Concept:JAF LER
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Description of concept "JAF LER"RDF feed
LERs by JAF
[[Category:Licensee Event Report]] [[Site::FitzPatrick]]
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- 05000333/LER-1917-003, Regarding Inadvertent Isolation of the High Pressure Coolant Injection System +
- 05000333/LER-1917-004, Regarding Safety Relief Valves Out of Tolerance +
- 05000333/LER-1978-008, Forwards LER 78-008/03L-0 +
- 05000333/LER-1978-008-03, /03L-0 on 780210:during Normal Plant Operation, Smoke Emanated from Supply Breaker for 13MOV131 Reactor Core Overload.Caused by Electrical Overload.Damaged Parts Replaced +
- 05000333/LER-1978-043, Forwards LER 78-043/01X-1 +
- 05000333/LER-1978-043-01, /01X-1 on 780616:3 Motors Had Electrical Winding Insulation Qualified to 250 F Rather than 295 F.Motors Were Rewound with Proper Insulation During 1978 Outage +
- 05000333/LER-1978-048, :Number Not Used +
- 05000333/LER-1978-056, Forwards LER 78-056/03L-1 +
- 05000333/LER-1978-056-03, /03L-1:on 780722,core Spray Sys Outboard Isolation Valve Would Not Close.Caused by Sheared Limitorque Shaft Key.Key Replaced +
- 05000333/LER-1978-059, Forwards LER 78-059/03L +
- 05000333/LER-1978-059-03, /03L-0 on 780805:primary Containment Pressure Suppression Pool Level Exceeded Tech Specs Limit by Two Inches.Caused by Operator Failure to Isolate RHR Sys from keep-full Subsys +
- 05000333/LER-1978-075, Forwards LER 78-075/03L-1 +
- 05000333/LER-1978-075-03, /03L-1:on 780902,during Surveillance Test F-ST-3D, Normally Closed Inboard Core Spray Injection Valve 14-MOV-12B Failed to Open Electrically,Causing Sys Inoperability.Caused by High Differential Pressure +
- 05000333/LER-1978-079, Forwards LER 78-079/04L-0 +
- 05000333/LER-1978-079-04, /04L-0 on 780914:An Apparent Excessive Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Was Detected While Performing Aug 78 24-hour Complete Sample Analysis +
- 05000333/LER-1978-080, Forwards LER 78-080/03X-1 +
- 05000333/LER-1978-080-03, /03X-1 on 780914:noted That Valves in Pressure Suppression Chamber to Drywell Vacuum Breakers Were Never Subjected to Local Leak Rate Tests.Testing Will Be Completed During Refueling Outage Begun on 780916 +
- 05000333/LER-1978-081, Forwards LER 78-081/03L-0 +
- 05000333/LER-1978-081-03, /03L-0 on 780915:circuit Breaker for RHR Pump 10-P 10-P-3C Would Not Charge. Caused by Bending of Control Pwr Fuse Holder Causing Pump Circuit Breaker Not to Make Contact +
- 05000333/LER-1978-082, Forwards LER 78-082/03L-0 +
- 05000333/LER-1978-082-03, /03L-0:on 780920,during Refueling Shutdown, Pressure Suppression Pool Torus Level Increased to 0.8 Inches Above Tech Spec Limit.Caused by Leaking Past Seat of Safety Relief Valve +
- 05000333/LER-1978-085, Forwards LER 78-085/04X-1 +
- 05000333/LER-1978-085-04, /04X-1 on 781006:3rd Quarter Release of Halogens & Particulates Greater than Tech Specs.Caused by Steam Leaks & Fuel Pin Clad Performance +
- 05000333/LER-1978-086, Forwards LER 78-086/03L-0 +
- 05000333/LER-1978-086-03, /03L-0;on 781016,during Refuel Shutdown,Two Elec Conduits Passing Through Safety Related Area Fire Barrier Found to Be Improperly Sealed in Violation of Tech Spec. Both Penetrations Immediately Sealed +
- 05000333/LER-1978-087, Forwards LER 78-087/04T-0 +
- 05000333/LER-1978-087-04, /04T-0 on 781018:Environ Radiological Monitoring Sample of Periphyton Samples Pci/Gm(Wet)Does Not Meet Subj Facil Tech Spec Append B,Paragraph 5.6.2.6 +
- 05000333/LER-1978-088, Forwards LER 78-088/04L-0 +
- 05000333/LER-1978-088-04, /04L-0 on 781024:excess Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Detected.Caused by Unsound Sampling & Method of Determining Concentrations & Dissolved Solids +
- 05000333/LER-1978-089, Forwards LER 78-089/03L-0 +
- 05000333/LER-1978-089-03, /03L-0 on 781101:during Refueling & Maint Shutdown It Was Found That Surveillance Test Had Not Been Performed for Combustion Ionization Products Smoke Detectors Installed in Diesel Fire Pump Room on 780310,due to Oversight +
- 05000333/LER-1978-090, Forwards LER 78-090/03L-0 +
- 05000333/LER-1978-091, Forwards LER 78-091/03L-0 +
- 05000333/LER-1978-091-03, /03L-0 on 781201:low Level Radiation Test of Containment Penetrations Was Conducted & Indicated Leakage Exceeded Value of La Specified in Tech Specs.Probable Cause: Isolation Valves Associated W/ Penetrations +
- 05000333/LER-1978-092, Forwards LER 78-092/04L-0 +
- 05000333/LER-1978-092-04, /04L-0 on 781130:excessive Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel.Believe Method of Determining Solute Concentration Is Unsound +
- 05000333/LER-1978-093, Forwards LER 78-093/03L-0 +
- 05000333/LER-1978-093-03, /03L-0 on 781204:wiring Error Found on 10% Closure Position Switch for Inboard Main Steam Isolation Valve B(29-AOV-8OB).Caused by Crossed Wires +
- 05000333/LER-1978-094, Forwards LER 78-094/03L-0 +
- 05000333/LER-1978-094-03, /03L-0 on 781122:during Shutdown & Surveillance Test,A Number of Battery Cells Were Found W/Specific Gravity &/Or Individual Cell Voltage Variations(High or Low) Greater than Allowed by Test Acceptance Criteria +
- 05000333/LER-1978-095, Forwards LER 78-095/03L-0 +
- 05000333/LER-1978-095-03, /03L-0 on 781206:during Refueling Outage,Some Fire Barrier Electrical Penetration Sleeves Were Intentionally Opened to Install New Cable.A Fire Watch Was Present & Penetrations Were Resealed & Inspected +
- 05000333/LER-1978-096, Forwards LER 78-096/03L-0 +
- 05000333/LER-1978-096-03, /03L-0 on 781206:reactor Coolant Sample Indicated a Chloride Ion Sample of 0.180 Ppm Due to Inadvertent Contamination of the Sample W/Matl Containing High Amounts of Chloride Ions +
- 05000333/LER-1978-097, Forwards LER 78-097/01X-1 +
- 05000333/LER-1978-097-01, /01X-1 on 781215:during Instrument Surveillance Procedure F-ISP 10,the 8 Temp Switches Associated W/ Isolation of HPCI Sys Steam Line Were Set Above Tech Spec Limits.Caused by Use of Wrong Conversion Table +
- 05000333/LER-1978-098, Forwards LER 78-098/03L-0 +
- 05000333/LER-1978-098-03, /03L-0 on 781205:emergency Diesel Generator a Tripped When Being Paralleled to Bus.Caused by Misadjustment of Engine Governor After Extended Maintenance Period +
- 05000333/LER-1978-099, Forwards LER 78-099/04T-0 +
- 05000333/LER-1978-099-04, /04T-0 on 781220:activity Levels of Co-60 & Mn-54 in Several Radiological Monitoring Samples Were Greater than 10 Times the Control Station Activity Levels +
- 05000333/LER-1978-100, Forwards LER 78-100/03L-0 +
- 05000333/LER-1978-100-03, /03L-0 on 781209:rod-block Monitor Upscale & Downscale Instrument Functional Check Could Not Be Completed.Malfunction Disappeared & Could Not Be Duplicated +
- 05000333/LER-1978-101, Forwards LER 78-101/03L-0 +
- 05000333/LER-1978-101-03, /03L-0 on 781209:primary Containment Could Not Be Inerted W/Nitrogen to Reduce Oxygen Concentration to Less That 4% by Weight.Caused by Incorrect Operating Procedure Info +
- 05000333/LER-1978-102, Forwards LER 78-102/03L-0 +
- 05000333/LER-1978-102-03, /03L-0 on 781210:during Startup,Pressure Suppression Chamber (Torus) Water Level Exceed High Level Limits of Tech Specs by 1.5 In,Due to Establishing drywell- to-torus Differential Pressure of 1.7 Psi +
- 05000333/LER-1978-103, Forwards LER 78-103/03L-0 +
- 05000333/LER-1978-103-03, /03L-0 on 781211:during Shutdown for Refueling & Maint Insp of snubbers,4 Snubbers Were Declared Inoperable. Caused by Loss of Hydraulic Fluid in Snubbers +
- 05000333/LER-1978-104, Forwards LER 78-104/03L-0 +
- 05000333/LER-1978-104-03, /03L-0 on 781213:while Performing Operations Surveillance Test F-ST-76C,indicated Volume of Diesel Fuel Oil at Hand Was Below Tech Spec Minimum.Caused by Erroneous Initial Fuel Capacity Readings & Calculations +
- 05000333/LER-1978-105, Forwards LER 78-105/03L-0 +
- 05000333/LER-1978-105-03, /03L-0 on 781214:operations Surveillance Test F-ST-15A,torus Water Level Exceeded Tech Spec Requirements, Due to drywell-to-torus Differential Pressure Drop to 0 Psi Caused by Test +
- 05000333/LER-1978-106, Forwards LER 78-106/03L-0 +
- 05000333/LER-1978-106-03, /03L-0 on 781220:noted Coupling Key for Containment Pressure Suppression Pool Nitrogen Purge Supply valve(27-AOV-115)was Disengaged.Cause Unknown +
- 05000333/LER-1978-107, Forwards LER 78-107/03L-0 +
- 05000333/LER-1978-107-03, /03L-0 on 781221:combustion Ionization Product (Smoke) Detectors for Relay Room Intentionally Disabled During Repair Work.Detectors Verified Operable Following Repair Work +
- 05000333/LER-1978-108, Forwards LER 78-108/04L-0 +
- 05000333/LER-1978-108-04, /04L-0 on 781217:apparent Excessive Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel.Cause Not Stated +
- 05000333/LER-1978-109, Forwards LER 78-109/03L-0 +
- 05000333/LER-1978-109-03, /03L-0 on 781224:the a Residual Heat Removal Loop Could Not Be Maintained Full of Water Because a Discharge Check Valve Was Not Closing Properly.Disassembly Revealed No Cause for Sticking +
- 05000333/LER-1978-110, Forwards LER 78-110/04L-0 +
- 05000333/LER-1978-110-04, /04L-0 on 781223:during Operation at 68% Power, Storm W/High Winds Resulted in Heavy Concentrations of Algae on Travelling Water Screens.Caused by Unusually Heavy Intake of Algae from Lake Ontario +
- 05000333/LER-1978-111, Forwards LER 78-111/03L-0 +
- 05000333/LER-1978-111-03, /03L-0 on 781224:during Routine Plant Startup Operations,Eccs Equipment Was Started Automatically in Response to High Drywell Pressure Signal.Caused by Personnel Error +
- 05000333/LER-1978-112, Forwards LER 78-112/03L-0 +
- 05000333/LER-1978-112-03, /03L-0 on 781226:discovered That Surveillance Requirements Not Performed on Air Operated Isolation Valves. Procedures Revised & Testing Completed W/Satisfactory Results +
- 05000333/LER-1979-001, Forwards LER 79-001/03L-0 +
- 05000333/LER-1979-001-03, /03L-0 on 790105:failure to Perform Core Performance Surveillance on 781210 & 781223.Currently Developing Surveillance Test Checkoff List,To Ensure That Test Is Not Overlooked Again +
- 05000333/LER-1979-002, Forwards LER 79-002/03L-0 +
- 05000333/LER-1979-002-03, /03L-0 on 790108:flow Biased Portion of Average Power Range Monitor B Inoperable.Caused by Operational Amplifier Failure.Circuit Board Replaced +
- 05000333/LER-1979-003, Forwards LER 79-003/03L-0 +
- 05000333/LER-1979-003-03, /03L-0 on 790115:during Mainsteam Flow, Surveillance Procedure Instrument 02-DPIS-116B Found Set at 110 psid,2 Psid Above Tech Spec Max Due to Drift in Differential Pressure Switch +
- 05000333/LER-1979-004, Forwards LER 79-004/03L-0 +
- 05000333/LER-1979-004-03, /03L-0 on 790119:while Performing Operations Surveillance Test F-St-76D,water Leak Noted on Post Indicator Valve 76-FPS-30 & Discovered Water Leaking from Lubrication Line.Caused by Shovel Cut During Snow Removal +
- 05000333/LER-1979-005, Forwards LER 79-005/04L-0 +
- 05000333/LER-1979-005-04, /04L-0 on 790124: Apparent Excessive Solution Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Noted.Calculations Show Tech Specs Not Exceeded +
- 05000333/LER-1979-006, Forwards LER 79-006/03X-1 +
- 05000333/LER-1979-006-03, /03X-1:on 790124,during Normal Operations,Ground Fault on 125 Station Battery a Noted.Caused by Bellows Failure on Pressure Switch Circuit safety-relief Valve 02-RV-71J.Ground Cleared.Valve Restored to Operation +
- 05000333/LER-1979-007, Forwards LER 79-007/03L-0 +
- 05000333/LER-1979-007-03, /03L-0 on 790125:jet Pump Operability Surveillance Had Not Been Conducted on 790123-24 as Required.Procedures Subsequently Revised +
- 05000333/LER-1979-008, Forwards LER 79-008/03L-0 +
- 05000333/LER-1979-008-03, /03L-0 on 790125:core Performance Surveillance Not Done on 790120-22.Operations Surveillance Test for Daily Checks Was Being Developed to Include check-off of Surveillance Requirements.Caused by Operator Error +
- 05000333/LER-1979-009, Forwards LER 79-009/03L-0 +
- 05000333/LER-1979-009-03, /03L-0 on 790205:rod Control Drive Rendered Inoperable in Order to Repair Leak in Control Rod Drive Sys Hydraulic Control Unit.Upon Completion of Repair,All Components Returned to Svc +
- 05000333/LER-1979-010, Forwards LER 79-010/03L-0 +
- 05000333/LER-1979-010-03, /03L-0 on 790202:step Increase in Indicated Core Flow.Caused by Earlier Failure of Square Root Computation Module for Jet Pump.Square Root Computation Module Replaced W/Identical Unit & Core Flow Evaluation Test Completed +
- 05000333/LER-1979-011, Forwards LER 79-011/03L-0 +
- 05000333/LER-1979-011-03, /03L-0 on 790214:drywell Atmospheric Sample Isolation Valve 27-SOV-123B Blew a Fuse.Caused by Shorted Valve Solenoid.Incident Recurred 790306.Will Submit Followup Rept When Valve Replacement Is Completed +
- 05000333/LER-1979-014, Forwards LER 79-014/01T-0 +
- 05000333/LER-1979-014-01, /01T-0 on 790312:calculations in Piping Stress Analysis Are Being Redone on Accelerated Basis by Architect/Engineer.Shutdown Will Continue Until All Problems Are Resolved.Final Rept on Matter Is Forthcoming +
- 05000333/LER-1979-015, Forwards LER 79-015/03X-1 +
- 05000333/LER-1979-015-03, /03X-1:on 790315,during Load Reduction & Shutdown, Rod Sequence Control Sys Failed to Pass Operations Surveillance Test F-ST-23A.Cause Unstated.Mode Switch Moved from Shutdown Position.Sys Repaired +
- 05000333/LER-1979-020, Forwards Revised LER 79-020/03X-1 +
- 05000333/LER-1979-020-03, During Normal Cold Shutdown,Operations Surveillance Testing Revealed That Emergency Diesel Generator Starting Air Compressor 93-AC-B1 Did Not Load Properly.Caused by Dirt in Unloader +
- 05000333/LER-1979-023, Forwards Revised LER 79-023/99X-1 +
- 05000333/LER-1979-023-99, Fire Protection Piping Associated W/Hpci Maint Intentionally to Permit Required HPCI Maint.Partial Disassembly of Fire Protection Piping Required.Following Maint,Piping Restored +
- 05000333/LER-1979-024, Forwards Revised LER 79-024/03X-1 +
- 05000333/LER-1979-024-03, Emergency Svc Water Pump Failed to Meet Shutoff Head Requirements of Tech Spec. Caused by Normal Wear.Overhaul & Minor Mod of Impeller by Manufacturer Restored Shutoff Head to within Tech Specs +
- 05000333/LER-1979-026, Forwards LER 79-026/03L-0 +
- 05000333/LER-1979-026-03, /03L-0 on 790507:radwaste Bldg Exhaust Fan 69-FN-8A Did Not Trip Per Hi-Hi Radiation Signal.Caused by Misadjusted Position Switch Associated W/Discharge Damper. Switch Linkage Adjusted +
- 05000333/LER-1979-027, Forwards LER 79-027/03L-0 +
- 05000333/LER-1979-027-03, /03L-0 on 790514:instrument 02-3-LIS-72D Tripped Minus 47.3 Inches.Instrument Recalibr,Then Replaced.Weekly Testing Will Continue to Assure Good Performance +
- 05000333/LER-1979-028, Forwards LER 79-028/03L-0 +
- 05000333/LER-1979-028-03, /03L-0 on 790517:during Cold Shutdown,Level Instrument of Carbon Dioxide Storage Sys Was Out of Calibr. Caused by Procedural Error.Instrument Racalibr & Satisfactorily Tested +
- 05000333/LER-1979-029, Forwards LER 79-029/03L-0 +
- 05000333/LER-1979-029-03, /03L-0 on 790518:during Snubber insp,14 Snubbers Required Some Work & Six Snubbers Were Determined to Be Potentially Inoperable.Snubbers Removed & Tested.Two Snubbers Failed Test & Were Declared Inoperable +
- 05000333/LER-1979-030, Forwards LER 79-030/03L-0 +
- 05000333/LER-1979-030-03, /03L-0 on 790518:during Cold Shutdown,Test Point Was Discovered in Error.Caused by Deviations in Conduction of Surveillance Test Procedures F-ISP-89.Procedure Was Immediately Correted & Surveillance Complete +
- 05000333/LER-1979-031, Forwards LER 79-031/03L-0 +
- 05000333/LER-1979-031-03, /03L-0 on 790519:fire Door Between North & South Emergency Switch Gear Rooms Failed to Close on Automatic Signal.Door & Closing Mechanism Lubricated & Adjusted +
- 05000333/LER-1979-032, Forwards LER 79-032/03L-0 +
- 05000333/LER-1979-032-03, /03L-0 on 790519:sequencing Timer Associated W/Total Flooding Carbon Dioxide Sys Not Functioning Properly.Cause Not Stated.Sequencing Timer Cams Adjusted +
- 05000333/LER-1979-033, Forwards LER 79-033/03L-0 +
- 05000333/LER-1979-033-03, /03L-0 on 790524:during Review of Plant Sys, Determined That Reactor Bldg Cooling Sys Supply & Return Lines to Drywell Equipment Drain Sump Did Not Have Seismic Stress Analysis Performed.Uncertain If It Is Required +
- 05000333/LER-1979-034, Forwards LER 79-034/03L-0 +
- 05000333/LER-1979-034-03, /03L-0 on 790531:data Sheets Associated W/Instrument Surveillance Procedures F-ISP-4.5 Had Not Been Revised as Part of Procedure Revision Which Changed Instruments Calibr Range.Personnel Reinstructed +
- 05000333/LER-1979-035, Forwards LER 79-035/03L-0 +
- 05000333/LER-1979-035-03, /03L-0 on 790607:suction Pressure Switch 13PS-67A Found to Trip at 15.7 Inches of Mercury.Pressure Switch Recalibr & Operations Verified by Completing Surveillance Procedure F-ISP-14-1 +
- 05000333/LER-1979-036, Forwards LER 79-036/03L-0 +
- 05000333/LER-1979-036-03, /03L-0 on 790611:failure to Perform Scheduled Surveillance Tests.Caused by Failure of Computer to Generate Test Schedule Printout.Tests Immediately Conducted Satisfactorily +
- 05000333/LER-1979-037, Forwards LER 79-037/03L-0 +
- 05000333/LER-1979-037-03, /03L-0 on 790621:while Conducting Operational Surveillance Test F-ST-1B,inboard MSIV 29-AOV-80B Required 5.8-s to Reach Full Closed Position.Caused by Failure of Seals on Hydraulic Speed Controls Associated W/Valve +
- 05000333/LER-1979-038, Forwards LER 79-038/03L-0 +
- 05000333/LER-1979-038-03, /03l-0 on 790611:main Steam Line Tunnel High Temp Detectors 02-TS-121A Through 02-TS-124D Could Not Be Demonstrated as Fully Operable Due to Calibr Failure of Instrument 02-TIC-200 +
- 05000333/LER-1979-039, Forwards LER 79-039/03L-0 +
- 05000333/LER-1979-039-03, /03L-0 on 790627:while in Shutdown Condition B Loop LPCI Injection Valve Did Not Open in Response to Automatic Signal.Caused by Failure of Torque Switch in Valve Motor Operator.Torque Switch Was Replaced +
- 05000333/LER-1979-040, Forwards LER 79-040/03L-0 +
- 05000333/LER-1979-040-03, /03L-0 on 790630:during Cold Shutdown,Rhr Sys Not Fully Operable Due to Existence of Leak Flow Path Through Discharge Check Valve for Pump A.Caused by Valve Disc Detaching from Disc Holder.Repairs Are Continuing +
- 05000333/LER-1979-041, Forwards LER 79-041/03L-0 +
- 05000333/LER-1979-041-03, /03L-0 on 790711:procedure for Drywell Equipment Drain Pump Functional Test & Calibr Was in Error.Caused by Implementation of Plant Mod During 1978 Refueling Outage in Which Equipment Pump Level Control Logic Was Revised +
- 05000333/LER-1979-042, Forwards LER 79-042/03L-0 +
- 05000333/LER-1979-042-03, /03L-0 on 790713:RHR Svc Water Pump 10-P-1A & 10-P-1C Could Deliver Only 7800 Gallons Per Minute.Caused by Installation of Improper Orifice in RHR Svc Water Discharge Line.Orifice Removed & Willbe Modified +
- 05000333/LER-1979-043, Forwards LER 79-043/03L-0 +
- 05000333/LER-1979-043-03, /03L-0 on 790718:discharge Check Valve Associated W/Electric Motor Driven Fire Pump Failed to Properly Reseat Following Pump Shutdown.Caused by Small Pebble Between Valve Clapper & Valve Body.Returned to Svc +
- 05000333/LER-1979-044, Forwards LER 79-044/03L-0 +
- 05000333/LER-1979-044-03, /03L-0 on 790720:mainstream Line Tunnel Radiation Monitor D Drifted So That Indicator & Trip Point Were Approx 5.5% Low.Caused by Instrument Drift.Instrument Calibr & Tested +
- 05000333/LER-1979-045, Forwards LER 79-045/03L-0 +
- 05000333/LER-1979-045-03, /03L-0 on 790725:during Conduct of Entitled Containment Hydrogen Analyzer F-ISP-30,one Analyzer Was Found Out of Calibr.Cause Not Stated.Analyzer Recalibr +
- 05000333/LER-1979-046, Forwards LER 79-046/03T-0 +
- 05000333/LER-1979-046-03, /03T-0:on 790830,cables 1HP1ARC103 & 1LKDAR020 Found Routed in Some Areas within Same Cable Tray Sections as Cables Which Provide Power to Safety Relief Valves.Caused by Design Deficiency +
- 05000333/LER-1979-047, Forwards LER 79-047/03L-0 +
- 05000333/LER-1979-047-03, /03L-0:on 790810,operation of Diesel Driven Fire Pump Relief Valve Seemed to Be Sluggish.Fire Sys Placed in Degraded Mode.Relief Valve Spring & Stem Assembly Replaced +
- 05000333/LER-1979-048, Forwards LER 79-048/03L-0 +
- 05000333/LER-1979-048-03, /03L-0:on 790815,during Review of GE Svc Info Ltr 299,determined That Trip Points for low-low-low Water Level Instruments Should Be Readjusted to More Conservative Setpoint in Order to Preclude Possible Instrument Errors +
- 05000333/LER-1979-049, Forwards LER 79-049/03L-0 +
- 05000333/LER-1979-049-03, /03L-0:on 790819,during Conduct of Control Rod Drive Venting & Timing,Control Rod Drive 22-07 Could Not Be Positively Shown to Be Coupled W/Control Rod.Addl Testing, Timing & Analysis Performed Did Not Indicate Cause +
- 05000333/LER-1979-050, Forwards LER 79-050/03L-0 +
- 05000333/LER-1979-050-03, /03L-0:on 790828,during Offgas Process Radiation Monitor Instrument Functional Test,Recorder Did Not Respond to Reading Indicated on Channel a Radiation Monitor. Caused by Faulty Calibrator.Recorder Recalibr +
- 05000333/LER-1979-051, Forwards LER 79-051/04T-0 +
- 05000333/LER-1979-051-04, /04T-O:on 790829,activity Level of Mn-54 Onsite More than 10 Times Control Location (Offsite) for Same Period.Caused by High Bioaccumulation Factor of Manganese in Fresh Water Mollusks Used in Sample +
- 05000333/LER-1979-052, Forwards LER 79-052/04L-0 +
- 05000333/LER-1979-052-04, /04L-0:on 790830,computer Calculations for Condenser Inlet Water & Plant Cooling Water Discharge Temp Differential Temp Were Found Out of Calibr.Cause Not Stated. Instruments Recalibr within Tech Specs Limits +
- 05000333/LER-1979-053, Forwards LER 79-053/03L-0 +
- 05000333/LER-1979-053-03, /03L-0:on 790901,floor Sleeve 1FC023R18 Was Intentionally Opened.Caused by Need to Pull New Cable as Part of Plant Mod.Fire Watch Stationed & Maintained Until Floor Sleeve Was Resealed +
- 05000333/LER-1979-054, Forwards LER 79-054/03L-0 +
- 05000333/LER-1979-054-03, /03L-0:on 790902,during Surveillance Test F-ST-12BB,reactor Bldg Exhaust Monitor 17-RIS-452B Was Found Out of Calibr.Cause Not Stated.Instrument Recalibr to Satisfactory Operation +
- 05000333/LER-1979-055, Forwards LER 79-055/03L-0 +
- 05000333/LER-1979-055-03, /03L-0:on 790902,radwaste Bldg Monitor a Was Found Out of Calibr During Functional Test.Cause Not Given. Instrument Was Repaired & Recalibr +
- 05000333/LER-1979-056, Forwards LER 79-056/01X-1 +
- 05000333/LER-1979-056-01, /01X-1:on 790926,cabling Associated W/Hpci Sys Inboard Steam Supply Isolation Valve & Automatic Depressurization Sys (ADS) Did Not Meet NRC Separation Criteria.Caused by Proximity of HPCI & ADS Cables +
- 05000333/LER-1979-057, Corrects Typographical Error in LER 79-057/01T-0 +
- 05000333/LER-1979-057-01, /01T-0:on 790927,as Result of Pipe Stress Reanalysis,Plant Was Notified That Five Pipe Supports Were Considered Inoperable.Caused by Piping Overstress.All Mods & Analyses Performed within Tech Spec Framework +
- 05000333/LER-1979-058, Forwards LER 79-058/03L-0 +
- 05000333/LER-1979-058-03, /03L-0:on 790903,HPCI Sys Turbine Was Uncoupled from Pump to Allow Overspeed Testing.Caused by Intentional Disabling to Satisfy Insurance Underwriters Requirement. Following Test,Pump & Turbine Recoupled & Sys Operable +
- 05000333/LER-1979-059, Forwards LER 79-059/03L-0 +
- 05000333/LER-1979-059-03, /03L-0:on 790904,during Normal Startup,Leaking Cell Was Noted in Station Battery B.No Cause Stated.Cell Was Jumpered & Battery Was Verified to Be Operable.When Replacement Is Available,Cell Will Be Replaced +
- 05000333/LER-1979-060, Forwards LER 79-060/03L-0 +
- 05000333/LER-1979-060-03, /030-0:on 790904,reactivity Required to Demonstrate Shutdown Margin Was Found to Be Larger than Value Used During Demonstration at Beginning of Current Fuel Cycle +
- 05000333/LER-1979-061, Forwards LER 79-061/03L-0 +
- 05000333/LER-1979-061-03, /03L-0:on 790905,during HPCI Subsys Logic Functional Test,Switch 3 Associated W/Level Instrument 02-3-LIS-72D Did Not Properly Pick Up Follower Relay.Caused by Wiring Error During Installation of New Switch +
- 05000333/LER-1979-062, Forwards LER 79-062/03L-0 +
- 05000333/LER-1979-062-03, /03L-0:on 790905,during Normal Startup,While Conducting HPCI Subsys Logic Functional Test,Plug in Instrument 02-3-LIS-72A Was Found Leaking.No Cause Given. Plug Was Removed,Adjustment Screw Tightened & Plug Replaced +
- 05000333/LER-1979-063, Forwards LER 79-063/03L-0 +
- 05000333/LER-1979-063-03, /03L-0:on 790906,during Normal Startup,Control Rod Worth Minimizer Was Intentionally Bypassed.Caused by Revision in Control Rod Withdrawal Sequence +
- 05000333/LER-1979-064, Forwards LER 79-064/03L-0 +
- 05000333/LER-1979-064-03, /03L:on 790906,during Startup,Motor Failed on Condensate Storage Tank Suction Valve.Replacement Valve Mistakenly Left Closed.Caused by Communications Breakdown. Upon Discovery,Valve Opened & Position Logged Daily +
- 05000333/LER-1979-065, Forwards LER 79-065/03L-0 +
- 05000333/LER-1979-065-03, /03L-0:on 790907,rod Sequence Control Sys Failed, Not Allowing Normal Control Rod Insertion or Withdrawal. Caused by Failed Relay on One Printed Circuit Board. Replacement of Relay Restored Normal Operation of Sys +
- 05000333/LER-1979-066, Forwards LER 79-066/03X-1 +
- 05000333/LER-1979-066-03, /03X-1:on 790907,while Conducting Operations Surveillance Test,Average Power Range Monitor Channels A,D & F Tripped 0.5% Over Tech Spec Requirements.Caused by Operator Error.No Drift of Instrument Setpoint Occurred +
- 05000333/LER-1979-067, Forwards LER 79-067/03L-0 +
- 05000333/LER-1979-067-03, /03L-0:on 790908,required Differential Pressure Was Not Established within Specified Time Requirements of 22-h.Cause Not Given.Operations Personnel Were Counseled in Importance of Time Requirements in Completing Activities +
- 05000333/LER-1979-068, Forwards LER 79-068/03l-0 +
- 05000333/LER-1979-068-03, LER 068/03L-0:on 790908,while Establishing Drywell to Torus Differential Pressure,Torus Water Level Exceeded Max Vent Pipe Submergence Limitation Per Tech Specs.Cause Not Stated. Pump down-initiated to Return Level to Normal +
- 05000333/LER-1979-069, Forwards LER 79-069/03L-0 +
- 05000333/LER-1979-069-03, /03L-0:on 790908,recurrent Failure of Rod Block Monitor B Began.Caused by Failure of Low Power Range Monitor Loose Switch Connector & Sticky Contacts in Rod Info Relays. Replacement of Relay Card Eliminated Failures +
- 05000333/LER-1979-070, Forwards LER 79-070/03L-0 +
- 05000333/LER-1979-070-03, /03L-0:on 790909,during Normal Operation,Improper Inputs Noted at a & C Levels to Rod Block Monitor A.Caused by Failed Integrated Circuit.Circuit Replaced,Instrument Recalibr & Returned to Svc +
- 05000333/LER-1979-071, Forwards LER 79-071/01T-0 +
- 05000333/LER-1979-071-01, /01T-0:on 791004,pipe Stress Reanalysis Revealed That Pipe Support H15-124 on Emergency Svc Water Return Piping Was Inoperable.Cause Not Stated.Mod of H15-124 Was Completed within 7-day Time Frame +
- 05000333/LER-1979-072, Forwards LER 79-072/03L-0 +
- 05000333/LER-1979-072-03, /03L-0:on 790912,root Valves Not Verified in Proper Position.Caused by Temporary Change in Procedures to Verify Proper Position in Accordance W/Plant Administrative Controls.Double Verification Program Initiated +
- 05000333/LER-1979-073, Forwards LER 79-073/03L-0 +
- 05000333/LER-1979-073-03, /03L-0:on 790914,while Conducting Operations Surveillance Test,Emergency Diesel Generator C Tripped on Overspeed During Engine Start Sequence.Caused by Loose Connection in Overspeed Limit Switch.Repair Made +
- 05000333/LER-1979-074, Forwards LER 79-074/01T-0 +
- 05000333/LER-1979-074-01, /01T-0:on 790922,pipe Support Associated W/Svc Water Sys Return Line from Reactor Bldg Cooling Sys Considered Inoperable Per Lifting 790313 Show Cause Order.Mods Completed within seven-day Period +
- 05000333/LER-1979-075, Forwards LER 79-075/03L-0 +
- 05000333/LER-1979-075-03, /03L-0:on 790915,during Normal Operations,Drywell Equipment Drain Sump Flow Integrator Observed Not Operating While Sump Was Pumped Down Due to Blown Fuse in Integrator Current Power Supply.Fuse Replaced & Sys Tested +
- 05000333/LER-1979-076, Forwards LER 79-076/03L-0 +
- 05000333/LER-1979-076-03, /03L-0:on 790925,after Protracted Shutdown of Six Months,Reactor Water Conductivity Indicated Increase from Normal Range of Less than 1 Umho/Cm.Caused by Exhaustion of Condensate Demineralizer & Condenser Tube Leaks +
- 05000333/LER-1979-077, Forwards LER 79-077/04L-0 +
- 05000333/LER-1979-077-04, /04L-0:on 790922,during Normal Operation,Shear Pins for Travelling Water Screens a & C Failed.Shear Pins Replaced & Normal Operation of Travelling Watering Screens Restored +
- 05000333/LER-1979-078, Forwards LER 79-078/03L-0 +
- 05000333/LER-1979-078-03, /03L-0:on 791002,reactor Water Instrument 02-3-LIS-72A Was Found Out of Calibr.Caused by Instrument Drift Due to Unknown Causes.Surveillance Increased to Daily Until Switch Is Replaced or Determined Reliable +
- 05000333/LER-1979-079, Forwards LER 79-079/01T-0 +
- 05000333/LER-1979-079-01, /01T-0:on 791010,pipe Support Associated W/Emergency Svc Water Sys B Was Considered Inoperable Per Tech Specs.Cause Not Stated.Existing Support Was Upgraded +
- 05000333/LER-1979-080, Forwards LER 79-080/01T-0 +
- 05000333/LER-1979-080-01, /01T-0:on 791017,pipe Stress Reanalysis Revealed Pipe Hanger in Fuel Pool Cooling Sys Was Inoperable.Cause Not Stated.Hanger Was Ungraded.Hanger as Modified Is Acceptable.Sys Is Currently Operable +
- 05000333/LER-1979-081, Forwards LER 79-081/01T-0 +
- 05000333/LER-1979-081-01, /01T-0:on 791018,pipe Stress Reanalysis Revealed a Train RHR Svc Water H10-460,PFSK-727 & RHR Sys Pipe Supports Were Inoperable.Cause Not Stated.Mod of Supports Completed & Are Now Acceptable +
- 05000333/LER-1979-082, Forwards LER 79-082/03L-0 +
- 05000333/LER-1979-082-03, /03L-0:on 791005,during Normal Operation,Water Leaked from Lubrication Line on Fire Protection Sys Post Indicator Valve.Necessary to Isolate Portion of Fire Protection Yard Loop to Make Repairs.Cause Unstated +
- 05000333/LER-1979-083, Forwards LER 79-083/03L-0 +
- 05000333/LER-1979-083-03, /03L-0:on 791008,during Normal Operation,Routine Computer Printout of Core Performance Log Indicated That Max Fraction of Limiting Power Density Exceeded 1.000. Reactor Power Immediately Reduced 3% +
- 05000333/LER-1979-084, Forwards LER 79-084/03L-0 +
- 05000333/LER-1979-084-03, /03L-0:on 791009,during Surveillance Test F-ST-5Q, Average Power Range Monitor Channels a & D Tripped at Value Above Tech Spec Max.Caused by Error in Calibr Procedure. Calibr Procedure Revised & Instruments Returned to Svc +
- 05000333/LER-1979-085, Forwards LER 79-085/01T-0 +
- 05000333/LER-1979-085-01, /01T-0:on 791024,while Performing Pipe Stress Reanalysis,Pipe Support Found Inoperable.Cause Not Stated. Support Will Be Upgraded to Accept Increased Loading Resulting from SHOCK-III Analysis +
- 05000333/LER-1979-086, Forwards LER 79-086/01T-0 +
- 05000333/LER-1979-086-01, /01T-0:on 791025,A/E Advised That Six Supports Were Inoperable as Result of Pipe Stress Reanalysis Against Criteria in Lifting 790313 Show Cause Order.Cause Not Stated.Supports Upgraded +
- 05000333/LER-1979-087, Forwards LER 79-087/01T-0 +
- 05000333/LER-1979-087-01, /01T-0:on 791029,A/E Advised That Three Supports Associated W/Rhr Sys B Were Inoperable Per Criteria in Lifting 790313 Show Cause Order.Cause Not Stated. Supports Upgraded & Are Fully Acceptable +
- 05000333/LER-1979-088, Forwards LER 79-088/01T-0 +
- 05000333/LER-1979-088-01, /01T-0:on 791031,A/E Informed Plant Staff That H19-29 & H19-219 Supports in Fuel Pool Cooling Sys Found Inoperable.Analysis Revealed Associated Piping Would Fail During Dbe.Supports Modified +
- 05000333/LER-1979-089, Forwards LER 79-089/01T-0 +
- 05000333/LER-1979-089-01, /01T-0:on 791102,supports H11-8,H66-33 & H76-61 Declared Inoperable & Removed from Sys.Analysis Showed Standby Control & Fire Protection Sys Remained Operable. Caused by Mod to H66-33 in Containment Vent Sys +
- 05000333/LER-1979-090, Forwards LER 79-090/03L-0 +
- 05000333/LER-1979-090-03, /03L-0:on 791001,condensate Storage Suction Valve 23-MOV-17 Was Disabled.Caused by Relocation of Cable During Hanger Mods in HPCI Sys +
- 05000333/LER-1979-091, Forwards LER 79-091/03L-0 +
- 05000333/LER-1979-091-03, /03L-0:on 791020,during Surveillance Test F-ST-2B, RHR Pump C Failed to Start Properly.When Pump C Was Started Pump Would Trip Following Release of Control Switch.Caused by Improper Adjustment of Switches +
- 05000333/LER-1979-092, Forwards LER 79-092/03L-0 +
- 05000333/LER-1979-092-03, /03L-0:on 791013,during Normal Operation,Noted Intermittent Isolation Signal to HPCI Sys Steam Supply Inside Isolation Valve 23-MOV-15,indicating High Ambient Temp.Caused by Loose Lead to HPCI Switch.Lead Tightened +
- 05000333/LER-1979-093, Forwards LER 79-093/03X-1 +
- 05000333/LER-1979-093-03, /03X-1:on 791021,during Normal Operation,Routine Computer Printout Indicated Core Max Fraction of Limiting Power Density Was 1.003 Over Tech Spec Limit.Power Reduced 2%.Control Rod Pattern Adjusted.Cause Not Reported +
- 05000333/LER-1979-094, Forwards LER 79-094/03L-0 +
- 05000333/LER-1979-094-03, /03L-0:on 791025,while Conducting Operations Surveillance Test F-ST-76J14,master Valve on 10-ton Cardox Sys Did Not Fully Open.Caused by Hardening of Valve Packing. Repacking of Valve Corrected Problem +
- 05000333/LER-1979-095, Forwards LER 79-095/03X-1 +
- 05000333/LER-1979-095-03, /03X-1:on 791025,drywell-to-suppression Chamber Differential Pressure Transmitter 27-PT-102B Was Found Out of Tolerance.Caused by Improper Testing Procedure.Procedure Corrected & Proper Calibr Verified +
- 05000333/LER-1979-096, Forwards LER 79-096/03L-0 +
- 05000333/LER-1979-096-03, /03L-0:on 791028,during Normal Operation,Reactor Water Conductivity Exceeded Spec Limit.Power Reduction Initiated.Caused by Leakage from Radwaste Concentrator to Main Condenser.Shell to Tube Side Leak Exists.Study Ongoing +