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ML20199F65014 November 1997Special Rept:On 971031,one High Range Primary Containment Radiation Monitor Declared Inoperable for More than Seven Days.Caused by Component/Equipment Failure Inside Drywell. Will Repair or Replace Detector or Associated Cable
ML20207K9247 October 1988RO 88-01:on 880725,during Inventory of Snm,Discrepancy Noted for Intermediate Range Monitor Detector Removed from Core Location C.Caused by Inadequage SNM Control & Accountability Practices Existing at Time of Installation & Shipment
ML20235J4542 July 1987Special Rept 87-01,Rev 1:on 870321,three Seismic Triggers Would Not Provide Required Control Room Annunciation Upon Receipt of Horizontal 0.1 G Seismic Acceleration.All Instruments Removed from Site Repaired.Instructions Revised
ML20117N7508 May 1985Advises That Rept Will Not Be Prepared for RO BFRO-50-296/85011
ML20086G5973 January 1984Telecopy RO 50-259/83073:on 831231,reactor Water Sample Indicated Chloride Concentration of 525 Ppb.Steam Flow Greater than 100,000 Lbm/H.Caused by Possible Resin Intrusion.Investigation in Progress
ML20083E15515 December 1983Telecopy RO 50-296-83060:on 831214,nine of 13 two-stage Relief Valves Tested Initially Failed to Lift within Allowable Range.Cause Being Evaluated W/Manufacturer.Nine Valves Will Be Reset & Retested Prior to Installation
ML20082V34112 December 1983Telecopy RO 50-259/83068:on 831210,RHR Pump 1C Motor Sparked & Smoked.Motor Shut Down & Restarted,Then Tripped on Overcurrent.Pump Declared Inoperable.Caused by Winding Failure.Motor Will Be Replaced
ML20083A4308 December 1983Telecopy Ro:On 831207,linear Crack Indication Identified by NDE in Weld DSHS-3-2 of Head Spray Piping of RHR Sys. Apparently Caused by Intergranular Stress Corrosion Cracking.Insp Per IE Bulletin 83-02 Will Be Performed
ML20082D02514 November 1983Telecopy Ro:On 831110,HPCI Isolated Due to Failure of Exhaust Rupture Disc.Cause Unknown.Maint Request Issued to Replace Disc.Investigation Continuing
ML20078M97814 October 1983Telecopy Ro:On 831013,routine Analysis of 831007 Scram Revealed That 2-LT-85-45A Did Not Initiate Trip When SDIV Exceeded 50 Gallons.On 831014,testing of Transmitter Revealed Slow & Erratic Response to Measured Variable
ML20078H3286 October 1983Telecopy RO 83061:on 831004,hydrogen-oxygen Analyzer Sample Pump B Determined Inoperable Following Notification from Metal Bellows Corp of Generic Deficiency.Pump Replaced W/ Upgraded Model in Stock on 831005
ML20080L89620 September 1983Telecopy Ro:On 830919,Surveillance 4.7.A.2.G3 Determined Leakage Rates Exceeded for MSIV Lines A,C & D.Caused by Leakage Past Main Valve Seat.Seating Surfaces Modified
ML20076J58428 August 1983Telecopy Ro:On 830826,cracks Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Total Welds to Be Inspected Increased from 53 to 79.Updated Insp Results Encl
ML20076J74525 August 1983Telecopy RO BFRO-50-259/83049 R9:on 830825,weld Crack Indications Discovered in Welds on Core Spray & Reactor Water Cleanup.Number of Welds to Be Inspected Increased from 53 to 79
ML20076F33523 August 1983Telecopy RO 50-259/83-49:on 830811,pipe Weld Cracking Indications Revealed by Addl Ultrasonic Insps.Possibly Caused by Corrosion.Addl Welds Inspected.Insp Repts to Be Submitted Periodically
ML20080D69222 August 1983Telecopy RO 83049R7:on 830812,indications Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Addl 29 Welds Will Be Inspected.Insp Results Encl
ML20080E07722 August 1983Telecopy Ro:On 830812,cracks Found on Welds DCS-1-7, DSRWC-1-3,DCS-1-8 & DSRWC-1-2.Cause Not Stated.Total Number of Welds to Be Inspected Increased from 53 to 79
ML20080D57218 August 1983Telecopy Ro:On 830812,weld Cracks Discovered in Core Spray & Reactor Water Cleanup Sys.Addl 29 Welds Will Be Inspected. Insp Results Encl
ML20076F69117 August 1983Telecopy Ro:On 830812,indications Found on Pipe Welds for Core Spray & Reactor Water Cleanup.Addl 29 Welds Will Be Inspected Increasing Total Number of Welds to Be Inspected to 82
ML20076F86415 August 1983Telecopy Ro:On 830815,indications Identified on Welds DCS-1-7,DSRWC-1-3,DCS-1-8 & DSRWC-1-2.Weld Insp Results Encl
ML20076F52115 August 1983Telecopy Ro:On 830812,core Spray Weld DCS-1-7 Had Intermittent Indication on Pipe Side of Weld Approx 41% Through Wall Depth.Reactor Water Cleanup Weld DSRWC-1-3 Had Two Indications Approx 5 Inches Long
ML20076F53512 August 1983Telecopy Ro:On 830812,during Routine Surveillance Testing, Four of Four Turbine first-stage Permissive Switches Discovered Out of Tech Spec Limits.Caused by Setpoint Drift. Setpoints Reset
ML20077A03412 July 1983Supplemental Ro:On 830604,13,14 & 15 Standby Gas Treatment Train B Declared Inoperable.Caused by Increased Damper Closure Since Measurements Made in May 1983.Dampers Returned to Preset Position
ML20077A2796 July 1983Telecopy RO 50-259/83036:on 830705,seven two-stage Target Rock Relief Valves Tested at Wyle Labs for as-found Set Pressure Failed to Lift within Allowable Range.Caused Under Evaluation.Valves Will Be Reset & Retested
ML20071N44624 May 1983Telecopy RO 50-286/8331:on 830520,reactor Low Pressure Switches PS-3-74B & PS-68-96,switch 2 Found Below Tech Spec Limits.Caused by Setpoint Drift.Setpoints Reset & Design Change Request DCR 1398 Initiated to Replace Switches
ML20071H58018 May 1983Telecopy RO 50-259/83024:on 830517,design Review of Emergency Diesel Generator Room Ventilation Sys Capabilities Revealed Design Temp Limits of Some Electrical Components May Be Exceeded.Caused by Error in Heat Dissipation Data
ML20069M45525 April 1983Telecopy RO 50-259/83021:on 830424,130 Fuel Bundles Unloaded from Core & Placed in High Density Fuel Storage Rack in Spent Fuel Storage Pool Not Tested for Boron Concentration. Caused by Inadequate Procedures
ML20069L33620 April 1983Telecopy RO 50-296/83024:on 830419,review of Licensing Documents Revealed Lead Test Assemblies Could Reach Max of 18.8 Kw/Ft in Event of Rod Withdrawal Error.Caused by Error in Preparation & Review of GE Licensing Documents
ML20069K73718 April 1983Telecopy RO 50-259/83020:on 830418,leakage Rate for Line a MSIV Found Above Tech Spec Limit.Caused by Leakage Past Main Valve Seat.Corrective Maint & long-term Mod Planned
ML20064N9859 February 1983Telecopy Message of RO 50-260-8302:on 830208,pressure Switches PS-68-96,PS-3-74A & PS-3-74B Found Out of Tech Spec Limits During Performance of Surveillance Instruction 4.2.B-7.Caused by Setpoint Drift.Switches Recalibr
ML20064L2568 February 1983Telecopy Ro:On 830207,reactor Low Water Level Switches Found Out of Tolerance.Caused by Instrument Drift.Switches Recalibr,Tested & Returned to Svc.Switches Will Be Replaced W/Analog Transmitter/Trip Unit Sys at Later Date
ML20064M1467 February 1983Telecopy Message of RO 50-259/83006:on 830205,relief Valve PCV 1-22 Failed to Reseat Fully After Actuation to Control Reactor Pressure.Probably Caused by Excessive Leakage of Pilot Valve.Pilot Valve & Solenoid Actuator Replaced
ML20062K3023 December 1980RO 50-259/8085:on 801123 Reservoir Water Temp Exceeded Max Allowable Temp.Caused by Influence of Colder Water Upstream.Load on Unit 3 Reduced in Four Stages to Shutdown & Water Flows Increased
ML20064K34629 October 1980Ro:On 801029,HPCI Removed from Svc Due to Ground Occurring on Gland Seal Condensor Pump Motor.Cause Attributed to Moisture Found in Pump.Hpci Was Returned to Svc
ML20204B85014 September 1978RO 50-259/7827:on 780913,recirculation Loop a Flow Decreased from 41,000 to 33,000 Cpm W/Corresponding Increase in Pump Delta F.Caused by Valve Stem Separating from Valve Disc
ML20084T91321 September 1976Telecopy RO BFRO-50-259/7615:on 760921,HPCI & RCIC Failed Test.Reactor Shutdown Effected & Pressure Reduced to 100 Psi
ML20084T89321 September 1976Telecopy RO BFRO-50-259/7617:on 760921,prescribed Rate of Reactor Coolant Change During Normal Heatup Exceeded When Averaged Over 1 H Period
ML20084U3217 September 1976Telecopy RO BFRO-50-260/7610:on 760906,out-of-sequence Control Rod Withdrawn.Cause Not Stated
ML20084U26928 July 1976Telecopied RO BFRO-50-296/762T:on 760728,during Surveillance Testing,Control Rod Accumulators Found Discharged W/O Control Rod Drive Electrically Disarmed.Cause Not Stated
ML20084U3529 July 1976Telecopy RO BFRO-50-260/768T:on 760709,unit Scrammed Due to Loss of Neutron Monitoring Battery 2A.Cause Not Stated
ML20084U45419 June 1976Telecopied RO BFRO-50-260/765T:on 760619,water Supply Valves 85-612 & 85-615 to Hydraulic Control Unit 30-32 Found Closed.No Cause Stated.Valves Opened
ML20085E9534 July 1975Telecopy Message of Ro:On 750703,facility Became Inoperable Due to Governor Problems.Manual Operation Possible.Lee Gas Turbine Could Not Be Tied in Through Isolated Line to Supply & Buy Power.Investigation Continuing
ML20085F70011 March 1975Telecopy RO BFAO-50-259/754T:on 750311,drywell Atmosphere Above Permissible Oxygen Concentration.Cause Not Stated
ML20085F79027 February 1975Telecopy RO BFAO-50-259/753T:on 750226,pressure Relief Valve PCVI-4 Prematurely Lifted & Failed to Reseat Until Pressure Reached 480 Psig.Reactor in Cold Shutdown Condition for Valve Replacement.Cause Not Stated
ML20085G09019 January 1975Telecopy Ro:On 750119,pressure Relief Valve PCV-1-4 Operated Several Times W/No Appreciable Blowdown.Unit in Cold Shutdown for Investigation & Possible Repair
ML20085G1017 January 1975Telecopy RO BFAO-50-260/751T:on 750107,RCIC Failed to Operate Following Planned full-load Trip
ML20085G61427 December 1974Telecopy RO BFAO-50-259/7461T:on 741227,proper Documentation Not Issued Prior to Installation of Dampening Pin for Main Steam Line high-flow Pressure Switch Snubbers.Cause Not Stated
ML20085G62825 December 1974Telecopy Ro:On 741224,both Channels of Offgas Radiation Monitor Taken Out of Svc to Repair Leaking Flow Indicator. Cause Not Stated
ML20085G18019 December 1974Telecopy RO BFAO-50-260/7436T:on 741218,drywell Air Sampling Monitor Failed.Cause Not Stated
ML20085G25618 December 1974Telecopy RO BFAO-50-260/7435T:on 741218,RHR Valve 2-FCV-74-66 Closed During Routine Surveillance Testing & Could Not Be Opened.Cause Not Stated
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