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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20207R752 | 9 March 1987 | Ro:On 870207,MSIV Failed to Close During Plant Shutdown. Caused by Binding of Valve Disc on Partially Removed Valve Stop.Disc Stop Matl Removed & Valve Tested.Sketch of Valve & Stop Encl | Unanalyzed Condition Nondestructive Examination |
| ML20207C814 | 22 December 1986 | Ro:On 861023 & 1128,RCS High Pressure Transient Occurred. Caused by Lifted Pressurizer PORV Due to Internal Event.More Specific Info Re Events Can Be Found in LERs 86-008 & 86-011 | |
| ML20215D623 | 11 December 1986 | Followup Ro:On 861128,operator Inadvertently Closed Main Steam Line Isolation Valves 3516 & 3517 Instead of Containment Vessel Depressurization Valves,Causing Pressurizer High Pressure Reactor Trip | |
| ML20204F922 | 29 July 1986 | Ro:On 860729,manual Reactor Trip Initiated When Large Quantity of Steam Found Rising Over Turbine Bay Area.Caused by Leak from Moisture Separator Reheater Drain Line 2A to High Pressure Feedwater Heater 5B.Drain Lines Repaired | Nondestructive Examination |
| ML20138Q875 | 7 November 1985 | Followup Summary:On 851106,alarm & Deluge of Fire Sys S-05 Received in Control Room.Caused by Spurious Signal Spike on Second Alarm Module.Investigation on Failure Mode of Fire Sys Continuing.Cable Tunnel Dried Out | Continuous fire watch |
| ML20128L918 | 12 July 1985 | Ro:On 850701,containment Vessel Sump Pump Actuation Interval Decreased Significantly from Normal.Caused by Svc Water Leak.Fan Cooler Inspected & Repaired | |
| ML20083P814 | 20 March 1984 | Ro:On 840307,during Drainage of RCS to Holdup Tanks,Rhr Containment Sump B Suction Valves MOV 851 a & B Opened Before Valve 850 a Closed,Causing Drainage of RCS Into Sump B | |
| ML20087P733 | 21 February 1984 | Ro:Providing Sequence Summary of Closeout or Class Reduction Condition for Unusual Event on 840219 Re out-of-svc Accumulators.Accumulators Returned to Svc & Declared Operable | |
| ML20087P971 | 27 January 1984 | Ro:On 831228,turbine Driven Auxiliary Feedwater Pump Steam Stop Valve Found in Tripped Position,Although Control Room Indication Indicated Valve Open.Caused by Contractor Stepping on Valve Trip Mechanism | |
| ML20077N590 | 31 August 1983 | Ro:On 830303,diesel Fuel Oil for Fire Pump Found Below Viscosity Limit.Caused by Delays in Transporting Sample to Lab for Analysis.Procedures to Expedite Resampling & Analysis Being Reviewed | Boric Acid |
| ML20072N589 | 8 July 1983 | Ro:On 830609,during Safety Injection Functional Test,When Safety Injection Signal Initiated by Simulating High Containment Pressure,Charging Pump 1C Did Not Trip, Causing Operation of Reactor Overpressure Protection Sys | |
| ML20072U594 | 31 March 1983 | Ro:On 830331,health Physics Technician Fell 40 Ft to Floor of Reactor Cavity.Individual Removed from Area & Taken to Hosp to Be Treated for Serious Injuries & Decontaminated | Fire Watch |
| ML20083P102 | 21 January 1983 | RO 83-006/01:on 830120,alarm Received in Control Room Indicating Low Screenhouse Water Level of 20 Ft,Rendering Fire Suppression Water Sys Inoperable.Addl Info Will Be Presented in 14-day Written Rept | Frazil ice |
| 05000244/LER-1982-003, RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept | 24 February 1982 | RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept | |
| ML20084D941 | 15 July 1977 | Supplemental RO-77-010:four Addl Supports (SW-69,73,78 & 83) Found W/Stresses Under DBE Conditions in Excess of Allowable Values.Corrective Actions Underway | |
| ML20084D938 | 14 July 1977 | RO-77-010:on 770713,design Error Found in Redundant Svc Water Discharge Line Support.Overstress Condition Could Exist W/Line Not Yet Charged or in Svc.Line in Hold Condition | Backfit |
| ML20084B855 | 10 February 1977 | Supplemental RO 76-24:on 761008,leaks Found in 8-inch Schedule 10 Boric Acid Piping.Cause of Cracks Probably Due to Stress Corrosion Attack | Boric Acid Hydrostatic Nondestructive Examination Liquid penetrant |
| ML20084C151 | 21 December 1976 | Supplemental RO-76-21:on 760819,two Control Rods Dropped. Westinghouse Recommendations for Cause Later Determined Not to Be Actual Cause.New Recommendations to Be Carried Out During Next Refueling Outage | |
| ML20084C315 | 21 June 1976 | Supplemental RO 76-10:on 760228,excessive Leakage Observed from Valve Inside Purge Supply Control Valve.Results of Vendor Insp of Assembly Submitted | |
| ML20084C290 | 25 May 1976 | Supplemental RO-76-12:on 760331,during Testing,Excessive Leakage Found in Containment Personnel Airlock Handwheel Shaft Seal.Corrective Action Include Placing Seal on Packing Gland Nuts to Prevent Rotation W/Shaft | |
| ML20084A097 | 12 May 1976 | Supplemental RO 76-07 Re Train a Containment Isolation & Ventilation Isolation Failure to Latch.Fourteen Relays Checked for Clearance Between Electromagnet Pole Face & Raised Section of Armature | |
| ML20083R888 | 9 March 1976 | RO 76-11:on 760308,control Room Charcoal Filter Damper Discovered Improperly Positioned.Trouble Card Issued & Work Initiated to Correct Problem | |
| ML20084A012 | 23 February 1976 | RO 76-08:on 760227,39 Steam Generator Tubes Explosively Plugged in Steam Generator a & 2 in Steam Generator B.Tubes Exhibited Tube Wall Deterioration in Excess of 40% | |
| ML20084A135 | 8 February 1976 | RO 76-05:on 760208,excessive Leakage Observed Through Several Containment Penetrations.Cause Not Stated.Repairs to Valves Underway | |
| ML20084A972 | 7 November 1974 | Ro:On 741008,Westinghouse Informed Util That Safety Injection Sys Delivery Curve Employed for Steam Line Break Accident Analysis Inconsistent W/Analyses Used for Recent Loca.Util to Maintain Shutdown Margin of at Least 2.45% | Shutdown Margin |
| ML20084E225 | 7 June 1974 | Ro:On 740509,during Surveillence Procedure PT 16,little Flow Reduction Occurred Following Opening of Motor Driven Auxiliary Feedwater Pump a & B Discharge Valve.Cause Unapparent.Frequency of Surveillance Test Increased | |
| ML20084H096 | 25 February 1974 | RO: Overexposure of Individual to Radiation Occurred During First Quarter of 1974.Correction to Reporting Similar Occurrence Encl | |
| ML20084H099 | 20 February 1974 | RO: Individuals Overexposed to Radiation During First Quarter 1974.Investigation Underway | |
| ML20084E334 | 21 June 1973 | Ro:On 730523,thirty Minutes After Boric Acid Transfer Pumps Started Recirculation,Control Rods Noted as Stepping Out. Caused by Malfunction of Blend Sys Valve FCV-110B.Repair Instituted & Completed on 730524 | Boric Acid |
| ML20084E436 | 8 June 1973 | Ro:On 730529,during Performance of Monthly Surveillance Undervoltage & Underfrequency Protection,Device Armature of Knife Switches for Solenoid Coil Discovered Not Dropping to Assume Deenergized Condition.Caused by Scale Accumulation | |
| ML20084E365 | 7 June 1973 | Ro:On 730606,high Bistable Setting Approx 2.1% Higher than Specified Value Set Forth in Plant Procedure.Caused by Personnel Error in Transposing Desired Calculated Current Level from Work Sheet.Setting to Correspond W/Steam Flow | |
| ML20084E354 | 31 May 1973 | Ro:On 730502,Bank D Control Rod Sys Observed Stepping Out of Core.Caused by Loose Solder Joint in QM-401.Automatic Rod Control Immediately Switched to Manual W/No Indication of Any Change in Reactor Power.Averaging Unit Repaired | |
| ML20084E456 | 30 May 1973 | Ro:On 730529,upon Opening Knife for Solenoid Coil of Primary Undervoltage Device 273/IIA,device Armature Discovered Not Dropping Down to Assume Deenergized Condition.Caused by Scale Accumulation on Device.Investigation Continuing | |
| ML20084E616 | 28 December 1972 | RO:720831 & 0901 Unplanned Release of Radioactive Passes Occurred During Removal of Spent Resins from Spent Resin Tanks.Cause Not Stated.Written Procedure for Handling Resin Revised & Precaution Included Re Vent Header Pressure | |
| ML20084E964 | 30 June 1972 | Ro:On 720623,w/reactor at 5% Thermal Power,Control Board Received Alarms of Rod Bottom Rod Stop & Rod Control Urgent Failure Rod Stop.Caused by Water from Swagelok Fitting on Tubing Dropping on Rod Control Cabinets.Fitting Repaired | |
| ML20084E973 | 31 May 1972 | Ro:On 720503,upon Entering Steam Generator & Starting Grit Blasting Equipment,Workman Discovered Face Mask Not Functioning & Exited Area.Caused by Failure to Tighten Threaded Connection of Air Hose to Mask.Exams Performed | |
| ML20084E468 | 28 April 1972 | Ro:On 720420,while Plant Being Cooled Down in Preparation for Refueling,Release Rate of Airborne I-131 from Plant Vent Exceeded Tech Spec Limits.Cause Unknown.Charcoal Filters from Plant Vent Iodine Monitor Being Replaced | Boric Acid |
| ML20084E659 | 30 March 1972 | Ro:On 720320,while Reactor in Hot Shutdown,Msivs Tested for Closure & MSIV-1B Valve Found Closed Only Half Way.Cause Unknown.Valve Mfg Contacted for Recommendations to Prevent Recurrence | |
| ML20084F080 | 7 February 1972 | Ro:On 720131,while Conducting Monthly Surveillance Test, Underfrequency Relay on 4160-kV Bus 11B Failed to Transmit Signal to Logic Racks.Caused by Faulty Capacitor.Spare Relay Installed & Tested Satisfactorily | |
| ML20084F121 | 14 December 1971 | Ro:On 711205,safety Injection Pump Motor C Tripped Automatically When Nearly Up to Speed.Caused by Motor Tripping Out on Starting Current Due to Leakage in Time Delay Dashpot.Replacement Overcurrent Device Installed | |
| ML20084E567 | 9 July 1971 | Ro:On 710630,MSIV Failed to Close on Signal.Solenoid Operators on MSIV 1A Removed & Inspected and All Parts | |
| ML20084E610 | 11 June 1971 | Ro:Between 710601-05,calculations Indicated Gaseous Effluent Release Limits Exceeded.Caused by Gasket Leak on Vol Control Tank Pressure Control Regulator Valve PCV141.Continuous Recording Iodine Monitor Installed on Stack Vent | |
| ML20084E637 | 29 April 1971 | Ro:On 710422,during Diesel Generator Load & Safeguard Sequence Test,Valves 826 A,B,C & D Failed to Open.Caused by Momentary Loss of Voltage on 480-volt Safeguard Busses.Power Supply Transfer Recommended | Boric Acid |
| ML20084E836 | 21 December 1970 | Ro:During 700930-1015 Shutdown,Broken Stud Found on One Support for Primary Sys Component.W/O Stated Encl | |
| ML20084E856 | 14 October 1970 | Ro:On 701004,core Deluge Valve 852B Malfunctioned.Caused by Seizure of Stem Nut to Valve Stem.New Stem Nut Installed | |
| ML20084E550 | 15 July 1970 | Ro:On 700706,boron Dilution Performed W/Reactor Critical & No Reactor Coolant Pump on RHR Pump in Operation.Orders Issued That Maint Work Performed Only W/Authorized Procedures Available | Boric Acid Power change |
| ML20084E721 | 22 May 1970 | Ro:On 700514,during Reactor Cooldown Procedure,Msiv 1B Failed to Close.Caused by Malfunction of Valve Mechanism. Packing Gland Loosened | |
| ML20084E782 | 13 March 1970 | Ro:On 700306,during Surveillance Test,Excessive Air Leakage Around Lower Handwheel Shafts That Penetrate to Outside Handwheels Noted.Ring of Packing to Lower Handwheel Shaft Added | |
| ML20084E777 | 27 February 1970 | Ro:On 700130,motor Operated Svc Water Valves 4013,4300 & 4028 on Emergency Suction Line to Auxiliary Feedwater Pumps Reported to Operate Improperly.Caused by Operating Personnel Misunderstanding | |
| ML20084E416 | 19 January 1970 | RO:700108,during Draining Required to Permit Replacement of Coolant Temp detectors,in-core Thermocouple Reading Indicated Temp Exceeded Tech Spec Limit.Caused by Failure to Monitor Temp by Alternate Means |