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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
ML20084C916	2 August 1974	AO 50-219/74/42:on 740725,main Steam Line Low Pressure Switches RE23A,B,C & D Found to Trip at Pressures Less than Min of 860 Psig.Caused by Switch Repeatability.Setpoint Accuracy & Tolerence Under Investigation	Fuel cladding
ML20084C917	26 July 1974	AO 50-219/74/41:on 740719,main Steam Line Low Pressure Switches RE23C & D Found to Trip at Pressures Less than Min of 860 Psig.Caused by Lack of Setpoint Tolerances in Tech Specs.Setpoint Accuracy & Tolerance Under Investigation	Fuel cladding
ML20084C921	16 July 1974	AO 50-219/74/40:on 740715,one Bergen-Paterson Hydraulic Shock & Sway Arrestor on South Core Spray Sys in Drywell Noted Inoperable.Caused by Loss of Hydraulic Fluid.Unit Replaced
ML20084D013	16 July 1974	AO 50-219/74/39:on 740714,electromatic Relief Valve Pressure Switches IA83A,B,C & E Found to Trip at Pressures in Excess of Max Allowable Value of 1070 Psig.Caused by Setpoint Repeatability.Switches Reset
ML20084D026	16 July 1974	AO 50-219/74/38:MSIV NS04B Failed to Close in Less than 10 S.Cause Under investigation.Four-way Valve in Pilot Valve Assembly Cleaned & Relubricated
ML20084D031	12 July 1974	AO 50-219/74/37:on 740712,main Steam Line Low Pressure Switches RE23A,B,C & D Found to Trip at Pressures Less than Min Value of 860 Psig.Caused by Switch Repeatability. Corrective Actions Continuing	Fuel cladding
ML20084D050	10 July 1974	AO 50-219/74/36:on 740710,reactor Pressure Sensor REO3D Failed to Trip at Point Corresponding to Reactor Pressure of 1060 Psig.Cause Under Investigation.Sensor Recalibr
ML20084D062	8 July 1974	AO 50-219/74/35:on 740705,main Steam Line Low Pressure Switches RE23B,C & D Found to Trip at Pressures Less than Min of 860 Psig.Caused by Switch Repeatability.Problem Under Investigation	Fuel cladding
ML20084D185	30 May 1974	AO 50-219/74/34:on 740529,indications of Coolant Leakage Existing in Area of in-core Flux Monitor Reactor Vessel Housing Noted.Cause Not Determined	Hydrostatic
ML20084D199	22 May 1974	AO 50-219/74/32:on 740521,core Spray Booster Pump Pressure Switch RV4OD Failed in Permissive Position.Cause Under Investigation
ML20084D205	20 May 1974	AO 50-219/74/31:on 740519,one Bergen-Paterson Hydraulic Shock & Sway Arrestor on South Core Spray Sys Found Inoperable.Caused by Loss of Hydraulic Fluid.Seven Units Replaced W/Units Equipped W/Ep Seals	Design basis earthquake
ML20084D213	15 May 1974	AO-50-219/74/30:on 740514,generator Load Rejection Scram Failed to Operate at Turbine Steaming Rates Greater than 40% of Rated While in Run Mode.Cause Under Investigation. Switch Recalibr
ML20084D219	1 May 1974	AO-50-219/74/28:on 740423,electromatic Relief Valve Pressure Switches 1A83B & D Found to Trip at Pressures in Excess of Max of 1070 Psig.Caused by Setpoint Repeatability.Switches Reset & Will Be Surveyed Each Time Reactor Shut Down
ML20084D224	19 April 1974	Preliminary AO 50-219/74/28:on 740419,motor Operated Suction Valve v-20-4 Failed to Open Electrically After Closing Electrically During Surveillance Testing on Core Spray Sys. Cause Under Investigation
ML20084D228	18 April 1974	Preliminary AO 50-219/74/27:on 740417,three Hydraulic Shock & Sway Arrestors Failed.Caused Not Identified.Units Will Be Replaced W/Units Rebuilt W/Ethylene Propylene Matl
ML20084D239	12 April 1974	Preliminary AO 50-219/74/26:on 740412,emergency Svc Water Pump 52C Failed to Start.Cause Under Investigation
ML20084D289	10 April 1974	Preliminary AO 50-219/74/25:on 740409,loss of Primary Integrity W/Reactor Critical & Reactor Water Temp Greater than 212 F Occurred.Cause Unknown.Valves Properly Seated & Successfully Leak Tested & Power Increased to Initial Value
ML20084D307	10 April 1974	Preliminary AO 50-219/74/24:on 740409,stack Gas Particulate Filter in Svc from 740328-31 Not Analyzed for Gross Beta, Alpha & Lambda.Cause Under Investigation
ML20084E038	18 March 1974	Preliminary AO 50-219/74-23:on 740315,high Flow Isolation Setpoint for Isolation Condenser Condensate Line Break Sensors Found to Actuate at Differential Pressures in Excess of Tech Specs.Caused by Sensor Drift
ML20084E040	18 March 1974	Preliminary AO 50-219/74/22:on 740315,low Pressure Main Steam Line Pressure Switch RE23D Found to Trip at Pressure Less than Min of 860 Psig.Caused by Switch Repeatability. Recommendations to Eliminate Setpoint Problem Received	Fuel cladding
ML20084E060	11 March 1974	AO 50-219/74/19:on 740309,primary Containment Integrity Not Maintained W/Reactor Water Temp Above 212 F & Fuel in Reactor Vessel.Caused by Equipment Malfunction & Operator Error
ML20084E115	1 July 1975	RO 50-219/75-18:on 750623,two 8-1/2 Inch Handhole Covers in Standby Gas Treatment Filter Train Not in Place.Cause Unknown.Handhole Covers Repositioned & Secured
ML20084E851	5 October 1970	Telecopy Ao:On 701004,gape Valve 852B Only Opened Halfway. Caused by Loose Stem Nut of Limitorque Operator.Nut Replaced
ML20084E863	14 October 1970	Telecopy Message of Ao:On 701014,gate Valve 851A Failed to Fully Close.Caused by Loose Stem Nut Locking.Lock Tightened & Stem Lubricated
ML20084F163	11 October 1973	Preliminary AO-73-26:on 731006,average Power Range Monitor (APRM) Scram & Rod Block Setpoints Not Set to Tech Spec Values.Caused by Communication Problem.Aprm Adjusted
ML20084F227	1 October 1973	Preliminary AO 73-25:on 730929,during Surveillance Test, Contacts on Relay 6K12 Failed to Open within Preset Time Delay.Cause Unknown.Relay Replaced
ML20084H968	28 September 1973	Preliminary AO-73-24:on 730927,MSIVs NA04A & B Failed to Meet Acceptable Leakage Limit.Caused by Leakage Past Valve Packing
ML20084J076	10 September 1973	Preliminary AO-73-22:on 730909,during MSIV NS03B Test Following Reactor Scram,Leakage Found in Excess of Tech Spec Limit.Cause Unknown Steam Measurements Taken on Valves
ML20084J079	10 September 1973	Preliminary AO-73-21:on 730908,several Hydraulic Shock & Sway Arrestors on Piping Sys in Drywell Failed.Caused by Inoperable Snubbers Due to Hydraulic Fluid Loss.Hydraulic Shock & Sway Arrestors Replaced
ML20084J081	10 September 1973	Preliminary AO-73-20:on 730909,during Last Stages of Plant Cooldown,Isolation Condenser NE01A Condensate Return Valve V-14-34 Failed to Operate.Caused by Tripped Overloads for Starting Contactor.Overloads Reset
ML20084J084	10 September 1973	Preliminary AO-73-19:on 730908,setting on Base Differential Monitoring Relay C of Startup Transformers Considered Inoperable.Caused by Incorrect Setting of Transformer Ratio Matching Taps.Taps Set Properly
ML20084J086	31 August 1973	AO-73-18:on 730823,max Amount of Radioactivity Contained in Outside Radwaste Storage Tanks Exceeded Tech Spec Limits. Caused by Failure to Recirculate Tank for Sufficient Time to Eliminate Stratification.Tanks Will Be Cleaned Out
ML20084J089	2 April 1974	Supplementary AO: Beginning 740112,during Plant Shutdown, Hydraulic Shock & Sway Arrestor Insp Found 30 Affected Snubbers.Surveillance Program Outlined on 731207 Will Continue Until Satisfactory Solution Is Found
ML20084J212	17 August 1973	AO-73-17:on 730808,during Surveillance Insp of Diesel Generator 1,two Starting Motors Failed to Engage.Caused by Bushing Which Slipped Out of Position & Prevented Pinion Gear from Engaging Ring Gear.Starter Motor Replaced
ML20084J222	6 August 1973	Ao:On 730721,during Plant Shutdown,Eight Drywell Snubbers Discovered Missing Hydraulic Fluid.Caused by Seal Failure Creating Leakage Path.Snubbers Replaced.Forwards Snubber Repair Activities..., Summary Rept	Earthquake
ML20084J241	25 July 1973	Preliminary AO-73-15:on 730725,during Closure Timing & Scram Checks,Msiv NS04B Closed in Less than 3 S.Caused by Insufficient Oil in Hydraulic Dashpot.Seal Cartridge Assembly Replaced
ML20084J248	31 July 1973	AO-73-14:on 730723,plot of Absorption Pool (Torus) Water Level Developed.Caused by Feedwater Leak Around Check Valve Hinge Pin Seal Plugs.Erosion of Seating Surface on Valve Body Machined Out
ML20084J253	28 June 1973	AO-73-11:from 730609-13,reactor Coolant Not Analyzed for Total Radioactive Iodine Content.Caused by Failure of Multichannel Analyzer.Analyzer Repaired	Grab sample
ML20084J266	28 June 1973	AO-73-12:on 730618,containment Spray Sys 2 Automatic Reset Circuitry Failed.Caused by Relay Coil 16K22B Failure.Coil & Relay Series Resistor Replaced
ML20084J276	15 May 1973	Ao:On 730504,during Local Leak Rate Testing,Torus to Reactor Bldg Vacuum Breaker Lines Failed to Hold Pressure Between Isolation Valves V-26-17 & 18.Caused by Butterfly Valve V-26-18 Leakage.Valve Linkage Adjusted
ML20084J284	22 June 1973	Followup of 730424 AO Rept Re Failure of Electromatic Relief Valve NR-108-B During Operability Test.Addl Investigation Revealed Failure Due to Solenoid Core Guide Pin.New 304SS Guide Pins Machined to Proper Dimensions
ML20084J547	5 July 1973	AO-73-13:on 730621,during Power Operation,Diesel Generator 2 Failed to Fully Operate.Caused by Three Transformer Fuses Blowing During Lightning Storm.Two Fuses Replaced & One Jumped
ML20084J550	5 June 1973	Ao:On 730522,during Leakage Testing for MSIV NSO4B,vol Between NOS3B & 4 Could Not Be Drained.Caused by Leak in NSO3B.Valve Stem Replaced
ML20084J551	30 May 1973	Ao:On 730518,during Refueling Outage Test,Liquid Poison Pump NP01A Failed.Caused by Blown Logic Control Power Fuse. Fuse Locations Tagged or Identified for Proper Size	Squib
ML20084J563	22 June 1973	AO-73-10:on 730611,during Surveillance Test,Diesel Generator 1-1 Failed to Assume Load.Caused by Engine Governors Not Set for 60 Hz Unloaded Operation.Generator Properly Synchronized
ML20084J607	5 June 1973	Ao:On 730527,drywell Head Manhole Cover Double Gasket Seal Failed to Meet Acceptable Leakage Specified in Tech Specs. Caused by Brittle Outer Gasket.Gasket Replaced
ML20084J675	24 April 1973	Ao:On 730424,during Surveillance Test of B Isolation Condensor Motor Operated Condensate Return Valve V-14-35, Breakaway from Closed Motor Current of 75 Amps Observed. Cause Undetermined.Torque Applied to Handwheel Freed Disc
ML20084J712	23 March 1973	Ao:On 730310,recirculation Loop Started When Coolant Temp & Reactor Coolant Temp Exceeded 50 F Differential.Caused by Personnel Error.Recirculation Sys Operating & Emergency Procedures Revised
ML20084T882	15 June 1970	Ao:On 700605,turbine electro-hydraulic Control Sys Transient Caused Turbine Trip & Reactor Scram,Followed by Inadvertently Opened Safety Valves.Two Safety Valves Failed to Close,Releasing Primary Coolant to Containment
ML20084U950	2 January 1975	AO 50-265/74-29:on 741223,cracks at Welds in 4 Inch Reactor Recirculation Discharge Valve Bypass Lines Indicated.Cause Undetermined.Piping on a & B Loops to Be Completely Replaced

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