ML19309D802
| ML19309D802 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/16/1975 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19309D789 | List: |
| References | |
| NUDOCS 8004110678 | |
| Download: ML19309D802 (4) | |
Similar Documents at Arkansas Nuclear | |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19319E5481976-03-11011 March 1976
[Table view]AO 50-313/76-2:on 760301,discovered Pilot Cell Daily Voltage Readings for Station Batteries Not Taken for 760227-0301. Caused by Voltmeters Being Removed for Calibr & Reading Not Recognized as Tech Spec Surveillance Requirements ML19319E5361976-01-13013 January 1976 AO 50-313/75-11:on 751229,intermediate Cooling Water Sys Reactor Bldg Isolation Valve CV-2233 Failed to Close Remotely from Control Room.Caused by Operator Failing to Make Proper Valve Lineup Verification Per Standing Order 3 ML19319E5401976-01-13013 January 1976 AO 50-313/75-12:on 751229,svc Water Sys Valve CV-3821 to Decay Heat Cooler Failed to Automatically Open When Decay Heat Pump Started.Caused by Increase in Binding in Valve Packing or Seating Valve Hard Against Valve Seat ML19319E5471975-12-30030 December 1975 AO-50-313/75-10:on 751220,Group 6 Control Rods Ratchet Trip Occurred,Violating Tech Specs Group Overlap Requirement. Caused by Group 6 Power Supply Failure.Overlap re-established by Realigning Groups 5 & 6 ML19319E4321975-12-0505 December 1975 AO-50-313/75-9:on 751120,during Diesel Generator 2 Test,Oil Leak Developed at Oil Cooler Outlet Flange.Caused by O-ring Gasket Failure.Gasket Replaced & Diesel Generator 2 Tested to Verify Operability & Gasket Tightness ML19319E4571975-11-11011 November 1975 AO-50-313/75-8:on 751101,leak Found in Schedule 10,6 Inch Line from Borated Water Storage Tank to P36A Makeup Pump. Cause Unknown.Two Ft Spool Piece Removed from Affected Area & Replaced.Spool Piece to Receive Metallurgical Exam ML19326B6581975-10-31031 October 1975 AO 50-313/74-11C:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Cause Discussed in Encl Failure Analysis of Schedule 10S Piping Rept & Corrective Action in Encl Insp & Examination Program ML19320A1071975-10-0808 October 1975 AO 50-313/74-14:on 741228,pinhole Leak Found on Upstream Pipe to Valve Weld on RBV-77B.Caused by Temp Variables & Amount of Weld Matl.Weld Ground Out & Rewelded ML19326B6641975-08-29029 August 1975 AO 50-313/74-11B:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Caused by Intergranular stress-assisted Corrosion Cracking.Cracked Sections of Piping Replaced ML19309D8021975-07-16016 July 1975 AO 50-313/75-04:on 750707,makeup Pump P36C Tripped When Started During Normal Operation.Caused by Communications Failure Between Operators.Pump Inspected.Frozen Number 1 Impeller & Wear Ring Will Be Repaired ML19326B4001975-07-16016 July 1975 AO 50-313/74-08A:on 741003,initial Investigation Per AO 50-313/74-08 Revealed Thta Loss of Core Flood Tank Ref Leg Resulted from Evaporation.Investigation Found Evidence of Leakage on Ref Legs of Each Tank ML19319E4971975-07-16016 July 1975 Followup AO 50-313/75-1A:on 750120,water Outlet Es Valve CV-3814 Full Open Position Not Reached During Surveillance Testing.Caused by Galling of Metal Between Stem & Upper Bushing.Stem & Bushing Polished & Bushing Lubricated ML19309D7831975-07-0303 July 1975 AO 50-313/75-03:on 750620,180 Degree Visible Crack Found in Socket Weld on Upstream Side of Isolation Valve RBV-6510F. Caused Not Determined.Valve RBV-6510F Replaced ML19326B6921975-03-0404 March 1975 AO 50-313/74-12A:on 741109,PDT-1035,PDT-1037 & PDT-1039 Reactor Protection Sys Instrument Line Socket Welds Failed. Caused by Interdendritic Shrinkage Imperfections, Supplementing AO 50-313/74-12.Micrographs Encl ML19319E4541975-01-30030 January 1975 AO-50-313/75-2:on 750123,leak Found on Primary Makeup Pump P36C 1/2 Inch Casing Drain Line Near Casing Discharge Nozzle.Caused by Improper Fitup of Threaded Section of Casing Drain Line.Other Possible Causes Being Investigated ML19319E4991975-01-30030 January 1975 AO 50-313/75-1: on 750120,inlet Es Valve CV-3813 Failed to Open & Outlet Es Valve CV-3814 Failed to Reach Full Open Position.Caused by Operator Binding Due to Lubrication Lack. Valves Lubricated.Valve CV-3814 Will Be Inspected ML19326B6871975-01-22022 January 1975 AO 50-313/74-11A:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Caused by Intergranular stress-assisted Corrosion Cracks.Piping Partially Replaced.Pictorial Review of Cracks Encl ML19326B6591975-01-22022 January 1975 AO 50-313/74-10A:on 741025,metallurgical Analysis Revealed That Leak from Cold Leg of RCS (AO 50-313/74-10) Caused by Failure of Weld Metal Due to Fatigue Fracture.Weld Rewelded & Expansion Loop Added ML19320A1111974-12-28028 December 1974 AO 50-313/74-14:on 741228,pinhole Leak Found on Upstream Pipe to Valve Weld RBV-77B.Cause & Corrective Actions to Be Determined.No Hazard to Public Health & Safety ML19320A1001974-12-0303 December 1974 AO 50-313/74-13:on 741123,reactor Protection Sys Failed to See Coolant Pump Trips.Caused by Under/Overpower Monitoring Relay Maladjustment.Relays Bench Tested & Overpower Circuit Holding Coils Removed ML19326B3781974-11-27027 November 1974 AO-50-313/74-01A:on 740624,metallurgical Test of Cracked Weld on Decay Heat Removal Sys, (AO 50-313/74-02A) Revealed Fatigue as Failure Mode.Caused by Design & Installation Error.Flow Orifice Installed ML19320A1041974-11-25025 November 1974 AO 50-313/74-13:on 741123,reactor Monitor Sys Failed to See Coolant Pump Trips.Caused by Monitoring Relay Maladjustment. No Hazard to Health & Safety ML19320A1101974-11-24024 November 1974 AO 50-313/74-13:on 741123,reactor Protection Sys Failed to See Coolant Pump Trips.Caused by Pump Monitor Relay Maladjustment.Relays Immediately Adjusted ML19326B6941974-11-15015 November 1974 AO 50-313/74-11:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Cause Unknown.Spool Piece Will Be Removed for Replacement & Metallurgical Testing ML19320A0701974-11-15015 November 1974 AO 50-313/74-13:on 741115,fish Impingement on Intake Screens Totaled 3,196 Lbs.Disposal Means Other than Into Discharge Embayment Used ML19326B7041974-11-11011 November 1974 AO 50-313/74-12:leak Identified in Coupling to Tube Weld in Loop 2B RCS Flow Instrumentation Sensing Line.Three Pinhole Leaks Detected ML19326B3461974-11-10010 November 1974 AO 50-313/74-01:on 741109,leak Found in Weld Downstream of Root Valves on 2B RCS Loop Flow Instrumentation.Cause Unknown.No Hazard to Public Health & Safety ML19326B6651974-11-0404 November 1974 AO 50-313/74-10:on 741025,leak from Cold Leg Loop Weld of RCS Was Discovered & Determined to Be Same Weld Reported in AO 50-313/74-09.Cause Unknown.Weld Removed & Sent to B&W Lab for Analysis ML19326B3881974-10-25025 October 1974 AO 50-313/74-09:on 741017,leak Found on Cold Leg Drain Loop of Reactor Coolant Pump.Cause Unknown.Socket Weld Filler Matl Applied to Weld & Single Root Pass Made.Leak Test Performed;No Discrepancies Noted ML19326B4031974-10-0606 October 1974 AO 50-313/74-08:on 731003,following Reactor Turbine Trip Test,Discrepancies Occurred for Readings on Core Tank Level Indication.Caused by Ref Leg Tank Leakage.Cause of Leakage Unknown.Coolant Removed from Tank ML19326B4011974-08-21021 August 1974 AO-50-313/74-07:on 740812,B&W Identified Miscalibration on Reactor Coolant Flow Input to Reactor Protection Sys.Caused by Design Error.Procedures Revised to Correct Calibr Error & Bistables Recalibr ML19326B4111974-08-19019 August 1974 AO 500813/74-06:on 740811,reactor Protection Sys Channels A&D Tripped on High Flux During Pseudo Control Rod Ejection Test.Caused by Procedural Error.Procedure Changed & Emphasis Placed on in-limit Bypass ML19326B3251974-07-19019 July 1974 AO 50-313/74-05:on 740708,valve Leaks Found in Clean Liquid Radwaste & Makeup Sys.Caused by Casting Flaws.Valve Defect Being Investigated ML19326B3301974-07-16016 July 1974 AO 50-313/74-04:on 740706,primary Makeup Pump P-36A Radial Bearing Failed.Caused by Dislodged Mating Pins.Mating Pins Lengthened from 1/2 to 1 Inch & anti-rotation Pin in Sleeve Bearing Lengthened from 3/8 to 3/4 Inches ML19326B3381974-07-16016 July 1974 AO 50-313/74-03:on 740706,reactor Bldg Purge Control Isolation Valve CV-7402 Failed in mid-position During Surveillance Stroke Test.Caused by Rusted & Unlubricated Lower Bearing.Valve Operator Cleaned & Lubricated ML19326B5261974-07-13013 July 1974 AO 50-313/74-05:on 740713,during Initial Heatup Preparation, Valve Leaks Found in Clean Liquid Radwaste & Makeup & Clearification Sys.Caused to Be Determined.Valves Will Be Repaired or Replaced as Required ML19326B3331974-07-0808 July 1974 AO 50-313/74-04:on 740706,makeup Pump P-36A Stopped Due to Excessive Vibration.Cause Appears Bearing Oriented.Pump Will Be Inspected & Repaired as Required ML19326B3411974-07-0808 July 1974 AO 50-313/74-03:on 740706,reactor Bldg Control Purge Isolation Valve CV-7402 Failed in mid-position.Cause Appears to Be Binding in Operator.Valve Operators Will Be Disassembled,Inspected & Repaired as Required ML19326B6991974-07-0505 July 1974 AO 50-313/74-12:on 741109,PDT-1035,PDT-1037 & PDT-1039 Reactor Protection Sys Instrument Line Socket Welds Failed. Cause Unknown.Tube on Each Side of Socket Weld Coupling Replaced W/New Coupling.Metallurgical Test in Progress ML19326B3171974-07-0202 July 1974 AO 50-313/74-02:on 740626,crack Found in Decay Heat Sys Loop a Discharge Piping Near Coupling Weld at Vent Valve DH-1010. Caused by Extensively Ground & Slighty Undercut Base Metal. Pipe Replaced & Vent Valve Will Be Reinstalled ML19326B3191974-06-26026 June 1974 AO 50-313/74-02:on 740626,leak Found in Decay Heat a Sys Discharge Piping at Coupling Weld of Vent Valve DH-1010. Cause Metallurgical & Will Be Investigated.Defective Pipe Section Will Be Replaced ML19326B3131974-06-0505 June 1974 AO 50-313/74-01:on 740526,emergency Diesel Generator K4B Synchronized Through Breaker 152-408 & Tripped by Actuation of anti-motoring Relay.Caused by Incorrect tolerances.Anti- Motoring Relay Holding Coil Setting on K4B Adjusted ML19326B3141974-05-30030 May 1974 AO 50-313/74-01:on 740526,anti-motoring Trip Relay Problems Found in Emergency Diesel Generator K2B.Cause Unknown.No Safety Implications 1976-03-11 Category:TEXT-SAFETY REPORT MONTHYEARML20217L8931999-10-31031 October 1999
[Table view]Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs 05000313/LER-1999-313, :on 990911,AI of EFWS Occurred During Plant Shutdown as Result of Securing Running RCPs Due to Reverse Rotation of Idle Pump.Caused by Failure of Motor anti-rotation Device.Device Was Replaced.With1999-10-11011 October 1999
1999-09-09 |