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Issue date | Title | Topic | |
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ML20084K945 | 6 September 1974 | AO 50-237/1974-43:on 740901,during Run mode,2B Condensate Booster Pump Vent Line Found Ruptured.Caused by Pipe Nipple Coming Out of Casing Due to Vibration.Similar Nipples Will Be Replaced After hands-on Insp | |
ML20084L453 | 30 August 1974 | AO 50-237/1974-42:on 740824,during Snubber Insp,Eight Snubbers Found Low on Oil.Two Snubbers Leaked Upon Refilling.Cause Undetermined.Snubbers Will Be Disassembled | Earthquake |
ML20084L541 | 30 August 1974 | AO 50-237/1974-41:on 740823,during Shutdown Insp,Pin Hole Leak Discovered on 2B Reactor Feed Pump Min Flow Line to Condenser.Caused by Erosion in Min Flow Line.Line Weld Ground Out & Mod Initiated to Replace Line Section | |
ML20084L550 | 23 August 1974 | AO 50-237/1974-40:on 740815,during Routine Instrument Surveillance,Hpci Pressure Switches Ps 2389 a & B Found W/ Setpoints Out of Calibr.Caused by Setpoint Drift.Switches Reset.Switch Will Be Replaced | |
ML20084L564 | 16 August 1974 | AO 50-237/1974-39:on 740810,during Weekly Surveillance Testing,Control Valve Fast Acting Solenoid 1 Failed to Give one-half Scram Signal.Cause Undetermined.Power Reduced to 40%.Sys Being Monitored | |
ML20084L644 | 14 August 1974 | AO-50-237/1974-38:on 740805,torus Water Level Found to Be Below Specs.Caused by Mechanical Failure of Water Level Instrumentation.Sight Glasses for Verifying Torus Level Will Be Installed | |
ML20084L659 | 9 August 1974 | AO 50-237/1974-37:on 740801,during HPCI Testing,Valve 2-2301-35 Failed to Open.Caused by out-of-adjustment Breaker Contractors.Contractors Adjusted.Breaker Operated Satisfactorily | |
ML20084L700 | 9 August 1974 | AO 50-237/1974-36:on 740802,during Withdrawal of Control Rod Drive,Crd K-11(38-43) Went Into Overtravel Condition. Caused by Component Failure.Rod Inserted to Position 00, Electrically Disarmed & Removed from Svc | Overtravel |
ML20084L705 | 6 August 1974 | AO 50-237/1974-35:on 740730,during Cold shutdown,4-inch Crack Discovered in Feedwater Heater Drain Line 2-3508 A-10-L.Caused by Line Vibration.Crack Ground Out & Rewelded | Safe Shutdown |
ML20084L718 | 2 August 1974 | AO 50-237/1974-32,33 & 34:on 740724 & 29,primary Containment Failed Due to Leakage Through AO-2-1601-21 & 22 & Crack in Line 2-8503-8-LX.Caused by Liquid Nitrogen Reaching Both Valves.Valves & Line Repaired | |
ML20084L741 | 2 August 1974 | AO 50-237/1974-31:on 740726,excessive Leakage Found on Reactor Bldg to Torus Vacuum Breaker 2-1601-31A.Caused by Binding Between Disc & Disc Arm.Valve Will Be Modified During Next Refueling Outage | |
ML20084L761 | 2 August 1974 | AO 50-237/1974-30:on 740724,during Monthly Surveillance, Setpoint on HPCI Turbine Trip Pressure Switch Found High. Caused by Lack of Precycling of Switch Prior to Installation.Switch Reset | |
ML20084L767 | 31 July 1974 | AO 50-237/1974-24,25 & 26:on 740722,during Reactor Load Changes,Three Motor Operated Valves Failed to Operate When Given Open Signal from Control Room.Caused by Mounting Bolts That Vibrated Loose.Bolting Replaced | |
ML20084L776 | 25 July 1974 | AO 50-237/1974-29:during Routine Monthly Surveillance, Pressure Switch PS-504C Setpoint Found High.Caused by Instrument Calibr Drift.Switch Reset & Will Be Precycled Later in Yr | |
ML20084L780 | 26 July 1974 | AO 50-237/1974-28:during Routine Instrument Surveillance, Reactor Pressure 600 Psi Bypass Switch Observed to Operate at 604 Psi.Caused by Instrument Drift Due to Lack of Factory Precycling.Switch Reset & Will Be Recycled | |
ML20084L786 | 29 July 1974 | AO 50-237/1974-27:on 740720,during Routine Surveillance Testing of torus-to-drywell Vacuum Breakers,Valve 2-1601-33E Found Binding Open.Caused by Swelling of Teflon Bushings. Valve Willbe Remachined.Study Initiated | |
ML20084L799 | 24 June 1974 | Ao:On 740615,during Control Rod Withdrawal,Control Rod Drive L-9 Overtraveled to Uncoupled Position.Cause Unknown.Control Rod Will Be Removed During Next Extended Maint Outage | Shutdown Margin Overtravel |
ML20084L818 | 27 June 1974 | Ao:On 740620,floor Drain Sample Bank Discharged to Discharge Canal at Rate Which Resulted in Excessive Radioactivity. Caused by Failure to Follow Operating Order.Discharge Reduced | |
ML20084L840 | 19 June 1974 | Ao:On 740611,during Refueling,Reactor Pressure Switch PS-2-263-53C Found to Operate High.Caused by Lack of Precycling Prior to Installation.Switch Will Be Removed & Sent to Factory for Precycling | |
ML20084L874 | 6 June 1974 | Ao:On 740528,during Analysis of Waste Sample Tank A,High beta-gamma Radioactivity Concentration Determined.Condition Was Not Brought Into Compliance within 24 H.Caused by Damaged Filter Septa.Water Transferred to C Tank | |
ML20084L885 | 3 June 1974 | Ao:On 740527,diesel Generator 2/3 Failed to Acquire Full Load After Starting.Caused by Partially Plugged Oil Filter & Loose Butt Connection in Governor Raise Circuitry.Loose Connection Repaired | |
ML20084N646 | 31 March 1977 | Followup AO 50-249/75-44A:on 751125,offgas Activity Increased.Ge Insp Revealed Major Defect in Fuel Assembly DD-418.Assembly Removed from Reactor | Fuel cladding |
ML20084N654 | 11 December 1975 | AO 50-249/75-44:on 751125,offgas Increase Exhibited Which May Have Represented Abnormal Degradation of Fuel Cladding.Cause Unknown.Investigation Underway | Fuel cladding |
ML20084N671 | 7 October 1975 | AO 50-249/75-43:on 750927,leak Discovered in Drain Line from Feedwater Heater 3D3 to Heater 3C3.Caused by Poor Weld Installation of Drain Line Pipe Support.Crack Ground Out & Pipe Rewelded | |
ML20084N683 | 29 June 1976 | Supplemental AO 50-249/1975-42A:motor Operated Valve 3-1501-5D Failed to Open During Testing Due to Thermal Overload Trip.Caused by Undersized Overload Heaters.Overload Heater Will Be Replaced W/Larger Capacity Unit | |
ML20084N688 | 20 October 1975 | AO 50-249/75-42:on 750920,motor Operated LPCI Suction Valve 3-1501-5D Failed to Open Twice During Testing. Apparently Caused by Defective Valve Motor.Valve Motor Will Be Replaced | |
ML20084N691 | 16 September 1975 | AO 50-249/75-41:on 750908,intermediate Range Monitors 11, 12,14,16 & 18 Failed to Respond During Plant Startup. Apparently Caused by Personnel Accidentally Loosening Cables.Cables Replaced | |
ML20084N728 | 4 September 1975 | AO 50-249/75-40:on 750827,during Routine Instrument Surveillance,Pressure Switches PS3-263-51A & 51B Had Setpoints Above Tech Spec Limit.Caused by Drifting Due to Long Periods at Zero Pressure.Switches Reset | |
ML20084N748 | 3 September 1975 | AO 50-249/75-39:on 750826,overload Relay Tripped Twice on Motor Operated Isolation Valve 3-220-1.Caused by Defective Overload Relay.Relay Replaced | |
ML20084N774 | 20 June 1975 | Followup to AO Rept Re Correlation of Fuel Failures, Identified by Wet Sipping Tests to Calcualted Violations of GE Pciomr | |
ML20084N777 | 4 September 1975 | AO 50-249/75-38:on 750826,pressure Switches 3-263-52A1 & 52A2 Found W/Setpoints Above Tech Spec Limit.Apparently Caused by Setpoint Drift Due to Long Periods of Inactivity. Switches Reset | |
ML20084N794 | 2 September 1975 | AO 50-249/75-36:on 750823,reactor High Pressure Sensors 263-55A,55B & 55C Found W/Setpoints Above Tech Spec Limit. Apparently Caused by Extended Periods at Zero Pressure. Switches Reset | |
ML20084N833 | 15 October 1975 | Supplemental AO 50-249/75-22:plant Mod Being Initiated to Eliminate Valve Seat Failures Due to Cryogenic Stress | Packing leak |
ML20084N841 | 4 September 1975 | AO 50-249/75-37:on 750826,pressure Switches PS3-263-53A,53B & 53C Had Setpoints Above Tech Spec Limit.Apparently Caused by Setpoint Drift Due to Long Periods at Zero Pressure. Setpoints Reset | |
ML20084N866 | 29 August 1975 | AO 50-249/75-35:on 750821,circuit Breaker 152-3403 Failed to Trip During Breaker Trip Test.Caused by Failure of Trip Coil.Breaker Replaced | |
ML20084N882 | 15 August 1975 | AO 50-249/75-34:on 750807,isolation Condenser High Flow Switches 1349A & B Exhibited Instrument Setpoint Drift.Cause Unknown.Switches Reset | |
ML20084N905 | 31 July 1975 | AO 50-249/75-32:on 750721,clamp Bolt Keeper Tack Welds on Jet Pumps 6 & 17 Failed.Caused by Poor Tack Welding.Clamp Bolt Keepers Rewelded & Successfully Retested | |
ML20084N914 | 3 July 1975 | AO 50-249/1975-31:on 750626,cracks Discovered on Collet Housings of Control Rod Drives 984,883,1032 & 1099. Apparently Caused by Temp Cycles Drive Experiences During Reactor Scram.Analyses Initiated | |
ML20084N975 | 13 June 1975 | AO 50-249/1975-30:on 750605,standby Liquid Control Pump Discharge Relief Valves Found at Setpoints Lower than Tech Spec Limits.Caused by Setpoint Drift.Valves Cleaned & Reset | |
ML20084R434 | 25 April 1975 | AO 50-249/75-19:on 750416,leak Test Line to Bellows Seal for Drywell Penetration X-105D Discovered Broken Off.Caused by Personnel Using Penetration to Stand on While Conducting Maint in X-area.Tubing Replaced & Satisfactorily Tested | |
ML20084R479 | 27 March 1975 | AO 50-249/75-17:on 750318,main Steam Line High Radiation Monitor 1705-2A Setpoint Above Tech Spec Limit.Caused by Lack of Conservatism in Setpoint Valve.Monitor Trip Point a & B Reset | |
ML20084R488 | 27 March 1975 | AO 50-249/75-16:on 750316,during Control Rod Drive Scram Testing Surveillance,Control Rod Drive Scram Times Failed to Meet Limiting Condition for Operation Per Tech Specs.Caused by Deterioration of Drive Seals.Control Rod Drive Retested | |
ML20084R517 | 20 March 1975 | AO 50-249/75-15:on 750310,during Routine Surveillance of Pressure Switch PS3-263-52A-2,setpoint Found Below Tech Spec Limits.Caused by Inherent Setpoint Drift.Switch Trip Point Reset | |
ML20084R535 | 18 March 1975 | AO 50-249/75-14:on 750310,operator Heard Air Blowing Inside Diesel Generator Which Revealed Air Receiving Tank Outlet Valves Closed & Generator Inoperable.Caused by Personnel Error.Operability Check Changed | |
ML20084R577 | 12 March 1975 | AO 50-249/75-13:on 750302,control Rod Drive Scram Times Failed to Meet Limiting Condition for Operation Per Tech Specs.Caused by Deterioration of Drive Seals.Five Questionable Drives Scheduled for Retesting | |
ML20084R586 | 7 March 1975 | AO 50-249/75-09:on 750228,during MSIV Not Full Open Scram Test,Relay 590-102B Failed to Deenergize.Apparently Caused by Faulty Limit Switch on 3-203-2A Msiv.Fuse 590-702B Removed,Placing Sys in Fail Safe Condition | |
ML20084R602 | 27 February 1975 | AO 50-249/75-08:on 750218,during Routine Calibr of Level Switch LIS 3-263-57B,setpoint Found Above Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Tested for Repeatability & Performed within Manufacturer Limits | |
ML20084R645 | 17 January 1975 | RO 50-249/75-04:on 750107,pin Hole Leak Discovered in Reactor Feed Pump 3B Min Flow Line to Condenser.Caused by Swirl Being Created by Velocity Change Through off-set Reducer.Failed Section of Pipe Isolated & Repaired | |
ML20084R723 | 9 January 1975 | AO 50-249/75-02:on 750103,concentration of Chloride Ions in Reactor Coolant Determined Above Limiting Condition for Operation,Per Tech Specs.Caused by Inoperability of Reactor Coolant Cleanup Sys.Shutdowm Immediately Initiated | |
ML20084R737 | 7 January 1975 | Telecopy Ao:On 750107,during Control Rod Pattern Alteration, Xexon Transient Experienced.Apparently Caused by Fuel Clad Failure in Lower Region of Core |