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 Issue dateTitleTopic
ML20247E07020 July 1989Info Rept:On 890717-0804,fire Penetration Seals Will Be Removed from Svc to Allow Access for Ventilation Sys Mod. Addl Fire Barrier Penetrations Will Be Made in Wall Between RHR Pump Pit & Fuel Handling Bldg,Per Tech Spec 3.14.7.2Fire Barrier
ML20205F60223 March 1987Special Rept:On 870302,noble Gas Effluent Monitor for Main Steam Line B Declared Inoperable & Svc Not Returned Until 870312.Caused by Defective Detector.Detector Replaced.High Voltage for Detector Adjusted & Sys Operation Checked
ML20215F03629 September 1986Special Rept:On 860902,during Cold Shutdown,Pressurizer PORV Lifted Twice to Prevent Overpressurization.Caused by Inadvertent Action by Unit Operators.Operations Personnel Counseled Re Importance of Breaker Position Indicators
ML20203P09825 April 1986Special Rept:On 860329,mechanical Fire Penetration Returned to Svc After Being Inoperable for Greater than 7 Days.Caused by Unacceptable Repair on 860327.Foam Sealant Equipment Repaired & Personnel TrainedFire Barrier
ML20154R02613 March 1986Special Rept:On 860204,motor-driven Fire Pump Taken Out of Svc to Permit Divers to Enter Circulating Water Intake Structure.Intake Bay Dewatered on 860206 to Perform Addl Insps & Maint.Intake Bay Flooded on 860211.Part 21 Related
ML20128C21616 April 1985Special Rept:On 850318,RCS Iodine Radioactivity Spike Occurred.Cause Not Stated.Subsequent Sampling Met Requirements of Tech Spec 3.1.4.RCS I-131 Dose Equivalent Returned to Previously Experienced Levels on 850320
ML20093M0135 October 1984Special Rept:As Result of Extensive Util Fire Barrier Penetration Insp Program,Number of Deficient Fire Barrier Penetrations Discovered.Penetrations Will Be Upgraded/ Dispositioned Prior to StartupFire Barrier
ML20081C9886 March 1984Special Rept:On 840131,six Hose Stations,Seven non-Tech Spec Hose Stations & Two Hydrants Inoperable Due to Isolation of Water Loop for Bldg Const.Addl Support for Rerouted Fire Water Piping ProvidedHydrostatic
ML20082H65323 November 1983Ro:On 831103,plant Shutdown for Steam Generator Tube Insp. Results Listed.Outage Still in Progress.Final Insp Results Forthcoming in 14-day LER
ML20081M0999 November 1983RO 82-009:specific Procedures to Test Motor Operated Valve Torque Switch Settings Not in Place by 830930.Caused by Committing Resources to Other Recent Regulatory Requirements.Procedures Will Be Established
ML20080P70329 September 1983Ro:On 830928,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24
ML20078D42927 September 1983Ro:On 830926,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Cooler Declared Inoperable.Repairs Initiated. Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24
ML20080M02819 September 1983Ro:On 830916,Tech Spec Instantaneous Release Limit for Radioiodine Exceeded.Investigation Continuing
ML20081F85712 September 1983Ro:On 830905,facility Shut Down Due to Secondary Leak in Steam Generator A.Two Tubes Exhibited through-wall Indications Which Should Have Been Plugged.Tubes Plugged & Tested SatisfactorilyEddy Current Testing
ML20076H70224 August 1983Ro:On 830823,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Svc Water to Cooler Isolated.Repairs Performed
ML20081F8825 July 1983Ro:On 830704,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Operability Testing of Containment Spray Pumps Completed.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24
ML20151H72828 April 1983Ro:On 830427,svc Water Pump a Removed from Svc for Normal Preventative Maint & Replaced W/Rebuilt Spare Pump. Post-maint Testing Resulted in Pump Over Current Trip.Caused by Internal Binding of Rebuilt Pump
ML20073R27625 April 1983Ro:On 830424,svc Water Booster Pump B Declared Inoperable Due to Bearing Failure & Plant Shutdown Commenced Following Pump a Trip Due to Blown Control Power Fuses.Fuses Replaced & Pump a Restarted.Investigation Continuing
ML20073H93811 April 1983Ro:On 830410,svc Water Leak Discovered on Containment Fan Cooler HVH-3.Svc Water Immediately Isolated.Condition Reportable Per IE Bulletin 80-24 as Degradation of Containment Boundary
ML20072E16828 February 1983RO-82-009 Re Failure of Motor Operated Valve RHR-759A. Due to Larger than Anticipated Work Scope,Completion Date for Corrective Actions Revised.Insp & Testing of Torque Switch Will Be Completed by End of Next Refueling Outage
ML20063M11031 August 1982Ro:On 820811,RHR Containment Suction Valve RHR-861A Found Opening Only Halfway & Promptly Declared Inoperable. Requests Extended 48-h Maint on Valve.Valve Not Completely Disassembled & Total Scope of Repair Not Established
ML20063M1413 August 1982Ro:On 820731,during Hot Shutdown,Leak Observed Coming from Control Rod Drive Mechanism Valve for Rod L-11.Leak Identified as Abnormal Degradation of RCPBTime of Discovery
ML20063M11416 July 1982Ro:On 820715,small Leak in Form of Mist Found on Hydrogen Vent Header 2 Motor Cooler.Header Secured & Svc Water Isolated.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24
ML20054H45618 June 1982Ro:On 820428,PT-9.13 Revealed Failure in Power Supply to Damper Relay Panel B1 (Train B) Concurrent W/Failed Relay for Zone 10 (South Cable Vault) on Panel A1 (Train A). Correction in Progress & Completion Expected by 821231
ML20063M10527 April 1982Ro:On 820426,during Refueling outage,100% Eddy Current Insp of All Steam Generators Revealed Pluggable Indications of 4.4% & 1.5% on Generators B & C,Respectively.Generators Classified as Sampling Category C-3
ML20063M31321 April 1982Ro:On 820416,routine Reading of Contractor Health Physics Technician TLD Indicated 6.6 Rem.Cause Not Stated.Backup Dosimetry Did Not Confirm Reading.Investigation Results to Be Submitted
ML20084S86330 January 1978Ro:On 780129,RCS Pressure Exceeded Tech Spec Limit by 60 Psig.Cause Not Stated.Rhr Pumps Restarted to Reduce Pressure
ML20084S88326 August 1977Ro:On 770825,Westinghouse Notified Util of Probable Error in Calculation of Sodium Hydroxide Concentration in Containment Spray Additive Tank.Caused by Procedural Error. Concentration Increased & New Analysis Initiated
ML20084S89015 August 1977Telecopy Ro:On 770812,Westinghouse Informed Util of Incorrect Tech Spec Limits of Pressurizer Heatup & Cooldown Limits.Tech Spec States Heatup & Cooldown Rates Shall Not Exceed 200 F & New Limits Equal 300 F
ML20084S9047 June 1977Telecopy Ro:On 770607,charging Pump High Speed Alarm Received & Pressurizer Level Decreased.Charging Pump C from Svc for Venting,Pump B Failed to Maintain Normal Pressurizer Level & Pump a Being Repaired
ML20084S92126 January 1977Telecopy Ro:On 770125,flow Paths from Boric Acid Tanks Made Inoperable for Valve RepairBoric Acid
ML20086D2601 December 1976RO:761117,discovered Canopy Seal Welds for Two Control Rod Drive Mechanism Housings Had Small Pin Hole Leaks
BSEP-76-1374, Ro:On 761119,RHR Low Pressure Coolant Injection Valves E11-FO15A & B Had Marginal Breaker Magnetic Trip Settings. Cause Appears to Be Generic.Breakers Being Replaced19 November 1976Ro:On 761119,RHR Low Pressure Coolant Injection Valves E11-FO15A & B Had Marginal Breaker Magnetic Trip Settings. Cause Appears to Be Generic.Breakers Being Replaced
ML20086F40617 November 1976Rept of Incidents/Occurrences for 760102-1117Boric Acid
BSEP-76-1143, Ro:On 760922,engineering Analysis Delineated Potential Problem W/Primary Containment Instruments 2-CAC-AT-1259 & 2-CAC-AT-1263.Dehumidifiers May Trip in Event of Loca.Caused by Excessive Heat.Short Sensing Lines Isolated23 September 1976Ro:On 760922,engineering Analysis Delineated Potential Problem W/Primary Containment Instruments 2-CAC-AT-1259 & 2-CAC-AT-1263.Dehumidifiers May Trip in Event of Loca.Caused by Excessive Heat.Short Sensing Lines Isolated
ML20086D33918 August 1976Ro:On 760817,while Performance PT 22 on Auxiliary Feedwater sys,V2-16A Would Not Open Electrically from Rtgb.Redundant Equipment Operated Satisfactorily,Proving Ability to Feed Steam Generator in Emergency Conditions
ML20086D3626 August 1976Ro:On 760806,util Notified by Westinghouse of Recent Developments Re Westinghouse Safety Analyses.Limiting Values for Fq & Pnh Reduced to 2.27 & 1.49,pending Further Investigation
ML20086D4022 April 1976Ro:On 760402,discovered That Boric Acid Heat Tracing Circuit 56 Had No Current Flow & Was Inoperative.Breaker Opened in Each Heat Trace Power PanelsBoric Acid
ML20086D41215 March 1976Ro:On 760312,util Notified by Westinghouse of Possible Error in LOCA Analysis.Error Involves Oversight of Potential Effect of Steam Generator Tube Plugging.Limiting Valve of Fq Reduced to 2.26 Pending Further Investigation
ML20085D0369 August 1973Ro:Water Vol in Safety Injection Accumulators Found Below Min Required Tech Spec Limit.Caused by Incorrectly Fixed High & Low Level Alarm Setpoints.New Setpoint Documentation Approved
ML20085D11227 June 1973Ro:On 730620,during Test on Turbine Redundant Overspeed Trip Sys,Turbine Trip Inadvertently Initiated.Caused by Turbine Stop Valve Limit Switch Failure.Switch AdjustedOverspeed trip
ML20085D23226 April 1973Ro:On 730327,individual Received Overexposure to Radiation While Checking for Leakage in Reactor Sump Area.Technicians Instructed on Importance of Knowing Exposure Limit & Remaining Dose of Individual Working in AreaOverexposure
ML20085D22424 April 1973Ro:On 730410,spill of Water from Refueling Water Storage Tank to Plant Storm Drainage Sys Occurred.Caused by Leakage in Line Between Spent Fuel Cooling Sys & Safety Injection Sys Due to High Pressure.Piping & Valves Pressurized
ML20085D3179 February 1973Ro:On 721220,leak Detected Inside Containment Vessel in Joint Where Auxiliary Feedwater Pipe B,4-FW-23 Joins Main Feedwater Pipe B,16-FW-10.Caused by Saddle Welds Not Designed as Pressure Boundary.Boundary Rewelded
ML20085D26330 November 1972Ro:On 721105,power Operated Relief Valve RV-2 on Steam Line B Failed to Close.Caused by Relief Valve Sticking in Open Position.Inner Valve & Guide Bushing Polished
ML20085D39910 November 1972Ro:On 721019,boric Acid Tank B & Boron Injection Tank Found Low in Boron Concentration.Caused by Improper Seating of Suction & Discharge Isolation Valves of Tank.Tank Recirculated W/Boric Acid Tank aBoric Acid
ML20085D40720 October 1972Telecopy Ro:On 721019,boron Injection Tank & Boric Acid Tank B Found to Have Low Concentration of Boric Acid.Steps Initiated to Return Tanks to Normal ConcentrationBoric Acid
ML20085D37311 September 1972Ro:On 720726 Following Part Length Rod Control Sys Alarm, Frequency Sensor Relay Found Inoperable.Relay Replaced
ML20085D42224 July 1972Ro:On 720716,concentration of Boron Injection Tank Found Diluted Below Tech Spec Limit.Caused by Plugged Recirculation Path Between Boric Acid & Injection Tanks. Temporary Hose Rigged to Recirculate Acid Between Two TanksBoric Acid
ML20085D13718 July 1972Ro:On 720709,steam Line Isolation Valve B Malfunctioned During Periodic Test.Caused by Sheared Pin in Linkage Between Valve Stem & Disc.Valve Repaired