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Issue date | Title | Topic | |
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ML20247E070 | 20 July 1989 | Info 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 3.14.7.2 | Fire Barrier |
ML20205F602 | 23 March 1987 | Special 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 | |
ML20215F036 | 29 September 1986 | Special 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 | |
ML20203P098 | 25 April 1986 | Special 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 Trained | Fire Barrier |
ML20154R026 | 13 March 1986 | Special 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 | |
ML20128C216 | 16 April 1985 | Special 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 | |
ML20093M013 | 5 October 1984 | Special 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 Startup | Fire Barrier |
ML20081C988 | 6 March 1984 | Special 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 Provided | Hydrostatic |
ML20082H653 | 23 November 1983 | Ro:On 831103,plant Shutdown for Steam Generator Tube Insp. Results Listed.Outage Still in Progress.Final Insp Results Forthcoming in 14-day LER | |
ML20081M099 | 9 November 1983 | RO 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 | |
ML20080P703 | 29 September 1983 | Ro:On 830928,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 | |
ML20078D429 | 27 September 1983 | Ro: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 | |
ML20080M028 | 19 September 1983 | Ro:On 830916,Tech Spec Instantaneous Release Limit for Radioiodine Exceeded.Investigation Continuing | |
ML20081F857 | 12 September 1983 | Ro: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 Satisfactorily | Eddy Current Testing |
ML20076H702 | 24 August 1983 | Ro:On 830823,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Svc Water to Cooler Isolated.Repairs Performed | |
ML20081F882 | 5 July 1983 | Ro: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 | |
ML20151H728 | 28 April 1983 | Ro: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 | |
ML20073R276 | 25 April 1983 | Ro: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 | |
ML20073H938 | 11 April 1983 | Ro: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 | |
ML20072E168 | 28 February 1983 | RO-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 | |
ML20063M110 | 31 August 1982 | Ro: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 | |
ML20063M141 | 3 August 1982 | Ro:On 820731,during Hot Shutdown,Leak Observed Coming from Control Rod Drive Mechanism Valve for Rod L-11.Leak Identified as Abnormal Degradation of RCPB | Time of Discovery |
ML20063M114 | 16 July 1982 | Ro: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 | |
ML20054H456 | 18 June 1982 | Ro: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 | |
ML20063M105 | 27 April 1982 | Ro: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 | |
ML20063M313 | 21 April 1982 | Ro: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 | |
ML20084S863 | 30 January 1978 | Ro:On 780129,RCS Pressure Exceeded Tech Spec Limit by 60 Psig.Cause Not Stated.Rhr Pumps Restarted to Reduce Pressure | |
ML20084S883 | 26 August 1977 | Ro: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 | |
ML20084S890 | 15 August 1977 | Telecopy 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 | |
ML20084S904 | 7 June 1977 | Telecopy 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 | |
ML20084S921 | 26 January 1977 | Telecopy Ro:On 770125,flow Paths from Boric Acid Tanks Made Inoperable for Valve Repair | Boric Acid |
ML20086D260 | 1 December 1976 | RO: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 Replaced | 19 November 1976 | 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 Replaced | |
ML20086F406 | 17 November 1976 | Rept of Incidents/Occurrences for 760102-1117 | Boric 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 Isolated | 23 September 1976 | 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 Isolated | |
ML20086D339 | 18 August 1976 | Ro: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 | |
ML20086D362 | 6 August 1976 | Ro: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 | |
ML20086D402 | 2 April 1976 | Ro:On 760402,discovered That Boric Acid Heat Tracing Circuit 56 Had No Current Flow & Was Inoperative.Breaker Opened in Each Heat Trace Power Panels | Boric Acid |
ML20086D412 | 15 March 1976 | Ro: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 | |
ML20085D036 | 9 August 1973 | Ro: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 | |
ML20085D112 | 27 June 1973 | Ro:On 730620,during Test on Turbine Redundant Overspeed Trip Sys,Turbine Trip Inadvertently Initiated.Caused by Turbine Stop Valve Limit Switch Failure.Switch Adjusted | Overspeed trip |
ML20085D232 | 26 April 1973 | Ro: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 Area | Overexposure |
ML20085D224 | 24 April 1973 | Ro: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 | |
ML20085D317 | 9 February 1973 | Ro: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 | |
ML20085D263 | 30 November 1972 | Ro: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 | |
ML20085D399 | 10 November 1972 | Ro: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 a | Boric Acid |
ML20085D407 | 20 October 1972 | Telecopy 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 Concentration | Boric Acid |
ML20085D373 | 11 September 1972 | Ro:On 720726 Following Part Length Rod Control Sys Alarm, Frequency Sensor Relay Found Inoperable.Relay Replaced | |
ML20085D422 | 24 July 1972 | Ro: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 Tanks | Boric Acid |
ML20085D137 | 18 July 1972 | Ro:On 720709,steam Line Isolation Valve B Malfunctioned During Periodic Test.Caused by Sheared Pin in Linkage Between Valve Stem & Disc.Valve Repaired |