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{{#ask: [[Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)]] [[Site::Oyster Creek||05000000]]
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{
    "query_string": "[[Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER &amp; RO)]] [[Site::Oyster Creek||05000000]]",
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	Issue date	Title	Topic
ML19291C264	8 September 1975	AO 73-19:when Closing Signal Was Applied to Breaker S1A,loss of Power Occurred at 4160-volt Ac Bus 1A Causing Trip of Various Pumps.Caused by Incorrect Setting of Current Transformer Ratio Matching Taps.Taps Set Properly
ML19291C282	15 March 1974	AO 50-219/74/17:on 740307,during Transfer of Power from Auxiliary to Startup Transformer,Closing Switch for Breaker S1B Would Not Operate.Caused by Component Failure of Closing Spring Not Being in Charged Position
ML19343C218	23 December 1975	AO 50-219/75-33:on 751212,during 6-month Load Test on Station a batteries,125 Volt Dc Distribution Ctr de-energized.Caused by Personnel Error in Following Procedure.Distribution Ctr re-energized
ML19343C219	11 December 1975	AO 50-219/75-32:on 751203,during Testing,Emergency Diesel Generator 1 Failed to Start When Simulated Loss of Power Condition Applied to Fast Start Logic Circuit.Caused by Failure of Relay to Operate Due to Varnish on Armature
ML19343C220	26 July 1974	AO 50-219/74/41:on 740719,main Steam Line Low Pressure Switches RE23C & D Tripped at Pressures Less That Min Required Value of 860 Psig.Caused by Lack of Setpoint Tolerances.Setpoint Accuracy & Tolerance Being Investigated	Fuel cladding
ML19343C221	25 July 1974	AO 50-219/74/42:on 740725,main Steam Line Low Pressure Switches RE23A,B,C & D Tripped at Pressures Less than Min Required Value of 860 Psig.Caused by Switch Repeatability. Setpoint Accuracy & Tolerance Under Investigation	Fuel cladding
ML19343C222	24 July 1974	AO 50-219/74/40:on 740715,insp Located Inoperable Bergen- Paterson Hydraulic Shock & Sway Arrestor on South Core Spray Sys in Drywell.Caused by Loss of Hydraulic Fluid Due to Burns on Main Control Rod.Units Replaced	Earthquake
ML19343C223	23 July 1974	AO 50-219/74/39:on 740714,electromatic Relief Valve Pressure Switches 1A83A,1A83B,1A83C & 1A83E Tripped at Pressures in Excess of Max Allowable Value of 1,070 Psig.Caused by Lack of Allowance for Setpoint Tolerances in Tech Specs
ML19343C224	19 July 1974	AO 50-219/74/37:on 740712,main Steam Line Low Pressure Switches RE23A,B,C & D Tripped at Pressures Less than Min Required Value of 860 Psig.Caused by Switch Repeatability. Setpoint Accuracy & Tolerance Under Investigation	Fuel cladding
ML19343C225	15 July 1974	AO 50-219/74/35:on 740705,main Steam Line Low Pressure Switches RE23B,C & D Tripped at Pressure Less than Min Required Value of 860 Psig.Caused by Switch Repeatability. GE Requested to Investigate Feasibility of Tech Specs Mod	Fuel cladding
ML19343C226	11 July 1974	Addendum to AO 50-219/74/28 Dtd 740426:on 740419,motor- Operated Valve V-20-4 Failed to Open Electrically After Closing Electrically.Caused by Premature Opening of Position Switch 20-C.Position Switch Readjusted
ML19343C229	7 June 1974	AO 50-219/74/34:on 740529,coolant Leakage Found in Area of Incore Flux Monitor Reactor Vessel Housing at Core Coordinate 28-05.Cause Undetermined.Insp Program Developed to Examine Incore Flux Monitor Tube from Below Vessel	Hydrostatic
ML19343C351	31 May 1974	AO 50-219/74/32:on 740521,relay 16K114D in Sys 2 Core Spray Booster Pump Initiation Logic Found in Energized Position. Caused by Failed Core Spray Booster Pressure Switch RV40D. Relay Placed in de-energized Position by Valving Out Switch
ML19343C352	1 May 1974	AO 50-219/74-28:on 740423,suction Valve V-20-4 to B Core Spray Pump Stuck in Closed Position for 15 Minutes,Causing Loss of Core Spray Redundancy in Sys 2.Cause Undetermined. Valve Manually Closed & Circuit Breaker Tagged Open
ML19343C353	31 May 1974	AO 50-219/74/33:on 740521,auto-depressurization Sys Initiation Timers 16M23A & 16M232B Failed to Complete Timing Cycle in Less than Two Minutes.Cause Under Investigation. Timers Reset & Timed Out in Less than Two Minutes
ML19343C354	29 May 1974	AO 50-219/74/31:on 740519,Bergen-Paterson Hydraulic Shock & Sway Arrestor Located on South Core Spray Sys Found Inoperable.Caused by Loss of Hydraulic Fluid.Units Replaced W/Units Equipped W/Emergency Preparedness Seals	Design basis earthquake
ML19343C355	23 May 1974	AO 50-219/74/30:on 740514,pressure Switch PSH-C Failed to Trip at Nominal Trip Pressure of 180 Psig.Cause Under Investigation.Switch Recalibr & Tested Satisfactorily
ML19347C795	29 January 1974	AO 50-219/74/8:on 740117,isolation Condenser Sys Initiation Time Delay Switch Failed to Close within Tech Specs Time Limit After High Reactor Pressure Reached.Caused by Instrument Drift.Research Initiated to Clarify Requirements
ML19347C796	28 January 1974	AO 50-219/74/7:on 740123,during Monthly Surveillance Test, Reactor High Pressure Sensor RE03D Failed to Trip at Point Corresponding to Reactor Pressure of 1,060 Psig.Caused by Design Error.Pressure Sensor Recalibr & Returned to Svc
ML19347C797	28 January 1974	AO 50-219/74/6:on 740122,24-h After Placing Mode Selector Switch Into Run,Torus Atmosphere Contained 6.2% Dioxide in Excess of Tech Specs Limit of 5.0%.Caused by Operator Error & Late Nitrogen Truck Delivery
ML19347C798	25 January 1974	AO 50-219/74/8:on 740117,during Surveillance Test,Isolation Condenser Sys Initiation Switches Time Delays Failed to Close within Tech Specs Limt of 15-s.Caused by Design Error & Instrument Drift.Plant Committee Reviewing Occurrence
ML19347C799	25 January 1974	AO 50-219/74/5:on 740116,MSIV NS04A Failed to Meet Allowable Leakage Requirement.Caused by Failure of Packing Ground Valve Shaft.Valve Shaft Repacked & Valve Retested Successfully
ML19347C800	25 January 1974	AO 50-219/74/4:on 740116,while Reactor Shut Down for Maint Work W/Mode Switch in Refuel,Msiv NS03B Failed to Close on Manual Signal.Caused by Pilot Valve Design & Oxide Residue on Valve Spools & Sleeves	Overtravel
ML19347C801	24 January 1974	AO 50-219/74/3:on 740113,during Insp of Bergen-Paterson HSSA-10 Units in Primary Containment Hydraulic Shock & Sway Arrestors Found Devoid of Fluid.Cause Under Study.Units Replaced W/Units Rebuilt W/Ethylene Propylene Seal Matl
ML19347C802	23 January 1974	AO 50-219/74/6:on 740122,24-h After Placing Mode Selector Switch Into Run,Torus Atmosphere Contained 6.2% Dioxide in Excess of Tech Specs.Caused by Operator Error & Late Nitrogen Truck Delivery.Corrective Actions Being Studied
ML19347C803	7 January 1974	Ao:On 731218-20,test Spool Valve for MSIV NS04A Failed to Properly Reset & Experienced Pressure Transients During & After 5% Closure Test.Caused by Faulty Operation of Test Valve & Improper Valve Resetting	Overtravel
ML19347C804	14 January 1974	AO 50-219/74/3:on 740113,during Insp of Bergen-Paterson HSSA-10 Units Primary Containment Hydraulic Shock & Sway Arrestors Found Devoid of Fluid.Cause Under Study.Units to Be Replaced W/Units Rebuilt W/Ethylene Propylene Seal Matl
ML19347C806	14 January 1974	AO 50-219/74/1:on 740104,low Pressure Main Steam Line Pressure Switch Trip Setpoint of 850 Psig Determined Incorrect & in Violation of Tech Specs.Caused by Design, Procedure & Unusual Svc Condition	Fuel cladding
ML19347C807	6 December 1973	AO 73-30:on 731206,main Steam Line Low Pressure Switches RE23A Through RE23D Tripped at Pressure Below Min Setpoint of 850 Psig.Cause Undetermined.Switches Reset.Mfg Conducting Study W/Ge to Investigate Setpoint Drift	Fuel cladding
ML19347C808	9 January 1974	Ao:On 731227,during Quarterly Calibr Test of Main Steam Line High Radiation monitors,RN05A Log Count Rate Monitor Failed to Trip at Normal Setpoint of 1,000 Cps.Caused by Cold Soldered Connection in High Alarm Trip Section of Assembly	Half scram
ML19347C809	9 January 1974	AO 50-219/74/2:on 740108,RE22C & RE22E Main Steam Line High Flow Sensors Actuated Above Max Allowable Tech Specs Pressure Levels.Cause Being Investigated.Sensors Recalibr & Returned to Svc as Failures Discovered
ML19347C810	4 January 1974	Ao:On 731221,four Isolation Condenser High Flow Sensors Failed to Trip on Delta P Values During Surveillance Testing Due to Setpoint Drift.Cause of Setpoint Drift Investigated. Sensors Reset & Procedures Reviewed
ML19347C811	3 January 1974	Ao:On 731220,3,400 Gallons of Contaminated Radioactive Chromated Water Spilled.Caused by Crack in Drain Line Due to Severely Cold Weather.Contaminated Water Pumped Into Ground Containers.Shallow Wells Being Drilled for Analyses
ML19347C812	2 January 1974	Ao:On 731125,during Reactor Cooldown Operation,Unexplained Isolation of Isolation Condenser B Occurred.Caused by Slow Instrument Response Due to Defective Snubbers.Snubbers Replaced & Pressure Decay Tests Established
ML19347C813	24 December 1973	Ao:On 731206,Meletron Corp Model 372,main Steam Line Low Pressure Switches RE23A Through RE23D Found to Trip at Pressure Below Min Required Setpoint of 850 Psig.Cause of Setpoint Drift Under Study.Switches Reset	Fuel cladding
ML19347C814	24 December 1973	Ao:On 731213,momentary Interruption of 125 Volt Power Supplying Instrumentation to Panel E Safeguard Sys Occurred. Caused by Improper Placement of Jumper Used to Parallel a & B Distribution Buses.Automatic Reset Function Restored Svc
ML19347C815	20 December 1973	Ao:On 731121,relay 6K43 de-energized When Smoke Observed Emanating from Panel 10F Control Room.Cause Undetermined. Relay 6K43 Removed for Testing.New Relay of Higher Voltage Installed.Further Action Considered Based Upon Insp Results
ML19347C816	13 November 1973	Ao:During Insp of Bergen-Paterson HSSA-10 Units on Steam Line B Isolation Condenser NE01B,hydraulic Shock & Sway Arrestors Found Devoid of Fluid.Cause Under Study.Units Will Be Replaced W/Units Rebuilt W/Ethylene Propylene Seal Matl	Earthquake
ML19347C817	8 November 1973	Ao:On 730914,leakage Occurred from Reactor Bldg Closed Cooling Water Sys to Discharge Canal Via Svc Water Sys. Caused by Leaking Tubes in Reactor Bldg Closed Cooling Water Heat Exchanger 1-2.Investigation Continuing
ML19347C818	16 October 1973	AO 73-26:on 731010,average Power Range Monitor Scram & Rod Block Setpoints Not Set to Conservative Values Specified in Tech Specs.Caused by Personnel Error.Procedures Will Be Reviewed W/Personnel
ML19347C819	12 October 1973	Ao:On 730928,MSIV,NS04A & NS04B Failed to Meet Allowable Leakage Requirement.Caused by Failure of Valve Stem Packing. MSIV Repacked & Tested Satisfactorily
ML19347C820	9 October 1973	Ao:On 730929,during Surveillance Test on Reactor High Pressure Isolation Condenser Initiation Switches,Contacts on Agastat Relay 6K12 Failed to Close within Preset Time Delay of 15-s.Cause Unknown.Relay 6K12 Replaced W/New Relay
ML19347C821	21 September 1973	Ao:On 730908,during Leakage Rate Test MSIV NS03B Failed to Meet Acceptable Leakage Rate Criterion Per Tech Specs.Cause Unknown.New Procedures Established Before & After Disassembly of NS03B.Analysis Continuing
ML19347C822	21 September 1973	Ao:On 730908,plant Shut Down to Inspect Hydraulic Shock & Sway Arrestors on Piping Sys in Drywell Bldg.Insp Revealed 23 Failed Arrestors.Caused by Loss of Hydraulic Fluid from Failed Millable Gum Polyurethane Seals	Earthquake
ML19347C823	18 September 1973	Ao:On 730908,1A 4,160 Volt Ac Bus Lost Power Causing Two Circulating Water Pumps,Three Reactor Recirculation Pumps, & Operating Condensate & Feedwater Pumps to Trip.Caused by Improper Tap Setting of Transformer Ratio on C Relay
ML19347C824	18 September 1973	Ao:On 730910,isolation Condenser NE01A Condensate Return Valve V-14-34 Failed to Operate During Plant Cooldown.Cause Not Stated.Overloads Found Tripped Were Reset & New Overloads Installed.Weekly Surveillance Test Initiated
ML19347C825	10 September 1973	AO 73-22:on 730909,MSIV NS03B Tested for Leakage & Found to Exceed Tech Specs Limit.Cause Unknown.Prior to Disassembly of Valve,Stem Measurements Taken on All Valves to Check Conformity
ML19347C826	10 September 1973	AO 73-21:on 730908,during Plant shutdown,21 Hydraulic Shock & Sway Arrestors in Piping Sys in Drywell Found Failed. Caused by Loss of Hydraulic Fluid.Failed Snubbers Replaced W/Snubbers Rebuilt w/Bergen-Paterson Seal Kits	Earthquake
ML19347C827	10 September 1973	AO 73-20:on 730909,isolation Condenser NE01A Condensate Return Valve V-14-34 Failed to Operate During Last Stages of Plant Cooldown.Caused by Tripped Overloads on Starting Contactor.Overloads Reset
ML19347D308	3 October 1973	Ao:On 730924,during Surveillance Testing,Differential Pressure Switch DPS66A Failed to Trip.Caused by Excess Friction in Linkage Pivots.Switch Removed,Disassembled & Cleaned

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