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	Issue date	Title	Topic
ML20084K167	25 October 1974	AO 50-237/1974-52:on 741018,during Run Mode,Recirculation Pump Suction Valve MO-2-0202-4B Failed to Close Completely. Caused by Open Torque Switch.Special Procedure Authorized to Bypass torque-limiting Switch
ML20084K202	10 October 1974	AO 50-237/1974-50:on 741004,during Shutdown,Safety Valve 2-203-4E Actuated Low.Caused by Valve Cold Pressure Set Using Nitrogen.Valve Replaced W/Valve Confirmed on Safety Valve Test Facility	Hydrostatic
ML20084K411	8 October 1974	AO 50-237/1974-49:on 740926,radioactivity in a Floor Drain Sample Tank Found Higher than Limit.Caused by Inability of Floor Drain Sys to Process Vol of Water Entering Sys.Max Recycle Radwaste Sys Under Const
ML20084K420	7 October 1974	AO 50-237/1974-48:on 740927,standby Gas Treatment Sys Train a Failed to Start on Spurious Initiation from Fuel Pool High Radiation Monitor.Caused by Faulty Sensor Converter. Converter Replaced
ML20084K431	31 October 1974	AO 50-237/1974-36:on 741023,control Rod Drive P-12 54-47 Became Uncoupled.Cause Undetermined.Control Rod Will Be Removed During Nest Refueling Outage	Overtravel
ML20084K458	17 October 1974	AO 50-237/1974-51:on 741006,during Shutdown,Zero Flow Indicated on Chimney Monitoring Sys.Caused by Gasket Failure for Glass Jar Muffler on Discharge Side of a Sample Pump Due to Deterrioration.A Sample Pump Replaced
ML20084K494	19 September 1974	Ao:On 740910,during Routine Surveillance,Operator Failed to Receive B Main Steam Line High Radiation Scram & Isolation Alarm.Caused by Operator Error.Time Delay Kit Will Be Installed.Operator Procedures Will Be Revised
ML20084K794	20 September 1974	AO 50-237/1974-46:on 740912,during steady-state Power,Leak Discovered in 2B Reactor Feed Pump Min Flow Line.Caused by Erosion of Min Flow Line Due to Leakage Past Normally Closed Min Flow Valve PCV-2-3201B.Patch Welded Over Leak
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

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