increase Was Initiated.Operating Procedures Revised | /01T-0:on 800408,while Attempting to Increase RHR Flow to Tech Spec Value Required for Dilution,Total Loss of Flow Was Experienced.Caused by Pump Not Being Vented When Flow Increase Was Initiated.Operating Procedures Revised | | | 05000334/LER-1980-023, Forwards LER 80-023/01T-0 | Forwards LER 80-023/01T-0 | | | 05000334/LER-1980-023-01, /01T-0:on 800411,during Operational Mode 5,w/ Steam Generators Drained & RCS Level mid-span in Loops, Complete Loss of RHR Flow Occurred While Plant Operators Were Increasing RHR Heat Exchanger Flow | /01T-0:on 800411,during Operational Mode 5,w/ Steam Generators Drained & RCS Level mid-span in Loops, Complete Loss of RHR Flow Occurred While Plant Operators Were Increasing RHR Heat Exchanger Flow | | | 05000334/LER-1980-024-03, /03L-0:on 780428,audit Revealed That Weekly Surveillance Tests on Boric Acid Pumps Missed During Wk of 780810.Caused by Operator Error Due to Confusion Between Modes.Test Scheduling Mods Have Been Made | /03L-0:on 780428,audit Revealed That Weekly Surveillance Tests on Boric Acid Pumps Missed During Wk of 780810.Caused by Operator Error Due to Confusion Between Modes.Test Scheduling Mods Have Been Made | | | 05000334/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000334/LER-1980-025-01, /01T-0:on 800415,during Tank Mod Project,Weld on 12-inch Nozzle Penetration to Refueling Water Storage Tank OS-TK-1 Reported Not to Be in Conformance W/Design.Caused by Failure of Manufacturer to Follow Drawings | /01T-0:on 800415,during Tank Mod Project,Weld on 12-inch Nozzle Penetration to Refueling Water Storage Tank OS-TK-1 Reported Not to Be in Conformance W/Design.Caused by Failure of Manufacturer to Follow Drawings | | | 05000334/LER-1980-025, Forwards LER 80-025/01T-0 | Forwards LER 80-025/01T-0 | | | 05000334/LER-1980-026, Forwards LER 80-026/03L-0 | Forwards LER 80-026/03L-0 | | | 05000334/LER-1980-026-03, /03L-0:on 800422,pump Being Used to Start Liquid Waste Discharge Observed to Have Higher than Normal Flow. Caused by Leaking Effluent Valves.Corrective Actions Scheduled to Be Completed as Soon as Possible | /03L-0:on 800422,pump Being Used to Start Liquid Waste Discharge Observed to Have Higher than Normal Flow. Caused by Leaking Effluent Valves.Corrective Actions Scheduled to Be Completed as Soon as Possible | | | 05000334/LER-1980-027-03, During Maint of Diesel Generator Lube Oil Cooler,Internals of River Water Check Valve Discovered in Cooler.Caused by Flutter Due to High Flow Conditions Eroding Hinge Pin Guide.Valve Replaced | During Maint of Diesel Generator Lube Oil Cooler,Internals of River Water Check Valve Discovered in Cooler.Caused by Flutter Due to High Flow Conditions Eroding Hinge Pin Guide.Valve Replaced | | | 05000334/LER-1980-027, Forwards Updated LER 80-027/03L-1 | Forwards Updated LER 80-027/03L-1 | | | 05000334/LER-1980-028-03, /03L-0:on 800504,power Was Lost to Vital Bus Inverter 4 Due to Blown Main Power Supply Fuse.Cause Unknown.Fuse & Rectifier Replaced.Frequency Adjusted | /03L-0:on 800504,power Was Lost to Vital Bus Inverter 4 Due to Blown Main Power Supply Fuse.Cause Unknown.Fuse & Rectifier Replaced.Frequency Adjusted | | | 05000334/LER-1980-029, Forwards LER 80-029/03L-0 | Forwards LER 80-029/03L-0 | | | 05000334/LER-1980-029-03, /03L-0:on 800409,during Performance of Containment Isolation Check Valves Test,Found Safety Injection Accumulator Fill Line Check Valve Opened Beyond Limits of Tech Spec.Cause Under Investigation | /03L-0:on 800409,during Performance of Containment Isolation Check Valves Test,Found Safety Injection Accumulator Fill Line Check Valve Opened Beyond Limits of Tech Spec.Cause Under Investigation | | | 05000334/LER-1980-030-01, /01T-0:on 800519,plant Operators Testing diesel- Driven Fire Pump When High Temp Alarm Was Received & Diesel Overheated.Caused by Brittle Fan Belt Slipping | /01T-0:on 800519,plant Operators Testing diesel- Driven Fire Pump When High Temp Alarm Was Received & Diesel Overheated.Caused by Brittle Fan Belt Slipping | | | 05000334/LER-1980-031-01, /01T-0:on 800521,upon Finding Leaking RHR Sys Vent Valve Weld,Evaluation Commenced to re-energize RHR Isolation Valve in Case of Gross Failure.Caused by de-energized Process Control Signal & Vent Weld Leak | /01T-0:on 800521,upon Finding Leaking RHR Sys Vent Valve Weld,Evaluation Commenced to re-energize RHR Isolation Valve in Case of Gross Failure.Caused by de-energized Process Control Signal & Vent Weld Leak | | | 05000334/LER-1980-031, Forwards LER 80-031/01T-0 | Forwards LER 80-031/01T-0 | | | 05000334/LER-1980-032-03, /03L-0:on 800503,during Control Board Insp,Vol Control Tank Outlet Valve Was Found Shut.Caused by Short Circuited Lead in Level Comparator.Shorted Wire Replaced | /03L-0:on 800503,during Control Board Insp,Vol Control Tank Outlet Valve Was Found Shut.Caused by Short Circuited Lead in Level Comparator.Shorted Wire Replaced | | | 05000334/LER-1980-033, Forwards LER 80-033/03L-0 | Forwards LER 80-033/03L-0 | | | 05000334/LER-1980-033-03, /03L-0:on 800617,diesel Generator 1 Governor Control Motor Failed.Caused by Cycling of Governor While Attempting to Shut Down Diesel W/Fast Start Signal Still Applied.Motor Replaced | /03L-0:on 800617,diesel Generator 1 Governor Control Motor Failed.Caused by Cycling of Governor While Attempting to Shut Down Diesel W/Fast Start Signal Still Applied.Motor Replaced | | | 05000334/LER-1980-034-03, /03L-0:on 800512,during Air Flow Surveillance Test on Fire Suppression Sys,Approx 50% of Sprinkler Nozzles Found Plugged.Caused by Rust & Unidentified Matl.Nozzles Will Be Cleaned & Sys Blown Down W/Air | /03L-0:on 800512,during Air Flow Surveillance Test on Fire Suppression Sys,Approx 50% of Sprinkler Nozzles Found Plugged.Caused by Rust & Unidentified Matl.Nozzles Will Be Cleaned & Sys Blown Down W/Air | |
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