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 Issue dateTitleTopic
ML20086D55729 September 1977Telecopy Ro:On 770929,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO-14-13A Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation
ML20086D56114 September 1977Telecopy Ro:On 770913,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO 14-13B Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Related Event on 770914
ML20086D56712 September 1977Telecopy Ro:Main Steam Drain Isolation Valve MD 2373 & Main Steam Outboard Isolation Valve AO 2-86A Exceeded Tech Spec Acceptance Criteria for Local Leak Rate Tests
ML20086D64211 July 1977Telecopy Ro:On 770709,determined That Recombiner Sys a Offgas Flow Control Valve PCV 7489A Could Be Opened W/ Controlling Solenoid Valve Deenergized.Valve Held from Svc Pending Investigation
ML20086D6912 March 1977Telecopy Ro:On 770301,torus Water Vol Found to Be Slightly Below Min Vol Established by Tech Specs.Water Vol Restored to Normal Operating Level
ML20086D70324 February 1977Telecopy Ro:On 770223,while Withdrawing in-sequence Control Rod to Bring Reactor Critical,Reactor Period of Less than 5 Obtained
ML20086D78810 September 1976Telecopy Ro:On 760909,discovered That Torus Water Vol Several Hundred Cubic Ft Below 68,000 Cubic Ft Min Required by Tech Specs.Caused by Failure to Correct for Vol Vs Level Correlation
ML20086D8235 May 1976Telecopy Ro:On 760504,during Routine Surveillance Test, Primary Containment Oxygen Concentration Found to Be in Excess of Tech Spec Limit.Caused by Leakage from Drywell Instrument Air Sys Into Containment Nitrogen Supply Line
ML20086F0806 June 1977Ro:On 770506,plant Iodine & Particulate Release Rate Exceeded 4% of Facility Tech Spec Averaged Over Second Calendar Quarter of 1977.Caused by Fuel Perforations Coupled W/End of Cycle Testing & Reactor Coolant & Steam LeaksFuel cladding
ML20086F4189 December 1976RO Re Plant Iodine & Particulate Release Rate Exceeding 4% of Tech Spec 3.8.C.2 Averaged Over Fourth Calendar Quarter 1976.Caused by Leaks in Reactor Water Cleanup Sys.Leaks Repaired & Equipment Modified to Reduce Leakage
ML20086F47027 January 1976Ro:On 760117,gaseous Activity Release Rate Exceeded 4% of Tech Spec 3.8.C.1 for More than 48 H.Caused by Increase in Offgas Activity Due to Fuel Cladding PerforationsFuel cladding
Power change
ML20086F47323 December 1975Ro:On 751123,during Insp of Upper Portions of Drywell,Two of Eight Reactor Vessel Stabilizers Appeared to Have Been Slightly Deformed.Caused by Stabilizer Bindup & Cyclic Loading During Vessel Heatup or Cooldown
ML20090D42520 April 1972Ro:On 720411,supply Dampers for Reactor Bldg Ventilation Sys Failed to Close.Caused by Shorted Motor Due to Electrical Problem in Supply Fan 1-13 & racked-out Supply Breaker. Circuit Design Change Will Be Implemented
ML20090D4296 October 1972Ro:On 720925 & 26,standby Liquid Control Pump Discovered Inoperable.Caused by racked-out Circuit Breaker.Operating Procedures Changed
ML20090D48717 January 1973Ro:On 721229,turbine Trip & Anticipatory Reactor Scram Initiated When Operator Opened Cabinet Door Carrying Protective Fuses for Generator Monitoring Relays.Caused by Open Pilot Valve for Electromatic Relief Valve DBreakaway torque
ML20090D67220 January 1972Ro:On 711213,unit Tripped Offline During Surveillance Testing.Sensor Support Accidentally Bumped Causing High Level Trip Sensor to Operate Resulting in Turbine Trip. Review of Expected Sys Responses Given to Operators
ML20101M84910 December 1984Ro:On 841203,wide-range Log Channel Malfunctioned,Resulting in Manual Scram.Cause Traced to Resistor in Filter on Detector High Voltage Supply.Repairs & Testing in Progress
ML20105D24324 June 1983Special Rept:Five Individuals Found to Have Received Radiation in Excess of 10CFR20.101 Limits W/O Required Documentation.Caused by computer-based Sys Feature Allowing Use of Outdated Info & Personnel Error.Procedures RevisedHigh Radiation Area
Locked High Radiation Area
ML20114B32214 January 1985Ro:On 850107,while Taking Unit to 95 Kw Power,Period Meter Indicated Period Decreasing W/Log Power Trace Levelling & Linear Power Trace Rising.Caused by wide-range Log Channel Malfunction.Manual Scram Initiated & Reactor Secured
ML20136H32913 November 1985Ro:On 851112,wide-range Log Channel Malfunctioned During Operation of Reactor.Caused by Faulty Calibr Switch in Log Channel.Switch Adjusted & Reactor Operated at Several Power Levels Up to 95 Kw
ML20137G44623 June 1977Ro:On 770621,radioactive Source Containing 200 Mci Cs-137 Recovered from Brine Well 33.Incident Described in
ML20137G45024 March 1981Ro:During walk-through of Operator Training Program, O-ring Seal of Filter Holder Found Not Seated Properly Causing Partial Bypass of Filter for Air Sucked Into instrument.Filter-in Lock Adjusted
ML20137G79322 November 1971Ro:On 711022,during Startup of Reactor,Period Limiting Signal Unavailable for Servo Sys Which Continued to Raise Rod Causing Rapid Rise of Power.While Reactor Manually Scrammed,Reactor Period Less than Min Allowed in Tech Specs
ML20137G81616 February 1973Ro:On 730125,available Excess Reactivity of Core Exceeded Tech Specs Limit.Caused by Change in Worth of Control Rods. Rearrangement of Core Configuration Initiated to Reduce Available Excess Reactivity
ML20137H38412 January 1976Ro:On 760106,operator Left Console Key in Switch So That Reactor Not Secured Per Tech Specs.Key Withdrawn from Console.Incident Discussed W/Operators & Large Red Plastic Tag Attached to Key to Make It More Visible
ML20198H36914 November 1983Ro:On 831003,results of as-found Tests Indicated Crosby Main Steam Relief Valves Had Lift Points Exceeding Tech Spec Limits.Valves Disassembled & Rebuilt by Mfg
ML20206K7092 November 1972Unusual Occurrence UO-72-6:on 720924 & 29,out-of-svc Condition of Primary Sys Boundary Coolant Leakage Air Sampling Sys Occurred.Caused by Moisture Accumulating in Detection Equipment.Mod to Equipment Designed
ML20211E07326 September 1986Unplanned Operating Event Rept 85-6, Manual Reactor Trip Following MSIV Closure Due to Inadvertent Emergency Feedwater Actuation,851009
ML20211K82118 June 1986Special Rept:On 860521,valid Failure Occurred on Div 2 Diesel Generator During Performance of Tech Spec Surveillance 4.8.1.1.2.Caused by Failure of Jacket Water Thermostatic Control Valve to Open
ML20212Q69726 August 1986Ro:On 860821,during Prestartup,Source Interlock Operated But Failed to Prevent Movement of Control Rods.Caused by Temporary Loss of Electrical Contact in Logic Circuits. Movement Restored Proper Electrical Contact
ML20215H50916 August 1972Ro:On 720727,during Shutdown,Two Employees Injured When Steam Vent Sys Malfunctioned.Caused by Decay Heat Release Piping Disengaging from Piping Support Sys.Workers Treated for Burns.Design Change Investigated.News Release Encl
ML20235C89928 April 1971Ro:On 710422,HPCI Sys Declared Inoperable & Taken Out of Svc Due to Minor Steam Leaks.During Maint,Lubrication & Control Oil Sys Found Dirty.Leaks Repaired & Oil Sys Cleaning & Flushing Will Be Done.Sys Should Be Operable by 710505
ML20235D06330 April 1971Ao:On 710422,during Analysis of Loss of Offsite Power Test Data,Initiation Setpoints of Four RCS Safety/Relief Valves Possibly in Excess of Tech Specs Limit Noted.Caused by Effect of Temp.Calibr Checks Done & Valve Settings Adjusted
ML20235D25229 April 1971Ro:On 710420,determined That Two Air Ejector off-gas Monitors Have Been Inoperable During Startup Testing Program to 25% Power Level.Caused by Improper Hookup of Ejector Sample Chamber Purge Valve.Sys Piped Up ProperlyGrab sample
ML20235D61719 May 1971Aos:On 710420,26 & 0502,condenser Pressure Switches Isolated,Msiv Closed Too Slowly & Automatic Pressure Relief Sys Fuses Found Missing,Respectively.All Conditions Corrected
ML20235D89611 June 1972Ro:On 720609,w/reactor in Shutdown Mode,Northeast Expansion Joint on Condenser Circulating Water Sys Ruptured.Unit 2 Reactor in Startup Mode & Shut Down Immediately
ML20235D99915 September 1971Ro:On 710904,during Monthly HPCI Operability Test,Steam Line Isolation Valve Tripped from False High Steam Flow Signal. Caused by Increase in Flow Elbow Differential Pressure.Flow Elbow Sensing Lines Backflushed & HPCI Sys Tested
ML20235E0273 July 1972Ro:On 720702,RCIC Manually Aligned to Inject Into Reactor. Final Injection Valve MO-1-1301-49 Failed to Open.Reactor Shut Down W/All Rods in
ML20235E03424 September 1971Ro:On 710915,during Monthly Surveillance Test,Eccs Pump Start Permissive Pressure Switches Tripped Below Settings Specified in Tech Specs.Caused by Incorrect Calibr Procedure.Switches Recalibr & Tested.Procedure Revised
ML20235E10228 September 1971Ro:On 710918,HPCI Sys Declared Inoperable & Remained So Until 710924.Caused by Recurrent Increase in Flow Elbow Differential Pressure Leading HPCI Steam Line to Isolate. Flow Rate Testing Procedure Revised to Isolate B Steam Line
ML20235E2565 October 1971Ro:On 710905,ECCS Initiation Problems Re Loss of Plant Air Noted.On 710909,false Initiation Signal Occurred During Surveillance Test & lo-lo Reactor Water Level Switch Failed. Caused by Human Error & Mechanical Failure
ML20235E3865 November 1971Ro:On 711006,13 & 15,respectively, Core Spray Header Differential Pressure Switch Isolated,Steam Line Differential Pressure Switch Failed & Low Condenser Vacuum Scram Instrument Setpoint Drifted.Conditions Corrected
ML20235E41115 December 1971Ro:On 711116,while Reactor Shut Down,Structural Damage to Torus Baffles Noted.Caused by Initial Transient Dynamic Loading Due to Discharge Into Torus Water.Baffles Removed & Relief Valve Discharge Lines Fitted W/Rams Head Tee
ML20235E56428 January 1972Ro:On 710928,following Reactor Scram & Isolation,Safety/ Relief Valve D Failed to Seat on Manual Actuation.Caused by Galled Stem in Main Valve Piston Assembly,Leading Valve to Stick.New Discs W/Stellite Coated Stems Installed
ML20235E64116 November 1972Telecopy Ro:On 721115,MSIV 1-203-2D Would Not Check Properly Using Test Circuit Load.Valve Closed to Comply W/Tech Spec Section 3.7.D.S
ML20235E67915 February 1972Supplementary Ro:On 711116,structural Damage to Torus Baffles Discovered.Caused by Initial Transient Dynamic Loading.Listed Repair Work,Including Catwalk Bracing & Insps Completed.Updated Diagrams Encl
ML20235E79021 February 1972Supplemental Ro:Updates Listed Util Repts Re Defective Main Steam Line High Flow Switches,Eccs Pump Start Permissive Switch (Ps) & ECCS Valve Operating Ps,Respectively. Instrumentation Problems Diagnosed & Corrected
ML20235E90825 November 1972Telecopy Ro:During Routine Surveillance Calibr on Main Steam Line Flow Switches,Two Switches Found to Have Drifted Beyond Tech Spec Limit.Both Switches Recalibr
ML20235E9682 June 1972Ro:On 720226,during Turbine Stop Valve 10% Closure Surveillance Test,All Stop Valves Tripped Closed Causing Reactor Scram & Momentary Opening of Safety Valve A.Caused by Loss of Turbine Trip Oil Pressure & Steam Transient
ML20235F03828 July 1972Ro:On 720721,main Transformer Fire Deluge Sys Initiated by Short in Manual Initiation Circuit.Caused by Malfunction of Steamline safety-relief Valve D.Valve Replaced
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