05000312/LER-1985-027, :on 851214,licensee Discovered That Testing Requirements for Containment Personnel Air Lock Seals Not in Accordance W/Tech Spec 4.4.1.2.5.(c).Caused by Technicians Not Adhering to Procedures.Retest Conducted on 851216
05000312/LER-1985-026, :on 850910,diesel Generators a & B Declared Inoperable.Diesel Generator B Failed to Start.Diesel Generator a Removed from Svc for Troubleshooting.Diesel Generator B Capable of Performing Intended Function
05000312/LER-1987-034, :on 870602,make-up & Two High Pressure Injection Pumps Declared Inoperable.Caused by Improper Classification of Min Flow Recirculation Lines.Design Package to Upgrade Lines Will Be Prepared
05000312/LER-1985-028, :on 851030,control Room Operator Noticed That Auxiliary Pump P-319 Started Automatically.Exact Starting Time Could Not Be Confirmed.Caused by Low Main Feedwater Discharge Pressure
05000312/LER-1987-033, :on 870529,11 Hourly Fire Watches Required by Tech Specs Missed.Caused by Unexpected Demand on Available Manpower Due to Breakdown in Security Computer Sys.Fire Watch Pool Will Be Established
05000312/LER-1987-030, :on 870529,due to Concurrent Work on Radiation Monitors R15049 & R15050,number of Operable Channels to Trip Reactor Bldg Purge Sys Reduced to Zero.Caused by Cognitive Personnel Error.Personnel Trained
05000312/LER-1987-032, :on 870526 & 0614,PORV Isolation Valve Stroke Tested,Rendering Low Temp Overpressure Protection Inoperable,Contrary to Tech Spec 3.2.2.1.Caused by Deficient Procedure.Procedure Will Be Revised
05000312/LER-1986-024, :on 861115,during Fuse Replacement Activity in Bus Inverter S1A,power Momentarily Interrupted & DHR Train a Tripped.Caused by Design Not Allowing for Testability Using Substitute Power Source
05000312/LER-1986-023, :on 861111,inadequate Voltage Supplies Sent to Control Room/Technical Support Center HVAC Under Certain Worst Case Conditions.Caused by Inadequate Engineering Review.Ecn R-0911 Written
05000312/LER-1987-028, :on 870514,diesel Generator B Automatically Started.Caused by Overvoltage Sensed by Emergency Power Supply Sys from Switchyard.Rev 2 to Proposed Tech Spec Amend 147 Submitted to Enhance Controls
05000312/LER-1987-017, :on 870209 & 0320,discrepancies in Local Leak Rate Test (LLRT) Discovered.Caused by Personnel Error.Tech Specs,Updated Sar,Integrated Leak Rate Tests & LLRT Will Be Revised to Reflect Addl Test Requirements
05000312/LER-1985-001, :on 850124,operations Personnel Found Hydrogen Monitor Sys Containment Isolation Valves Open.Caused by Tagging Inconsistency.Cover Panels added.Post-accident Sampling Sys Operation Procedure Revised
05000312/LER-1987-016, :on 870206,discovered That Cable Pulls Made Into safety-related Breaker Cubicle Cabinets for Both Trains of Emergency Electrical Power Left for Several Wks Causing Invalid Seismic Analysis.Caused by Const Error
05000312/LER-1987-014, :on 870204,12 & 13,deficiencies in Inservice Insp Procedures in Violation of Tech Spec 4.2.2.1 Discovered.Caused by Personnel Error.Missed Valve Insp Conducted.Procedure Development Underway
05000312/LER-1986-031, :on 860804,hourly Instead of Continuous Fire Watch Performed.Caused by Operator Error.Fire Protection Coordinator Will Establish Agreed Upon Terminology for Fire Staff to Use When Communicating
05000312/LER-1986-012, :on 860606 & 09,while in Cold Shutdown,Two Snubbers Removed from Operating Decay Heat Sys.Caused by Personnel Error.Snubbers Reinstalled & Planned Work on Snubbers Delayed Until Decay Heat Sys Outage
05000312/LER-1986-013, :on 860630,0706,22 & 23,CR/TSC Essential HVAC Sys a & B Autostarted.Incidents Part of Recurring Problems W/Design,Control & Operation of Cr/Tsc Essential HVAC Sys.W/
05000312/LER-1987-010, :on 870119,electrical Configuration for RCS High Point Valves Found in Noncompliance w/10CFR50,App R. Caused by Inadequate Assessment of Hot Short Effects.Design of Valves Will Be Modified,Per 10CFR50,App R
05000312/LER-1987-005, :on 870113,condensate Storage Tank Level Instrument Used to Determine Auxiliary Feedwater Pump Capacities During Periodic Surveillance Testing Not Adequately Calibr.Cause Not Stated
05000312/LER-1987-004, :on 870114,fire Watch Prematurely Removed in Violation of Tech Specs.Caused by Central Alarm Station Operator Error.Operator Removed from Duties & Assigned as Field Sergeant as Disciplinary Measure
05000312/LER-1987-003, :on 870120,welding Work Performed in Fire Zones 13 & 75 Required Continuous Fire Watch Post,But Only Hourly Fire Watch Performed by Fire Protection Staff.Caused by Personnel Error.Personnel Involved Reprimanded
05000312/LER-1987-001, :on 870117,fire Zone Detection & Suppression Sys Disabled for Grinding Work & Hourly Fire Watch Instituted Instead of Continuous Fire Watches.Caused by Failure to Follow Procedure
05000312/LER-1987-008, :on 870115,discovered Inadequate Sequencing of Diesel Generator High Pressure Pumps During Automatic Loading.Caused by Design Error.Design Control Procedures Implemented
05000312/LER-1987-002, :on 870108,determined That One Area in Existing Plant Electrical Distribution Sys in Noncompliance W/ 10CFR50,App R.Caused by Original Design Error.Instructions Written & Corrective Design Mods Initiated
05000312/LER-1985-009, :on 850530,diesel Generator B Failed to Follow Normal Shutdown Sequence When Stop Button on Safety Features Control Panel Pressed.Caused by 4,160-volt Safety Bus Undervoltage Condition.Time Delay Relay Added
05000312/LER-1986-015, :on 850921,two Trace Solder Pads Dislodged from Component Side of Printed Circuit Board.Dislodged Solder Pads Caused Nonconforming Rept to Be Written.Guidance Will Be Prepared for Technicians
05000312/LER-1987-020, :on 870212,discovered New Locations for Garden & Residence Not Added to Radiological Environ Monitoring Program within 30 Days of Identification.Caused by Personnel Error.Program Updated
05000312/LER-1987-019, :on 870213,fire Watch Not Upgraded When Fire Detection Sys Removed from Svc.Caused by Personnel Error. Special Order 87-15 Issued to Clarify Procedures
05000312/LER-1986-032, :on 861218,hourly Fire Watch for Fire Zone 39 Missed for 1 H While CO2 Sys Inoperable Due to Hole Being Drilled Through Wall for Conduit Installation.Caused by Operations Error.Info Streamlined
05000312/LER-1986-033, :on 861220,local Continuous Sampling Device on Reactor Bldg Not Operating Due to Loss of Power Receptacle. Caused by Overuse of Receptacle.Similar Event Occurred on 861223.Outlets Tagged
05000312/LER-1986-030, :on 861208,decay Heat Sys Isolation Occurred During Transfer of Source Transformer.Caused by Personnel Error & Inadequate Procedure.Personnel Counseled & Procedures Revised
05000312/LER-1986-011, :on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed
05000312/LER-1986-017, :on 860826,discovered That Plant Operated Outside Tech Specs Since 1983.Condition Could Have Caused Failure of Safety Sys Train in Event of Large Break Loca. Proposes Installation of Diesel Generators
05000312/LER-1986-019, :on 860826,auxiliary Bldg Gas Radiation Monitor Declared Inoperable.Noble Gas Grab Sample Not Taken at Required Time.Caused by Assumption That Sample Taken Shortly After Monitor Declared Inoperable
05000312/LER-1987-013-01, :on 870204,discrepancy Discovered Between Routing of Instrumentation Cables 1Y3X210B1 & 1Y3X215A1 & Designated Routing Per Cable Raceway Tracking Sys (Crts).On 870206,five Addl Crts Discrepancies Noted
05000312/LER-1987-021, :on 861121,pressurizer Heater Bundles Damaged Following Heater Breaker Trips.Caused by Energization of Heaters W/O Adequate Water Level & Inadequate Administrative Controls.Root Cause Investigation 86-34 Issued
05000312/LER-1986-006, :on 860414,failure to Implement Fire Protection Deluge Sys 3-yr Flow Test Identified.Caused by Confusion Over Tech Spec Requirements.Spray Sys Reviewed.Procedures Reviewed for mods.Cross-reference List Revised
05000312/LER-1987-007, :on 870117,power Supply Cutoff on High Current to Bailey 885 Auxiliary Relay Module Lamp Occurred.Caused by Power Supply Short Circuit.Engineering Change Notice Written to Reverse Wiring to Lamp Sockets
05000312/LER-1985-001-01, :on 850116,hydrogen Monitor Sys Containment Isolation Valves Open.Caused by Tagging Inconsistency, Inadequate Operating Procedure & Inadequate Panel Design. Procedure Revised & Cover Panel Added
05000312/LER-1986-018, :on 860717,determined That Control Room Did Not Implement Compensatory Fire Protection Measures When Smoke Detectors Disabled for Welding Operations.Caused by Communication Problems.Memo Issued
05000312/LER-1986-008, :on 860429,continuous Fire Watch for Breached Penetration Not Posted.Caused by Personnel Error.Training Program Being Conducted to Ensure All Fire Protection Group Members Trained in Fire Watch Requirements
05000312/LER-1978-016-01, /01T-0:on 781024,operability of a Diesel Generator Lost Due to Failure of Primary Fuses on the Voltage Regulators Control Power Circuit.Fuses Replaced,A Generator Tested Then Returned to Svc
05000312/LER-1985-022, :on 851120,pressurized Sampling Valve HV-21516 Found in Open Position W/Breaker Racked Out.Caused by Lack of Administrative Control.Process Sampling Procedures & Operator Training Upgraded
05000312/LER-1978-015-01, /01T-0:on 781120,failure of 9 Bergen-Patterson Snubbers.Seven of 9 Failures Caused by Abusive Handling During Reinstallation Following 1977 Testing.Other Two Failures Isolated Cases.Failed Units Repaired
05000312/LER-1980-044-01, /01T-0:on 801031,IE Bulletin 79-01B Review Determined That No Qualification Documentation Available for Pressure Switches Utilized in Main Steam Sys.Cause Not Stated.New Sys Will Be Installed or Old Switches Replaced
05000312/LER-1979-022-01, /01T-0:on 791217,Allis Chalmers Informed Util of Potential Problem W/Purge Valves & Recommended Limiting Valve Opening to Max of 60 Degrees Because Excess of 60 Degrees Could Cause Shaft Torsional Rating to Be Extended
05000312/LER-1978-003-04, /04T-0:on 780913,during Steady State Operation, Dissolved Oxygen Concentration Downstream of Confluence of Hadselville & Clay Creek Was Less than Minimum of 5mg/liter Typical of Stagnant Water.Location Is Beyond Util Propert
05000312/LER-1978-012-03, /03L-0:on 780927,header Failed to Discharge During Routine Testing of CO2 Sys.Caused by Defective Microswitch on Solenoid Which Operates Pilot Valve Integral W/Main Isolation Valve Controller
05000312/LER-1978-009-03, /03L-0:on 780913,diesel Driven Fire Pump P-996 Tripped on Overspeed During test.Engine-to-pump Coupling Bolts Were Discovered to Be Sheared,Probably Due to Overtorquing.Bolts Were Replaced,Torque Values Verified
05000312/LER-1978-013-03, /03L-0:on 780925,HPI Loop a Flow Transmitter FT-23807 Found Inoperable During Surveillance Procedure 200.14.Caused by Broken Bellows in Flow Transmitter.Failed Bellows Replaced
05000312/LER-1978-006-03, /03L-0:on 780611,during Normal Operation,Increased Leakage Noticed,Between 1.1-1.7 Gallons/Min.Caused by Leaking Pressure Safety Valves & Block Valve on Electromatic Relief Valve.Valves Replaced or Reworked
05000312/LER-1986-001, :on 860121,diesel Generator G-886B Declared Inoperable Due to Fuel Inlet Pressure Above Limits Specified in Process Stds.Safety Functions Performed.New Spare Parts Ordered for Generator
05000312/LER-1986-004, :on 860215,review of Fire Door Refueling Interval Surveillance Test Results Revealed That Fire Doors Determined to Be Inoperable & Fire Watches Not Posted within 1 H.Caused by Personnel Error.Watches Posted
05000312/LER-1986-003, :on 860314,while Attempting to Perform Calibr on Reactor Bldg Exhaust Monitor R15001 Sample Flow Meter, Containment Purge Went Unmonitored for 50 Minutes.Control Room Operator Counseled
05000312/LER-1985-024, :on 851222,RCS Leakage Calculated to Be Between 15 & 20 Gallons Per Minute.Shutdown Initiated.Caused by Leaking Packing Gland SFV-70001.Gland Disassembled & Inspected.Twelve Rings of Packing Added
05000312/LER-1985-021, :on 851119,emergency Diesel Generator a Automatically Started When Bus 4A Normal Supply Breaker Tripped on Overvoltage Condition.Caused by Technicians Disconnecting Ground Wiring
05000312/LER-1985-019, :on 851002,reactor Trip Occurred & RCS Temp Decreased to Approx 70 F.Caused by Excessive Steam Loads Due to Two Open Relief Valves on Feedwater Heater 4A.HPI Flow Manually Initiated to Maintain Pressure
05000312/LER-1985-020, :on 851007,internal Occurrence Description Rept Indicated That Flow Controllers for Control Room/Technical Support Ctr Essential HVAC Filtration Units Malfunctioning. Caused by Design Error.Correction Made
05000312/LER-1984-016, :on 840425,RCS Pump Seal Return Line Isolation Valve Exceeded Tech Spec Stroke Time Limit.Caused by Weaknesses in Documentation & Surveillances of Equipment. Valve Restroked.Surveillance Procedure Revised
05000312/LER-1985-023, :on 851205,reactor Trip Occurred on High RCS Pressure.Caused by Underfeeding of Main Feedwater Sys During Flow Scaling Procedure.Integrated Control Sys Modules Examined & Refurbished
05000312/LER-1984-020, :on 840703,tube Leak Experienced in once- Through Steam Generator B.During Cooldown,Unplanned Reactor Trip Occurred on Low RCS Pressure.Caused by Through Wall Defect at 15th Tube Support Plate
05000312/LER-1984-019, :on 840608,Tech Specs Violated When Diesel Generators No Longer in Ambient State Prior to Tests Being Performed.Caused by Rev to Procedures EM.177A & B.Maint Startup Deleted from Procedures
05000312/LER-1985-015, :on 850716,electrician Working in Switchgear Area Accidently Tripped Nuclear Svcs Bus 4B2,causing Emergency Diesel Generator B to Automatically Start.Caused by Loose Terminal Board Connections
05000312/LER-1985-017, :on 850906,leakage Flow Path Reported in Filtration Unit of Auxiliary Bldg a Ventilation Unit.Caused by Omission of Seal Plate During Mfg.Steel Plate Welded Over Bypass Opening
05000312/LER-1979-008-03, /03L-0:on 790719,while Performing Monthly Pump Surveillance on B Decay Heat Removal Pump,Leakage in Excess of 0.63 Gallons/Minute Allowable Per Tech Spec 4.5.3.1 Observed at Pump Seal.Seal Replaced & Sys Adequately Tested
05000312/LER-1985-005, :on 850420,valve BWS-041 in Boration Path Closed During Fuel Movement.Caused by Procedural Error. Procedure B.8 Revised to Require Clearance Tag to Be Placed on BWS-041 After Opening During Refueling
05000312/LER-1985-008, :on 850521,portion of Surveillance Procedure Sp 301.03k Re Accessible Cable Tray Fire Barriers Discovered Not Performed within Specified Interval.Caused by Incorrect Date Listed for Previous Surveillance
05000312/LER-1980-013-03, /03L-0:on 800218,following Biannual Insp of Diesel Generator B,Problem W/Dc Air Start Sys Noted.Probably Caused by Natural end-of-life for Flexible Synthetic Rubber Line. Line Replaced
05000312/LER-1980-014-03, /03L-0:on 800219,while Moving Aris Calibr Block, Sling Failed & 3,000 Lb Block Fell Into Flange Transfer Canal.Caused by Inadequate Sling Utilized for Lift.Speed Change Problem Corrected
05000312/LER-1979-024-03, /03L-0:on 791217,during Normal Operation,Hpi Pump B Taken Out of Svc.On 800109,discovered That Cooling Water Supply Valves Were Isolated.Caused by Removal of HPI Pump B from Svc.Pump B Returned to Svc & Placed on Standby
05000312/LER-1982-014-03, /03L-0:on 820619,pressurizer Liquid Sample Valve, SFV-70001,opened Properly But Failed to Close Properly on Command.Caused by Ax Relay Not Responding to Close Command. Relay Replaced
05000312/LER-1982-013-04, /04T-0:on 820607,during Chlorination of Nuclear Svc Spray Pond,Spray Pond Filters Went Into Backwash Mode. Cause Not Stated.Several Fish in Discharge Stream Killed Due to Excessive Chlorine.Chlorine Injection Point to Be Mov
05000312/LER-1982-012-03, /03L-0:on 820505,during Cold Shutdown,A Decay Heat Pump Inboard Bearing Found Leaking Oil.Cause of Leak Undetermined.Probable Cause Due to Partial Seal Failure.Leak Will Be Repaired
05000312/LER-1982-010-01, /01T-1:on 820419,insp of B once-through Steam Generator Auxiliary Feedwater Header Ring & a Ring on 820420 Revealed Deformations.Mod Work to Correct Problem Partially Scheduled.Old Header Will Be Stabilized
05000312/LER-1982-011-03, /03L-0:on 820415,check Valve CBS-022 on B Tank Supply to B Pump Found Stuck Closed.Caused by Chemical Deposit Buildup.Check Valves Cleaned,Reground & Returned to Svc
05000312/LER-1982-008-04, /04T-0:on 820121,plant Effluent Ph Found to Be High (8.6-8.7) for Approx 5 Minutes.Caused by Instrument Error.Rh & Delta TC Probes Replaced
05000312/LER-1982-005-03, /03L-0:on 820211,B Diesel Generator Found Inoperable.Caused by Output Breaker lock-out Due to Reverse Power Trip.Relays Marked to Improve Identification of Flag Targets,Personnel Trained & lock-out Alarm Moved
05000312/LER-1982-003-01, /01T-0:on 820301,B HPI Pump Found to Be Inoperable Due to Leaving Dc Charging Motion for Closing Spring in Unenergized State.Probably Caused by Personnel Error or Improper Procedure.Addl Training Provided
05000312/LER-1982-006-04, /04T-0:on 820305,during Review of Plant Effluent Records,Discovered That Ph Limit Was Exceeded on 820219. Caused by Sample Sys Configuration for Regenerate Hold Up Tank Discharging Into Plant Waste Stream.Sys Modified
05000312/LER-1982-001-01, /01T-0:on 820130,both Doors on Airlock Opened Simultaneously Resulting in Loss of Containment Integrity. Caused by Personnel Error & Failure of Inner Door Mechanism to Latch Properly
05000312/LER-1982-004-03, /03L-0:on 820209,reactor Protection Sys Channel C Pressure Transmitter Read 15 Psi High.Caused by Calibr of Transmitter During Artificial Cooling of Ambient Temp by Emergency Cooler.Input Buffer Amp Bias Changed
05000312/LER-1982-007-04, /04T-0:on 820305,monthly Review of Plant Effluent Records Revealed Plant Effuent Chlorine Limit Exceeded for Period of 2.5-hr on 820217.Caused by Analyst Failing to Take Sample at Site Boundary.Analysis Reinstructed
05000312/LER-1982-002-03, /03L-0:on 820130,snubbers 1SW-21007-7 & 1SW-23823-13A Failed Visual Insps.Caused by Low Fuel Level. Snubber 1SW-21007-7 Rebuilt & Passed.Snubber 1SW-23823-13A Failed Until Bechtel Developed New Criteria
05000312/LER-1981-058-03, /03L-0:on 811221,repts Required by Tech Specs 4.2.8 Re Cumulative Reactor Utilization Factor Had Not Been Written Since Jul 1980.Generation Engineering Is Writing Rept
05000312/LER-1981-056-01, /01T-0:on 811211,instrument Technician Tested Instrumentation on Reactor Protective Sys Channel When Trip Sys Not Set Up to Retain Min Degree of Redundancy.Caused by Failure to Follow Procedures.Technicians Reinstructed
05000312/LER-1981-057-03, /03L-0:on 811208,reactor Protection Channel C Found Indicating 15 Psi Higher than Channels A,B & D. Apparently Caused by Transmitter Failure.Investigation Continuing & Channel C Bypassed
05000312/LER-1981-055-03, /03L-0:on 811118,reactor Protection Sys Pressure Transmitters in B & C Channels Found to Have Drifted.Cause Not Stated.Setback of 20 Psi Implemented & Transmitters Rezeroed
05000312/LER-1981-054-03, /03L-0:on 811024,while Performing RPS Channel C Test I-108C,breaker Trip Test Not Done.Caused by Technician Failure to Perform Test as Required.Trip Test Performed on 811026
05000312/LER-1981-052-03, /03L-0:on 811005,nuclear Svc Raw Water Pump B (P-472B)tripped W/O Alarms or Target Drops.Cause Not Found. Pump Restarted & Quarterly Surveillance Test Run W/O Problems
05000312/LER-1981-053-03, /03L-0:on 811022,safety Features Valve SFV-20577 Failed to Stroke Fully Closed.Valve Cycled Manually Then Cycled Electrically W/No Difficulty.Motor Current Found Acceptable.Valve Will Be Tested Again in Cold Shutdown
05000312/LER-1981-049-03, /03L-0:on 810929,while Performing Surveillance Test,Safety Features Valve SFV-22025 Failed to Close.Caused by Lack of pre-set Compression on Spring Pack in Limitorque Operation.New Spring Pack Installed in Valve
05000312/LER-1981-051-03, /03L-0:on 810930,while Performing Surveillance Test,Safety Features Valve SFV-46014 Found to Have Excessive Stroke Time.Caused by Tightness of Valve Packing. Reajusted Packing & Lubricated Stem
05000312/LER-1981-016-03, Degradation of Lube Oil Cooling Capacity on HPI Pump B Found.Caused by Excessive Corrosion of Cooler Heads.Coolers Cleaned & One Epoxy Coated.After Satisfactory Performance Two Others Coated
05000312/LER-1981-050-03, /03L-0:on 810930,during Surveillance Test,Valve Failed to Stroke Closed.Caused by Water & Rust Preventing Solenoid from Proper Operation.Valve Cleaned & Replaced.Addl Maint Efforts Will Address Moisture Collection Problem
05000312/LER-1981-041-03, /03L-0:on 810916,found That Pipe Supports Could Be Overstressed by Thermal & Seismic Loads.Caused by Design Deficiency.Pipe Supports Redesigned & Modified to Conform to ASME Code Allowables
05000312/LER-1981-047-01, /01E-0:on 810930,bus a Emergency Pressurizer Heater Bank 3 Operated Intermittently Due to Loose Wire. Caused by Misoriented Screw Washer.Washer re-oriented & Screw Tightened
05000312/LER-1981-048-04, /04T-0:on 811003,monthly Record Review Revealed Violation on 4 Days of Ph Limit in Sept.Three Violations Caused by Instrument Calibr.Corrective Action in Followup Rept
05000312/LER-1981-044-03, /03L-0:on 810825,during once-through Steam Generator Sampling Operation W/Plant Shut Down,Abnormal Level of Radioactivity Found.Caused by Leak in Nitrogen Supply Sys.Spool Piece Replaced by Blank Flanges
05000312/LER-1981-046-03, /03L-0:between 810910 & 19,snubber Surveillance Procedure Revealed One Failed Snubber & Five Snubbers Low in Hydraulic Fluid.Caused by Clevis Pin & Pipe Line Clamp Nuts Missing in Former & Worn Valve Block Body in Others
05000312/LER-1981-042-04, /04T-0:on 810903,during Monthly Review of Plant Effluent Records,Found That Ph Limit Was Violated on Four Days in Aug.Plant Effluent Sys Allows Several Minor Violations Per Month.Followup Rept Will Be Submitted
05000312/LER-1981-043-03, /03L-0:on 810818,performance of Surveillance Procedure Revealed 26 Discrepant Pipe Penetration Fire Stops.Caused by Insufficient Grouting,Supports & Silicone Foam.Fire Watch Will Continue Pending Repairs by 811215
05000312/LER-1981-040-04, /04T-0:on 810831,review of Water Quality Records Revealed That Limit on Total Dissolved Solids Exceeded on 810709.Caused by Operator Inattention to Integrated Flow Rate/Dissolved Solids Indication.Operator Will Review Rept
05000312/LER-1981-035-03, /03L-1:on 810625 Diesel Generator a Synchronization Test Revealed Unstable Operation of Diesel Generator G886A.Caused by Slow Oil Leak in Governor.Oil Added.Generator to Be Replaced
05000312/LER-1981-036-04, /04T-0:on 810713,monthly Review of Plant Effluent Records Revealed 12 Instances of Plant Effluent Ph Exceeding Allowable Levels.Caused by Ongoing Work on Instrumentation, Poor Sampling Techniques & Leaking Valves
05000312/LER-1982-029-03, /03L-0:on 821026,QA Dept Reported That Portion of Auxiliary Feedwater Start Circuit Was Not Being Tested Per Requirements.Caused by Transposed Requirements in Tech Specs.Tech Specs Will Be Amended
05000312/LER-1982-023-03, /03L-0:on 820909,weekly Nitrogen Sys Surveillance Showed Xe-133 Activity in Auxiliary Bldg Nitrogen Header. Cause Undetermined.Investigation Will Be Conducted.Followup Rept on Cause & Corrective Actions Will Be Provided
05000312/LER-1982-027-03, /03L-0:on 821012,weekly Surveillance of Nitrogen Sys Revealed Presence of Contamination in Form of Xe-133. Cause Undetermined.Sys Purged & Activities Reduced to Below Detectable Levels.Investigation Underway.Rept Will Follow
05000312/LER-1982-028-99, /99X-0:on 820922,small Pieces of Matl Resembling Paint Chips Observed During Flow Control Valve Repair in Auxiliary Bldg Fire Protection Sys.Probably Caused by Detached Liner Matl.Piping to Be Inspected & Repaired
05000312/LER-1983-025-03, /03L-0:on 830601,during Records Review,Effluent Sample on Release Erdf 83-56 Discovered Not Performed. Caused by Operator Failing to Notify chem-rad Officer at Onset of Release.Procedure Revised
05000312/LER-1983-022-03, /03L-0:on 830507,cooling Water to Reactor Bldg Emergency Cooling Unit a 500c Motor Found to Be Drawing Locked Rotor Current Preventing Valve from Stroking.Female Control Disconnect Switch Found Spread Apart
05000312/LER-1983-016-03, /03L-0:on 830331,during Surveillance Testing on snubbers,10 Snubbers Mfg by Grinnell & Bergen-Patterson Failed Acceptance Criteria.Caused by Defective Seals,Body Corrosion & Water in Fluid.Valves Rebuilt
05000312/LER-1981-045-03, /03L-0:on 810827,during Plant Shutdown,Decay Heat Pump B Was Found Leaking.Cause Not Stated.Shaft Seals Will Be Replaced Prior to Next Reactor Startup
05000312/LER-1981-039-03, /03L-0:on 810807,switchyard Voltage Decreased to 206 Kv W/Reactor Shut Down.Caused by High Local Electrical Demand.Direct Indication of Voltage & Alarm Will Be Installed in Control Room.Updated Analysis Forthcoming
05000312/LER-1981-038-03, /03L-0:on 810713,fire Door Surveillance Procedure Revealed 37 Apparently Unacceptable Fire Doors.Cause Not Stated.Obstruction Removed from one,13 Repaired & 23 Found Acceptable.Fire Watches to Be Established
05000312/LER-1981-037-03, /03L-0:on 810707,during Surveillance Test, Isolation Valve Failed to Close within Tech Spec Limit. Apparently Caused by Foreign Matl in Air Discharge Port.Port Cleaned & Valve Operated Properly
05000312/LER-1981-034-03, /03L-0:on 810619,switchyard Voltage Decreased W/ Reactor Shutdown.Caused by High Local Electrical Demand. Direct Indication of Switchyard Voltage & Alarm to Be Installed in Control Room & Safety Analysis to Be Updated
05000312/LER-1981-033-03, /03L-0:on 810611,investigation of Diesel Trouble Alarm Revealed Open Relay Which Would Have Prevented Operation of Diesel Generator A.Relay Reset.Alarm to Be Modified
05000312/LER-1981-032-03, /03L-0:on 810527,snubber W/Nearly Empty Accumulator on Letdown Cooler Discovered During Sp at Cold Shutdown.Caused by Leaking Valve Block Seal.Snubber Removed, Adjusted & Reinstalled & Seal Replaced
05000312/LER-1981-030-04, /04T-0:on 810602,plant Effluent Ph Exceeded Limit. Caused by Fluctuating Ph of Water Supply.Negotiations Underway to Set Ph Limits Based on Max Observed Canal Ph in Previous 30 Days
05000312/LER-1981-031-03, /03L-0:on 810520,fire Barrier Failures Discovered During Sp at Cold Shutdown.Caused by Personnel Failure to Return Barriers to Satisfactory Condition Following Breach. Firewatch Established for Compromised Barriers
05000312/LER-1981-028-03, /03L-0:on 810506,inaccessible Snubber Found Low on Fluid During Safety Sys Hydraulic Snubbers Surveillance Inservice Test.Caused by Faulty Accumulator Internals or Valve Body.Internals & Body Removed,Reworked & Reinstalled
05000312/LER-1981-027-03, /03L-0:on 810502,RBS Pump Breaker 3A09 Tripped When Attempting Start from Control Room.Cause Unknown.Trip Reset
05000312/LER-1981-025-03, /03T-0:on 810420 & 0506,pressurizer Liquid Sample Valve Failed to Operate.Caused by Stripped Drive Sleeve Bevel Gear.Operator Removed & Replaced.Valve Tested & Stroked
05000312/LER-1981-024-03, /03T-0:on 810419,approx 4,000 Gallons of Reactor Coolant Was Inadvertently Transferred from RCS to Reactor Bldg Emergency Pump.Caused by Personnel Error.Rcs Was Refilled & Revented
05000312/LER-1981-021-03, /03T-0:on 810402,BWST Valve SFV-25003 Failed to Open Electrically Due to Rounded Off Dogs on Worm Shaft Clutch Gear.Caused by Manual Operation of Valve.Worm Components Replaced.Design Changes Are Being Processed
05000312/LER-1981-020-04, /04T-0:on 810326,liquid Effluent Ph Exceeded 8.5 Tech Spec Limit for Approx 15 Minutes.Caused by Retention Basin Being Released Prior to Increasing Dilution Water Flow.Effluent Ph Instrumentation Calibr & Monitored
05000312/LER-1981-017-03, /03L-0:on 810316,unistrut Cable Tray Support H-80 Found 3 Ft Out of Position & Not Fastened W/Anchor Bolts. Probably Caused by Relocation to Facilitate Movement of Equipment.Support Relocated & Fastened
05000312/LER-1981-019-03, /03L-0:on 810316,obstruction in Suction of Atmosphere Radiation Monitor R15001B Discovered.Caused by Plastic Cap from Bottle of Industrial Leak Detection Fluid. Bottle Cap Removed from Sample Line Suction
05000312/LER-1981-013-03, /03L-0:on 810223,inner Door of Reactor Bldg Personnel Hatch Failed to Close Completely.Caused by Misinterpretation of Tech Specs.Written Interpretation to Be Distributed
05000312/LER-1980-049-03, /03L-0:on 801219,during Performance of Sp 206.03B, B Diesel Generator Failed to Start.Cause Not Stated.Unit Declared Operable 801222 After Passing Applicable Surveillance Test
05000312/LER-1980-046-03, /03L-0:on 801104 & 1128,overspeed Trip Lever on Turbine for Automatic Feedwater Pump P-318 Was Found in Apparent Tripped Condition.Cause Could Not Be Determined. Daily Visual Checks Initiated
05000312/LER-1981-005-04, /04L-0:on 810125,plant Liquid Effluent Ph Exceeded 8.5 Limit Established by Tech Spec App B,Section 2.4.Caused by Slightly out-of-tolerance Setpoint.Diversion Setpoint Was Reset.Alarm Setpoint Will Be Lowered
05000312/LER-1980-047-01, /01T-0:on 801222,IE Bulletin 79-01B Review Found Lack of Qualification Documentation for Flow Transmitter Utilized to Establish Dilution Flow to Prevent Boron Precipitation Following Loca.Cause Not Stated
05000312/LER-1981-014-03, /03L-0:on 810306,unacceptable Leak Rate Obtained During Local Component Leak Rate Test on Reactor Bldg Penetration 34.Caused by Motor Pinion Gear Key Backed Out of Keyway & Sheared Off.Set Screw Added to Operator Key
05000312/LER-1981-015-04, /04T-0:on 810214,review of Feb 1981 Effluent Charts Showed Tech Spec for Plant Effluent Ph Was Exceeded. Caused by Effluent Diversion Setpoint Being Slightly out-of-tolerance.Setpoints Lowered
05000312/LER-1981-010-01, /01T-0:on 810225,A/E,performing Analysis for IE Bulletin 79-14,informed of Potential Piping Stress Problem on Decay Heat Removal Sys A,Line 26120-10.Caused Not Stated. Sys Use Restricted to Temps & Pressures Below Design Lim
05000312/LER-1981-009-03, /03L-0:on 810217,during Testing of Mod to Diesel Generator Room Vent Fans,Breaker 52-3B17 Tripped Free. Cause Undetermined.Breaker Replaced W/Class 1 Breaker & Returned to Svc
05000312/LER-1981-008-01, /01T-0:on 810218,breaker Did Not Trip During Preventative Maint on Breaker 3A09,RBS Pump P-291A.Caused by Loose Wire on Pigtail of Trip Coil Due to Use of 14-16 Awg Lug on 20 Awg Wire.All Lugs on Pigtail Leads to Be Replaced
05000312/LER-1981-006-03, /03L-0:on 810206,one of Two Pressurizer Code Safety valves,PSV-21506,lifted Above Setpoint Level Per Tech Specs During Bench Test.Possibly Caused by Seat Leakage During Test & Limited Capacity of Bench Tester
05000312/LER-1981-023-04, /04T-0:on 810408,plant Liquid Effluent Ph Was Found to Have Dropped Below Tech Spec Limit.Probably Caused by Stagnant,Low Ph Water in Drain Line Due to Gravity Drain of Basin
05000312/LER-1981-022-03, /03L-0:on 810416,safety Sys Hydraulic Snubbers SS-16,SS-17 & 71(MS-20522-SW2) Were Found Low on Fluid Level.Cause Not Stated.Assemblies Reworked
05000312/LER-1981-029-03, /03L-0:on 810513,partially Failed Pipe Hanger on Main Steam Line a Was Discovered.Weld Holding Clevis to Attachment Plate on Hanger Was Partially Pulled Apart.Cause Unknown.Hangers to Be Reinspected When Operation Resumes
05000312/LER-1981-026-01, /01T-0:on 810516,alert Indication Shown on Condenser Air Ejector Radiation Monitor Followed by High Alarm.Caused by Tube Leakage Due to through-wall Crack.Tubes Stabilized & Plugged
05000312/LER-1981-018-04, /04T-0:on 810317,chlorine Concentration Exceeded Tech Specs Limit.Caused by Lower Flow Rate in One of Two Plant Sewage Sys Sump Pumps,Allowing Excess Hypochlorite Injection.Injection Rate Has Been Decreased
05000312/LER-1981-016-01, /01T-0:on 810312,during Maint Insp of Lube Oil Cooler for HPI Pump B Discovered Substantial Corrosion Products Causing Degradation in Cooling Capacity.Caused by Excessive Corrosion of Cooler Heads
05000312/LER-1980-039-01, /01T-0:on 800813,while Proceeding to Cold Shutdown,Reactor Protection Sys Was Placed in Shutdown Bypass Mode & Nuclear Overpower Trip Setpoint Not Reduced to Less than 5% of Rated Power.Caused by Personnel Error
05000312/LER-1980-036-41, /041-0:on 800710,review of Jul 1980 Effluent Monitoring Charts Indicated Plant Liquid Effluent Ph in Excess of 8.5 Tech Spec Limit.Cause Unknown.Automatic Diversion Setpoint Lowered to Minimize Recurrence
05000312/LER-1980-038-41, /041-0:on 800729,review of Plant Effluent Data for Jul 1980 Indicated That on 800629 & 30,sample Indicated 0.25 & 0.3 Mg/Liter Chlorine.Second Followup Sample Not Obtained.Caused by Personnel Error.Personnel Reinstructed
05000312/LER-1980-037-04, /04L-0:on 800728,monthly Review of Plant Effluent Recorder Charts Indicated Total Dissolved Solids Discharged Exceeded Tech Specs.Caused by Higher than Normal Flow Rate & High Conductivity
05000312/LER-1980-010-03, /03L-0:on 800213,during Refueling,Polar Crane Moved Over Upender When Upenders Contained New & Irradiated Fuel Assemblies.Caused by Personnel Ignorance of Restrictions in Core Monitor.Handling & Disposal Revised
05000312/LER-1980-009-03, /03L-0:on 800207,during Function Tests of Relays in 4,160-volt Feeder Breakers,Contacts Sfax (Sfbx) Found Not Wired.Caused by Discrepancy Between Design & Internal Switchgear Wiring Diagrams.No Changes Necessary
05000312/LER-1981-012-01, /01T-0:on 810303,as-found Setpoints for High Reactor Bldg Pressure Trip Were Noted Exceeding Tech Spec. Caused by Instrument Drift.Switches Reset & Setpoints Revised
05000312/LER-1981-011-03, /03L-0:on 810217,reactor Bldg Sump/Decay Heat Removal Sys Flow Path Obstructed.Caused by Installation of Blank Test Flanges on Suction Lines.Flanges Removed & Test Procedure Revised
05000312/LER-1981-003-03, /03L-0:on 810203,during Reactor Bldg Spray Sys Loop B Sfas Test,Reactor Bldg Spray Pump B Started Late. Caused by Incorrect Setting on Model 62B Agastat Timer. Timer Reset
05000312/LER-1981-004-03, /03L-0:on 810202,component Cooling Water Isolation Valve Failed to Close During Surveillance Procedure 205.07C, Isolation Valve Surveillance test,SFV-46204.Caused by Water in Air Line of Valve Actuator.Water Drained
05000312/LER-1981-007-01, /01T-0:on 810210,info Received That Certain safety-related Instrument Errors Exceed Those Assumed in FSAR Analysis.Possibly Caused by String Error Discrepancies. Applicability of Methodology Used in Rept Being Reviewed
05000312/LER-1980-050-04, /04T-0:on 810105,environ TLD Monitor Along Perimeter Fence Indicated Dose Rates Above Tech Spec.Caused by Close Proximity to Drum Storage Area.Bulk Radwaste Storage Bldg Will Be Constructed
05000312/LER-1980-042-04, /04T-0:on 801009,six of 19 Environ TLD Monitors Indicated Dose Rates Above Tech Specs,App B,Requirements. Caused by TLD Being Passed Through X-ray Prior to Being Brought Onsite.Tld No Longer Passed Through Machines
05000312/LER-1980-041-03, /03L-0:on 800823,diesel Generator B Did Not Achieve Rated Voltage of 4,160 Volts.Caused by Voltage Regulator.Unit Was Reset & Successfully Tested
05000312/LER-1980-040-03, /03L-0:on 800812,reactor Protection Sys Channel D Trip Signal Was Received.Caused by Amplifier Failure in Electronic Portion of Transmitter.Transmitter Replaced, Calibr,Leak Tested & Returned to Svc
05000312/LER-1980-035-41, /041-0:on 800703,plant Effluent Ph Momentarily Exceeded Acceptable Operating Band.Caused by Small Vol of off-std Water Being Trapped in Waste or Dilution Water Conduits.Automatic Diversion Sys Realigns Water Offsite
05000312/LER-1980-034-04, /04L-0:on 800602,review of June 1980 Effluent Monitoring Charts Indicated Liquid Effluent Ph Exceeded Tech Specs.Caused by Recurring Problem
05000312/LER-1980-033-04, /04T-0:on 800709,two Environ TLD Monitors Indicated Dose Rates Above Tech Spec App B Rept Level for Second Quarter 1980.Apparently Caused by Air Scattered Albedo & Location of Two Radioactive Matl Storage Trailers
05000312/LER-1980-031-03, /03L-0:on 800703,during Review of IE Bulletin 79-14 Work,Found Stress Analysis for Nonconforming Pipe Support Was Overlooked.Caused by Design Documentation & Const Drawings Not Conforming to Seismic Analysis
05000312/LER-1980-032-03, /03L-0:on 800712,during Routine Surveillance Test on Auxiliary Feedwater pump,P-318,pump Failed to Start from Control Room.Cause Undetermined.After Successfully Starting for Five Days,Pump Returned to Svc
05000312/LER-1980-026-01, /01T-0:on 800508,ATOG Analysis Showed Calculation of Offsite Dose Following once-through Steam Generator Tube Rupture May Be Higher than FSAR Figure.Operator Guidelines & Revised FSAR Analysis Will Be Developed
05000312/LER-1980-027-03, /03L-0:on 800508,during Periodic Insp of Accessible Safety Sys Hydraulic Snubbers,Discovered That Snubber Was Inoperable.Caused by Low Oil Level.No Seal Leakage Was Evident.Unit Refilled & Declared Operable
05000312/LER-1980-017-03, /03L-0:on 800322,after Manually Opening SFV-25003 Several Turns to Increase Level in Pressurizer,Valve Failed to Close Electrically.Caused by Excessive Wear to Shaft Clutch & Clutch Gear.Defective Parts Replaced
05000312/LER-1977-012-03, /03X-1:on 771001,borated Water Storage Tank Isolation Valve Motor Operator Failed.Caused by Manual Operation.Damaged Parts Replaced & Operator Returned to Svc. Automatic Cycling Restrictions Imposed.Updates RO-77-12
05000312/LER-1978-011-01, /01T-0:on 780914,required Continual Fire Watch Erroneously Terminated.Caused by Shift Personnel Misunderstanding.Personnel Instructed
05000312/LER-1977-016-03, /03X-1:on 780105,fluid Leakage Discovered on 781129 Traced to Failing Polyurethene O-ring.All Bergen- Patterson Snubber Polyurethane Seals Were Replaced w/ethylene-propylene Seals.Apparently One Seal Was Missed
05000312/LER-1980-030-03, /03L-0:on 800623,while Performing I-108C,reactor Protection Sys Channel C Test,Overpower Bistable Voltage Setting Was Found Drifted Out of Spec.Caused by Malfunctioning of Semiconductor Voltage Regulator
05000312/LER-1978-005-01, /01T-0:on 780509,four Main Steam Code Safety Valves Found Improperly Set in Nonconservative Direction. Caused by Procedural Inadequacy.Maint Procedure Included Hydroset Curve for One Type Orifice.Procedure Revised
05000312/LER-1980-029-04, /04T-0:on 800519,May 1980 Effluent Monitoring Charts Indictaed Effluent Ph Exceeded 8.5 Tech Spec Limit. Caused by Ph Fluctuations in Dilution Water,Common Phenomenon in Summer Months
05000312/LER-1980-028-01, /01T-0:on 800609,review of Safety Features Actuation Sys Revealed That If One Inverter Was Out of Svc, Failure of Remaining Inverter Would Disable Sys.Operational Restrictions Placed on Inverter Operability
05000312/LER-1978-002-04, /04T-0:on 780414,hypochlorite Spilled & Flushed Into Drain Sys During Hypochlorite Chemical Tank Filling, Causing Chlorine Levels to Exceed Limits.Fill Line Will Be Capped Prior to Removal & Spills Will Not Be Flushed
05000312/LER-1978-001-04, /04T-0:on 780109,plant Liquid Effluent Ph Levels Exceeded Tech Spec 8.5 Limit.Ph Sensor Setpoint Raised in Summer to Folson South Canal Ph Level & Not Reset When Ph Level Dropped,Eliminating Automatic Diversion Feature
05000312/LER-1978-002-03, /03L-0:on 780228,safety Sys Hydraulic Snubbers 25 & 26 Found Low on Fluid During Visual Insp.No Leakage Found. Cause Not Determined.Snubbers Refilled & Surveillance Interval Reduced to Six Months
05000312/LER-1978-007-03, /03L-0:on 780622,frequent Makeup Tank Level Changes Observed.Caused by Excessive Leakage from B Decay Heat Removal Sys Pump Seal.Pump Valved Out & Sys a Continued Operation.Leaking Seal Replaced
05000312/LER-1980-019-03, /03L-0:on 800406,during Performance of Sp 203.01A, Sfas Digital Channel 1A Refueling Test Breaker for a Nsrw Pump P-472A Did Not Close.Caused by Accumulation of Old Lubricant & Dirt on Closing Linkage.Linkage Cleaned
05000312/LER-1980-024-03, /03L-0:on 800409,during Performance Test,A Generator Failed to Meet Time Criteria to Reach Full Voltage.Caused by Uncoupled Governor Accumulator Booster Pump.New Coupling Fabricated & Installed
05000312/LER-1980-022-03, /03L-0:on 800406,refueling Test Revealed Valve Sfv 53603 Returned to Open Position After Signal Reset.Caused by Sticking Blpb Open Contacts.Blpb Replaced & Valve Successfully Tested
05000312/LER-1980-023-01, /01T-0:on 800414,vendor Notified Util That Representation for Specific Valves Will Not Be Provided Re Reliability & Operation for Other than Saturated Steam Svc. Cause Not Stated.Test Program Will Be Conducted
05000312/LER-1980-021-04, /04T-0: on 800318,review of Previous Month Plant Effluent Records Indicated That Effluent Ph Exceeded 8.5 for Approx 3-h.Caused by Canal Pumping Station Being Out of Svc for Approx Two Months
05000312/LER-1980-018-03, /03L-0:on 800324,pressurizer Gas Sample Valve, SFV-72502 Failed to Close.Caused by Wire Separation in Valve Control Circuitry.Wire Reconnected to Terminal Lug
05000312/LER-1980-015-01, /01T-0:on 800312,during Visual Insp of Cycle 3 Discharge Fuel,Approx 4 Inches of Cladding Discovered Missing from Fuel Assembly 1C47.Caused by Cladding Defect on One Pin.Insignificant Amounts of Fuel Dispersed
05000312/LER-1980-016-03, /03L-0:on 800310,while Performing IE Bulletin 79-14 Requirements,Seismic Analysis of Supports 1S-50052-1A, 1S-50062-1A & 1S-23626-1 Indicated Seismic Stress Would Exceed Allowable Limit.Supports Modified
05000312/LER-1980-011-03, /03L-0:on 800201,B&W Inservice Insp of Steam Generators Found Three Defective Tubes in First Sampling. Caused by Normal Wear of Generator Tubes.Addl Insp Found No Other Defective Tubes.Three Tubes Plugged
05000312/LER-1979-002-03, /03L-0:on 790205,redundant Unit A-500C Failed to Start,During Test of Reactor Bldg Emergency Cooler.Caused by Improperly Set Overcurrent Relay.Relay Reset, & Unit Retested & Declared Operable
05000312/LER-1980-007-03, /03L-0:on 800125,refueling Cycle Hydraulic Snubber Testing Program Revealed Seven Failed Units.Caused by Broken Springs,Worn Poppets & Seats & Worn O Rings.Defective Parts Replaced & Retested
05000312/LER-1980-005-03, /03L-0:on 800117,w/reactor in Cold Shutdown for Refueling Outage,Excessive Leakage Observed from Outboard Seal of Decay Heat Removal Pump A,P-261A.Seal Replaced,Sys Tested & Declared Operable
05000312/LER-1980-004-03, /03L-0:on 800112,evaluation of Seven Consecutive RCS Leakrates Indicated Leak Rates in Excess of 1 Gallon Per Minute Resulting in Shutdown of Reactor.Probably Caused by Packing Leak in Pressurizer Spray Valve PV-21509
05000312/LER-1980-006-01, /01T-0:on 800204,lab Results of Failed Stainless Steel Stud from Anchor Valve Co Valve Indicated Potential Problem Re Premature Stud Failure.Caused by Improper Temp for Heat Treating During Mfg.More Testing in Progress
05000312/LER-1980-003-03, /03L-0:on 800109,while Out of Svc for Fire Protection Mods,Hpi Pump B Was Restored to Standby.Makeup Pump Was Realigned to Normal.Caused by Operator Error. Standing Order Issued
05000312/LER-1980-008-03, /03L-0:on 800203,during Routine Tour of Reactor Bldg,U Bolt Bracket Found Missing on Pipe Support 1-G-26085-1.Probably Caused by Removal During Some Past Maint Evolution or During Const
05000312/LER-1979-017-03, /03L-0:on 791109,during Routine Operation,Diesel Generator a Failed to Start from Control Room.Cause Undetermined Because Major Factors Affecting Starting Capabilities Appeared Normal.No Recurrence of Problem
05000312/LER-1978-017-03, /03L-0:on 781215,during Refueling Shutdown, Blowdown Heat Transfer Pump Started & Sys Subjected to Sizable Water Hammer.Caused by Incomplete Valve Lineup. Hangers & Failed Snubber Repaired, & Personnel Notified
05000312/LER-1979-005-03, /03L-0 on 790509:two Inaccessible Safety Sys Hydraulic Snubbers Were Inoperable.Cause Unknown.One Snubber Rebuilt & Tested;Other Snubber Refilled
05000312/LER-1979-018-03, /03L-0:on 791117,during Periodic Visual Insp, Snubber 129 Found Inoperable Due to Lack of Oil.Caused by Loose lock-nut Which Allowed Unit to Rotate.Unit Will Be Modified During 1980 Refueling Outage to Secure Lock
05000312/LER-1979-006-04, /04T-0:on 791214,plant Effluent Sample Indicated 0.6 mg/1 of Chlorine & Followup Sample at Site Boundary Indicated 0.5 mg/1.Caused by Inadequate Dilution When Sewage Sys Discharged to Effluent.Normal Dilution Instituted
05000312/LER-1979-001-01, /01T-0:on 790129,RCS Cooldown Occurred at 120 F/H. Caused by Short Circuit Resulting in Reactor Trip.Procedure Mods Developed to Prevent Recurrence
05000312/LER-1979-003-04, /04T-0:on 791120,plant Effluent Sample Exceeded Tech Spec Limit of 0.2 Mg/L Chlorine.Caused by Excessive Flow in Plant Sewage Sys
05000312/LER-1979-001-04, /04L-0 on 790529:plant Liquid Effluent Ph Exceeded 8.5 Limit.Probably Caused by Error Band Associated W/Ph Alarm Setpoint.Investigation Feasibility of Reducing Error Band
05000312/LER-1979-019-03, /03L-0:on 791125,during Routine Plant Equipment Insp,Discovered Weld Leak on Seal Injection Line.Cause Not Stated.Defective Portion of Weld Ground Out & Weld Dye Penetrant Checked
05000312/LER-1979-005-04, /04T-0:on 791205,plant Effluent Sample Indicated Excess Amount of Chlorine at Site Boundary.Caused by Misunderstanding Between Chemistry & Operations Personnel Re Chlorine Specs.Recurring Problems W/Chlorine Under Review
05000312/LER-1979-004-04, /04T-0:on 791203,plant Effluent Samples Indicated Chlorine Levels Exceeded Tech Spec Limits.Caused by Partial Blockage of Sewage Sys Inlet Line.Dilution Flow Increased & Sewage Sys Hypochlorite Pump Stroke Reduced
05000312/LER-1979-016-03, /03L-0:on 791101,during Periodic Visual Insp of Accessible Safety Sys Hydraulic Snubbers,Snubbers 12 & 14 Determined Inoperable.Cause Unstated.Snubber 12 Rebuilt & Tested.Snubber 14 Refilled to Proper Level
05000312/LER-1980-001-03, /03L-0:on 800102,while Performing Requirements of IE Bulletin 79-02,found Support Did Not Meet Criteria 2, Making HPI B Sys Inoperable.Caused by Design Error.Pipe Support Modified
05000312/LER-1979-025-03, /03L-0:on 791227,during Verification of Test Data, Discovered Test SP205.02 Had Not Been Performed on Date Schedule Indicated.Caused by Error Made While Updating Surveillance Schedule.Rescheduled & Performed Tests
05000312/LER-1980-002-01, /01T-0:on 800104,while Performing Requirements of IE Bulletin 79-02,discovered That Pipe Support Did Not Meet Criteria 2.Caused by Differences in Design Criteria.Support Modified to Upgrade Safety Factor
05000312/LER-1979-021-03, /03L-0:on 791216,axial Power Shaping Rods Withdrawn Seven Days Earlier than Allowed Due to Error in Effective Full Power Day Calculations.Probably Caused by Crud on Feedwater Tubes.Tubes Inspected
05000312/LER-1979-020-03, /03L-0:on 791207,during Routine Insp of Plant Equipment,Weld Leak on Seal Injection Line Discovered.Caused by Previous Repair Problem or vibration-induced Stress.New Pipe Nipple & Socket Weld Cap Installed
05000312/LER-1979-012-03, /03L-0:on 791005,while Testing Anchor Bolts Per IE Bulletin 79-02,Region 5 Noted Excessive Failure Rates. Probably Caused by Const Installation.Discrepancies Being Corrected.Failure Criteria re-evaluated by Util
05000312/LER-1978-018-03, /03L-0:on 781221,while Increasing Power After Second Refueling Outage,Rcs Flow Indicator a Unusually Steady & Spurious Alarms Received.Caused by Operator Error. Transmitter Returned to Svc & Operator Instructed
05000312/LER-1978-010-01, /01T-0 on 780914:During Normal Oper It Was Found That Fire Hydrant 3 Hose Cabinet Had Not Been Relocated W/Hydrant.Upon Discovery of Discrepancy Hose Cabinet Was Relocated
05000312/LER-1979-007-01, /01T-0:on 790720,during Normal Operation,Analysis of Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts Indicated That Six safety-related Anchors at Facility Failed to Meet IE Bulletin 79-02,Criterion 2
05000312/LER-1979-006-02, /02T-0:on 790720,B&W Informed District That Addl Small Break LOCA Analyses Indicated That Certain Spectrum of Small Leaks in RCS Coupled W/Loss of Reactor Coolant Pumps Later in Transient Could Cause 10CFR50,App K to Be Exce
05000312/LER-1979-015-03, /03L-0:on 791031,A/E Informed Util That as-built Configuration of Line 47360-10 Inch,When Seismically Reanalyzed,May Result in Pipe Support Overstress.Caused by Nonconformance of Const Drawings.New Support Installed
05000312/LER-1979-002-04, /04T-0:on 791024,plant Effluent Sample Indicated Excessive Chlorine.Caused by Failure to Take Comparison Site Boundary Sample.Sampling Personnel Reinstructed
05000312/LER-1979-013-01, /01T-0:on 791101,while Analyzing Onsite Power Distribution Sys,Identified Possible Discrepancy in Event of Degraded Voltage Condition on Grid.Caused Unstated.Relay Reset
05000312/LER-1979-014-03, /03L-0:on 791008,as-built Configuration of Line 48222-18,when Seismically Reanalyzed,Resulted in Probable Support Pipe Overstresses.Caused by Design Documentation & Const Drawings Not Conforming W/Seismic Analyses
05000312/LER-1979-010-03, /03L-0:on 790829,bulbs for Pump P-4828 Were Not Lit.Dc Control Power Breaker Was in Off Position.Caused by Breaker Inadvertently Shut Off While Performing Maint on Another Breaker in Same Cubicle.Power Restored
05000312/LER-1979-011-03, /03L-0:on 790830,breaker 523A14 Was Inoperative Due to Connect Switch in Off Position,Causing Springs to Be Uncharged.Caused by Inadvertent Repositioning of Switch.Log Sheets Initiated for Verification
05000312/LER-1979-009-03, /03L-0:on 790814,contrary to Tech Specs,Borated Water Storage Tank Had Less than Specified Boron Concentration.Reactor Shutdown Initiated & Boric Acid Added to Tank,Bringing Concentration Above Limit
05000312/LER-1982-026-04, /04T-0:on 821006,review of Plant Effluent Records Disclosed Ph Reading of 6.2 for Less than 15 Minutes on 820918.Caused by Leaks at Two Elbows in Acid Line Running from Storage Tank to Turbine Bldg.Leaks Repaired