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| | U.1. NUCLEAR REtULATCGY COMMISSION N2C FO)[M }64 (7 771 * -- |
| U.1. NUCLEAR REtULATCGY COMMISSION | | LICENSEE EVENT REPORT CCNTRCL BLOCK. l l l ! l l |
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| N2C FO)[M }64 (7 771 * -- | |
| LICENSEE EVENT REPORT CCNTRCL BLOCK. l | |
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| ..h l (PLEASE PRINT OR TYPE ALL REcutRED INFORMATION) __ | | ..h l (PLEASE PRINT OR TYPE ALL REcutRED INFORMATION) __ |
| Ie l ta i3I Nl Ji 7 | | Ie l ta i3I Nl Ji 7 |
| O l C ! P l141 l@l yqEt43EE CODE 15 0l Ol -l 0 UCENSEl 0l 0N6Me l 0ERl 0 l - l 0 l 025 l@l 24 411 uCENSEl1 l1 l140l@l 97 Gl T 64l@ | | O l C ! P l141 l@l yqEt43EE CODE 15 0l Ol -l 0 UCENSEl 0l 0N6Me l 0ERl 0 l - l 0 l 025 l@l 24 411 uCENSEl1 l1 l140l@l 97 Gl T 64l@ |
| TYPE Cos T g3:,,"'' 3 l L l@l 0 l 5 l0 l0 10 l2 l1 l9 @l 1l 2 l 0 l 4 l 8 l 0 @l1121280 l318 l0 Felil 74 7S 7 8 | | TYPE Cos T g3:,,"'' 3 l L l@l 0 l 5 l0 l0 10 l2 l1 l9 @l 1l 2 l 0 l 4 l 8 l 0 @l1121280 l318 l0 Felil 74 7S 7 8 60 68 QQCK ET NWUS ER 68 69 EVENT CAfg MEPORT QATE EVENf CESCRIPTION AND PRC8AELE CCNSECUENCES h Ie 1:l t During surveillance testing, the Main Stea:n Line high flow senscrs.. I |
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| 60 68 QQCK ET NWUS ER 68 69 EVENT CAfg MEPORT QATE EVENf CESCRIPTION AND PRC8AELE CCNSECUENCES h Ie 1:l t During surveillance testing, the Main Stea:n Line high flow senscrs.. I | |
| ,o,3, l RE-22C and R'E-22G tripped at values greater than the limit of 97.5 psig I g o ,, , ; given in the Technical Specifications, Table 3.1.1, iten B.2. 'Ihe trip I i333, ; point values were 98.5 psig for both sensors. The safety significance I ic !e ! i is considered nuninal because the redundant switches RE-22D and RE-22H I | | ,o,3, l RE-22C and R'E-22G tripped at values greater than the limit of 97.5 psig I g o ,, , ; given in the Technical Specifications, Table 3.1.1, iten B.2. 'Ihe trip I i333, ; point values were 98.5 psig for both sensors. The safety significance I ic !e ! i is considered nuninal because the redundant switches RE-22D and RE-22H I |
| ; c ; ; ; would have actuated at the desired level to initiate the required nnin [ | | ; c ; ; ; would have actuated at the desired level to initiate the required nnin [ |
| ,,,3, ; steam isolation functions. l | | ,,,3, ; steam isolation functions. l x< sc SYSTEM CAUSE CAUSE COM8 VALV E 0003 .CCOE 3680002 00MP:NE*:7 000E Sut:0:5 ty200 t ioi9i l C l C l@ lX l@ l Z l@ lI lN lS lT lR IU l h l E l @ (Z _j h 20 7 a 2 13 tt 12 13 16 19 |
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| x< sc SYSTEM CAUSE CAUSE COM8 VALV E 0003 .CCOE 3680002 00MP:NE*:7 000E Sut:0:5 ty200 t ioi9i l C l C l@ lX l@ l Z l@ lI lN lS lT lR IU l h l E l @ (Z _j h 20 7 a 2 13 tt 12 13 16 19 | |
| , SECU ENTI AL CCCUARENCE RE' CAT 4 EvtS6CN gge so EVENT YEAR REPORT NC. COOE TYPE N O. | | , SECU ENTI AL CCCUARENCE RE' CAT 4 EvtS6CN gge so EVENT YEAR REPORT NC. COOE TYPE N O. |
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| el 0l lYl@ lLl@ lIl2!014l@ | | el 0l lYl@ lLl@ lIl2!014l@ |
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| [i;ol l The cause of the occurrence was due to instrument repeatability. Sensor I | | [i;ol l The cause of the occurrence was due to instrument repeatability. Sensor I |
| [,,,, ;RE-22C was reset tc trip within the desired level, yet sensor RE-22G had 1 | | [,,,, ;RE-22C was reset tc trip within the desired level, yet sensor RE-22G had 1 |
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| | , , , , , ,to have a microswitch replaced before it would reset to trip at the I i |
| , , , , , ,to have a microswitch replaced before it would reset to trip at the I | |
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| ; ,, ,,, gproper value. 'Ihe PORC has reuawaded that these switches be replaced I | | ; ,, ,,, gproper value. 'Ihe PORC has reuawaded that these switches be replaced I |
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| I 80 7 8 9 f A %PCWER CTHER STATUS isCO R DISCOVERY 0ESCRIPTTON h | | I 80 7 8 9 f A %PCWER CTHER STATUS isCO R DISCOVERY 0ESCRIPTTON h L,'_L5J l E l@ l 0l 9 l 432l@ln NA l [B_j @ l Surveillance Test l e ,g, , 4 * * . ' |
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| 7 8 9 to it 30 i *ERSONNEL EXPCSURES I NupeER TYPE OESCMtPTICN 39 l1171 l 0 l 0 l 0 l@l Z l@l NA l ; | |
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| , PSPSONNEt tNJU IES Nywegm 3 ESCRIPTICN NA l 11 l'4 l l 0 l 0 l 011l@l12 7 8 9 30 | | , PSPSONNEt tNJU IES Nywegm 3 ESCRIPTICN NA l 11 l'4 l l 0 l 0 l 011l@l12 7 8 9 30 |
| ' LCSS 08 Cm CAMAGE TO PAQUTY Q TY'E OEScal* TION N/ | | ' LCSS 08 Cm CAMAGE TO PAQUTY Q TY'E OEScal* TION N/ |
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| NA ITTT1 4 9 l Z l@l10 l 7 30 | | NA ITTT1 4 9 l Z l@l10 l 7 30 |
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| @TEScai, Weekly Tic,@News Release J01050 M i NRC USE ONLY . | | @TEScai, Weekly Tic,@News Release J01050 M i NRC USE ONLY . |
| j l lII!li1ll1I!!5 go . - | | j l lII!li1ll1I!!5 go . - |
| A a 9 to 68 49 | | A a 9 to 68 49 Michael J. Fitzgerald (609) 693-6038 NAME OF P9E8ARER PHONE: 3}} |
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| Michael J. Fitzgerald (609) 693-6038 NAME OF P9E8ARER PHONE: 3}} | |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045G7881993-07-0101 July 1993
LER 93-004-00:on 930602,discovered Potential Torus Condition Outside Design Basis.Caused by Inadequate Design Info. Documentation Procedures Revised.Torus Calculations to Include Peak Pressure info.W/930701 Ltr
ML20028H6911991-01-21021 January 1991
LER 90-016-00:on 901220,senior Reactor Operator Licensed Group Shift Supervisor Left Control Room W/O Replacement, Resulting in Lack of Operator in Control Room for 4 Minutes. Both Operators Returned to Control room.W/910121 Ltr
ML20044B3831990-07-12012 July 1990
LER 90-007-00:on 900614,discovered That Numerous Fire Detection Instruments Exceeded Max Allowable Interval for 6-month Operability Test.Caused by Personnel Error. Procedures for Surveillance Tests changed.W/900712 Ltr
ML20043G0931990-06-0808 June 1990
LER 90-006-00:on 900511,average Power Level Exceeded Licensed Limit by Approx 1.64 MW When Cleanup Sys Placed in Svc W/O 7.84 MW Loss Added Into Heat Balance Calculation. Caused by Personnel Error.Procedures changed.W/900608 Ltr
ML20043B1181990-05-18018 May 1990
LER 89-023-01:on 891209,four of Six Low Vacuum Scram Setpoints Found Out of Spec Due to Drift of Sensing Element & Lack of Margin for Drift in as-left Setpoint in Calibr Procedure.Instrument Setpoint adjusted.W/900518 Ltr
ML20043A4281990-05-15015 May 1990
LER 90-025-01:on 891216,operator Inadvertently Selected Incorrect Control Rod,Then Selected Correct Rod When Error Realized.Second Control Room Operator Will Be Used to Assure That No Signal Failure Will Move Two rods.W/900515 Ltr
ML20012D9441990-03-21021 March 1990
LER 90-004-00:on 900220,operation of hand-held Radio Near Analog Trip Units Caused Sys to Actuate & Air Operated Valves Repositioned.Caused by Personnel Error.Use of Radios Must Be Approved by Supervisor of technicians.W/900321 Ltr
ML20012D1601990-03-14014 March 1990
LER 90-003-00:on 900215,seven Control Rods Withdrawn During Reactor Startup While Rod Minimizer Was Bypassed.Caused by Personnel Error.Withdrawal Stopped & Keylock Switch Placed in Normal position.W/900314 Ltr
ML20012D1581990-03-14014 March 1990
LER 89-017-01:on 890711,main Generator Tripped Due to Phase Differential Condition Caused by Fault in Operating Maint Output Transformer.Caused by Equipment Failure.Oil Boxes on Transformers repaired.W/900314 Ltr
ML20012A1731990-02-27027 February 1990
LER-89-023-00:on 891209,four Out of Six Condenser Low Vacuum Setpoints Found at Values Less Conservative than Tech Spec Limit.Caused by Sensing Element Drift & Lack of Margin for Drift in Calibr Procedure.Setpoint changed.W/900227 Ltr
ML20011F4401990-02-22022 February 1990
LER 90-001-00:on 900123,fire Alarm Received for Fire Zone in Cable Spreading Room,Resulting in Operability of Deluge Sys. Continuous Fire Watch Not Established.Caused by Inadequate Procedural Guidance.Detectors disabled.W/900222 Ltr
ML19354D8341990-01-12012 January 1990
LER 89-021-01:on 890922,ref Leg of Level Instrument Vented to Test Equipment,Causing False High Reactor Pressure Vessel Signal.Caused by Trip of Turbine Generator Resulting in Scram.Excess Flow Check Valve depressurized.W/900112 Ltr
ML19327C0661989-11-0606 November 1989
LER 89-022-00:on 891005,Tech Spec Violation Occurred When Licensed Group Shift Supervisor Left Control Room W/O Informing Operating Supervisor.Caused by Personnel Error. Individual Involved counseled.W/891106 Ltr
ML19351A4161989-10-13013 October 1989
LER 89-020-00:on 890915,operator Trainee Identified That Knife Switch Used to Select Dc Control Power Source for 480 Volt Ac Unit Substation 1B2 Was Selected.Caused by Procedural Inadequacy.Lineup Sheet used.W/891013 Ltr
ML19327A8081989-10-11011 October 1989
LER 89-019-00:on 890911,emergency Diesel Generator Became Inoperable.Caused by Dirt on Wiper of Motorized Potentiometer in Peaking Load Control Circuit & Latent Heat Expansion of Engine.Fuel Injectors replaced.W/891011 Ltr
ML19327B4961989-09-23023 September 1989
LER 89-021-00:on 890922,false High Reactor Pressure Vessel Water Level Caused Turbine Generator Trip & Reactor Scram. Caused by Personnel Not Following Surveillance Procedure.All Involved Instruments Calibr checked.W/891023 Ltr
ML20028G4431983-01-28028 January 1983
LER 82-063/03L-0:on 821227,operability of Control Rod Drive Pump a Not Demonstrated During 1-month Period.Caused by Breakdown in Administrative Controls for Surveillance Test Program.Surveillance Completed
ML20028G2361983-01-28028 January 1983
LER 82-064/03L-0:on 821230,containment Spray Sys 1 Declared Inoperable Due to High Baffle Plate Differential Pressure Readings on 1-2 Hx.Caused by HX Fouling.Hx Inspected & Cleaned & Chlorination Sys for Emergency Svc Water Repaired
ML20028E7741983-01-20020 January 1983
LER 82-061/03L-0:on 821216,offgas Isolation Valve Failed to Close Fully on Independent Closure Signal.Caused by Defective Pilot Solenoid Valves Due to Foreign Matter on Solenoid Valve Seat Prohibiting Termination of Air Supply
ML20028C7991982-12-29029 December 1982
LER 82-058/03L-0:on 821128,main Steam Line Drain Valves V-1-106 & V-1-110 Failed to Close Fully.Cause Unknown. Investigation Will Continue During Next Outage
ML20028C7541982-12-27027 December 1982
LER 82-059/03L-0:on 821124,reactor Circulation Pump a Taken Out of Svc.Caused by Indications of Leaking Seals.Seal Confirmed to Be Leaking During Subsequent Shutdown. Cartridge Assembly Replaced
ML20027B9151982-09-16016 September 1982
LER 82-046/03L-0:on 820815,controls Keeping Main Line Drain Valves Deactivated in Isolation Position Were Defeated Prior to Temp Dropping Below 212 F.Caused by Personnel Error.Personnel Reinstructed
ML20052E6541982-05-0303 May 1982
LER 82-021/01T-0:on 820416,containment Oxygen Concentration Not Reduced within 24-h After Run Mode & Drywell to Torus Differential Pressure Greater than 1 Psi.Caused by Loss of 6-h Inerting Time Due to Insufficient Nitrogen
ML20052E2161982-04-28028 April 1982
LER 82-017/03L-0:on 820325,normal Auxiliary Power Bus 1C Relay Failed Totally & Svc Water Pump Trip Time Delay Relay SK8A Failed to Operate within Tech Spec Limits.Power Bus Failure Caused by Normal End of Life
ML20052B0941982-04-16016 April 1982
LER 82-020/01T-0:on 820328,MSIV Leak Rate Testing Disclosed Deterioration of Valve Internals on NS03-A & Packing Leak on Outboard Valve NS04-A.Caused Not stated.NS03-A Disassembled & repaired.NS04-A Repacked
ML20052G0011982-04-16016 April 1982
LER 82-021/01P:on 820416,primary Containment Atmosphere Not Reduced to Less than 5% Oxygen within 24-h After Reactor Mode Selector Switch Placed in Run Position.Caused by Insufficient Nitrogen & Blown Rupture Disc
ML20050D9091982-03-29029 March 1982
LER 82-013/03L-0:on 820128,low Voltage Annunciator Relay Setting for Main Station Batteries B & C & Diesel Generator 2 Battery Relay & Setting Found Below Tech Specs Limit. Caused by Annunciation Setpoints Out of Spec
ML20050A5051982-03-19019 March 1982
LER 82-008/03L-0:on 820210,monthly Channel Check of Secondary (Thermocouples) Safety & Relief Valve Position Monitoring Sys Not Performed as Required by Tech Spec. Caused by Lack of Administrative & Procedural Controls
ML20042B2951982-03-15015 March 1982
LER 82-012/01P-0:on 820226,air Operated Vacuum Breaker V-26-18 Exceeded Allowable Leak Rate.Caused by Improper Alignment of Valve Shaft & Operator Due to Inadequate Maint Instructions.Valve Realigned & Procedures Will Be Revised
ML20042B3141982-03-12012 March 1982
LER 82-009/03L-0:on 820210,overload Trip Occurred on Standby Gas Treatment Sys Exhaust Fan 1-8.Apparently Caused by Change in Breaker Trip Setpoint.Further Testing Underway
ML20042A6281982-03-10010 March 1982
LER 82-011/03L-0:on 820208,three Hydraulic Snubbers Were Inoperable & Accelerated Surveillance of Tech Spec 4.5.0.3 Was Not Performed.Caused by Component Failure.Snubbers Replaced W/Certified Operable Snubbers
ML20042A2941982-03-0505 March 1982
LER 81-071/01T-0:on 811231,radwaste Liquid Effluent Monitor Found Inoperable.Proper Surveillance Not Performed.Caused by Personnel Error & Lack of Administrative & Procedural Controls.Control Procedures Written & Parts Replaced
ML20042A1131982-03-0404 March 1982
LER 82-010/01T-0:on 820218,deluge Sys for Reactor Bldg Elevation 51 Ft Actuated Due to Smoke from Overheated Bearing in Cleanup Sys Auxiliary Pump Motor.Caused by Inadequate Electrical Sealing Techniques
ML20052G0281982-03-0101 March 1982
LER 82-012/01P:on 820226,reactor Bldg to Suppression Chamber Vacuum Breaker Valve V-26-18 Found Improperly Installed. Caused by Inadequate Procedure.Valve Shaft Realigned
ML20041D8071982-02-26026 February 1982
LER 82-006/01T-0:on 811203,one Trip Sys in Automatic Depressurization Sys Rendered Inoperable by Removal of Dc Control Power Fuses.Caused by Nonrating of Microswitches Inside IA83-A Replacement.All EMRV Switches Replaced
ML20041D8021982-02-25025 February 1982
LER 82-007/03L-0:on 820126,main Steam Line High Flow Sensor RE-22H Tripped at Greater Value than Given in Tech Specs. Caused by Instrument Repeatability & Drift.Sensor Reset & Setpoints Lowered
ML20041D7821982-02-25025 February 1982
LER 82-005/03L-0:on 820125,during Load Surveillance Test, Diesel Generator 1-1 Tripped on Engine Fault.Caused by Reduction of Water Inventory in Cooling Sys as Result of Radiator Tube Leak.Leaky Tubes Plugged
ML20041D4681982-02-22022 February 1982
LER 82-004/03L-0:on 820121,reactor Bldg Closed Cooling Water Drywell Isolation Valve V-5-167 Failed to Fully Close.Caused by Lack of Stem/Stem Nut Lubrication &/Or Packing Problem. Stem,Stem Nut & Bearing Lubricated & Valve Repacked
ML20041D5801982-02-19019 February 1982
LER 82-002/03L-0:on 820118,installation of Mod Could Have Led to Possible Failure to Maintain Primary Containment Integrity.Change Defeated Automatic Withdrawal Function 3 & 4 TIP Detectors.Caused by Inadequate Safety Review
ML20041D3791982-02-19019 February 1982
LER 82-003/03L-0:on 820122,containment Spray High Drywell Pressure Indicating Switch IP25B Found to Trip at Value Greater than Tech Spec Limits.Caused by Instrument Repeatability.Switch Reset
ML20041A2231982-02-0505 February 1982
LER 81-061/03L-0:on 811223,nine Snubbers on Core Spray, Containment Spray,Isolation Condenser & Shutdown Cooling Sys Determined Inoperable Due to Oil Leakage.Cause to Be Determined.Snubbers Replaced W/Operable Spares
ML20040F5301982-02-0101 February 1982
LER 82-001/03L-0:on 820128,during Testing,Containment Spray High Drywell Pressure Indicating Switches IP15A,IP15B & IP15C Found to Trip at Values Greater than Tech Spec Limits. Caused by Instrument Repeatability.Switches Reset
ML20040F4831982-01-28028 January 1982
LER 81-070/03L-0:on 811231,isolation Condenser Isolation Pipe Break Sensor IB11A1 Tripped Above Tech Spec Limit. Caused by Instrument Repeatability.Setpoint Lowered.Switches Will Be Replaced During Future Refueling Outage
ML20040F5201982-01-28028 January 1982
LER 81-072/03L-0:on 811229,core Spray Sys I Parallel Isolation Valve V-20-15 Became Inoperable in Partially Open Position.Caused by High Motor Current Drawn When Valve Close Signal Inadvertently Intiated During Valve Stroking
ML20040E4281982-01-26026 January 1982
LER 81-069/03L-0:on 811230,during Surveillance Testing,Core Spray High Drywell Pressure Switches RV-46A,RV-46B & RV-46D Tripped.Caused by Instrument Repeatability.Switches Reset. Setpoint Changed to Reflect Inherent Design Error
ML20040D7551982-01-20020 January 1982
LER 81-067/03L-0:on 811220,during Maint Testing,Scram Pilot Solenoid Valve 118 (for Control Rod Drive 14-23) Failed When Rod Was Individually Scrammed.No Plausible Cause Could Be Postulated.All Scram Solenoids Will Be Verified Operable
ML20040C6631982-01-18018 January 1982
LER 81-068/03L-0:on 811218,reactor Triple Low Water Level Indicator Switch RE18A Tripped at Monometer Reading Exceeding Tech Spec Limit.Caused by Instrument Drift.Switch Reset.Setpoint Sensors Will Be Replaced
ML20040B1501981-12-31031 December 1981
LER 81-066/03L-0:on 811201,during Surveillance Testing,Main Steam Line High Flow Sensors RE22C,RE22E & RE22F Tripped at Values Greater than Tech Specs Limit.Caused by Instrument Repeatability & Drift.Sensors Reset
ML20039G0981981-12-23023 December 1981
LER 81-065/01T-0:on 811209,shutdown Commenced to Investigate a Isolation Condenser Isolation Valve V-14-30 811203 & 04 Failure to Operate Properly.Caused by Excessive Stress on Valve Backseat & Damage to Stem Nut
ML20039G1891981-12-23023 December 1981
LER 81-062/03L-0:on 811125,core Spray Hi Drywell Pressure Switch RV46C Tripped in Excess of Tech Spec Limit.Caused by Sensor Repeatability.Sensor Recalibr
1993-07-01
[Table view]
Category:RO)
MONTHYEARML20045G7881993-07-0101 July 1993
LER 93-004-00:on 930602,discovered Potential Torus Condition Outside Design Basis.Caused by Inadequate Design Info. Documentation Procedures Revised.Torus Calculations to Include Peak Pressure info.W/930701 Ltr
ML20028H6911991-01-21021 January 1991
LER 90-016-00:on 901220,senior Reactor Operator Licensed Group Shift Supervisor Left Control Room W/O Replacement, Resulting in Lack of Operator in Control Room for 4 Minutes. Both Operators Returned to Control room.W/910121 Ltr
ML20044B3831990-07-12012 July 1990
LER 90-007-00:on 900614,discovered That Numerous Fire Detection Instruments Exceeded Max Allowable Interval for 6-month Operability Test.Caused by Personnel Error. Procedures for Surveillance Tests changed.W/900712 Ltr
ML20043G0931990-06-0808 June 1990
LER 90-006-00:on 900511,average Power Level Exceeded Licensed Limit by Approx 1.64 MW When Cleanup Sys Placed in Svc W/O 7.84 MW Loss Added Into Heat Balance Calculation. Caused by Personnel Error.Procedures changed.W/900608 Ltr
ML20043B1181990-05-18018 May 1990
LER 89-023-01:on 891209,four of Six Low Vacuum Scram Setpoints Found Out of Spec Due to Drift of Sensing Element & Lack of Margin for Drift in as-left Setpoint in Calibr Procedure.Instrument Setpoint adjusted.W/900518 Ltr
ML20043A4281990-05-15015 May 1990
LER 90-025-01:on 891216,operator Inadvertently Selected Incorrect Control Rod,Then Selected Correct Rod When Error Realized.Second Control Room Operator Will Be Used to Assure That No Signal Failure Will Move Two rods.W/900515 Ltr
ML20012D9441990-03-21021 March 1990
LER 90-004-00:on 900220,operation of hand-held Radio Near Analog Trip Units Caused Sys to Actuate & Air Operated Valves Repositioned.Caused by Personnel Error.Use of Radios Must Be Approved by Supervisor of technicians.W/900321 Ltr
ML20012D1601990-03-14014 March 1990
LER 90-003-00:on 900215,seven Control Rods Withdrawn During Reactor Startup While Rod Minimizer Was Bypassed.Caused by Personnel Error.Withdrawal Stopped & Keylock Switch Placed in Normal position.W/900314 Ltr
ML20012D1581990-03-14014 March 1990
LER 89-017-01:on 890711,main Generator Tripped Due to Phase Differential Condition Caused by Fault in Operating Maint Output Transformer.Caused by Equipment Failure.Oil Boxes on Transformers repaired.W/900314 Ltr
ML20012A1731990-02-27027 February 1990
LER-89-023-00:on 891209,four Out of Six Condenser Low Vacuum Setpoints Found at Values Less Conservative than Tech Spec Limit.Caused by Sensing Element Drift & Lack of Margin for Drift in Calibr Procedure.Setpoint changed.W/900227 Ltr
ML20011F4401990-02-22022 February 1990
LER 90-001-00:on 900123,fire Alarm Received for Fire Zone in Cable Spreading Room,Resulting in Operability of Deluge Sys. Continuous Fire Watch Not Established.Caused by Inadequate Procedural Guidance.Detectors disabled.W/900222 Ltr
ML19354D8341990-01-12012 January 1990
LER 89-021-01:on 890922,ref Leg of Level Instrument Vented to Test Equipment,Causing False High Reactor Pressure Vessel Signal.Caused by Trip of Turbine Generator Resulting in Scram.Excess Flow Check Valve depressurized.W/900112 Ltr
ML19327C0661989-11-0606 November 1989
LER 89-022-00:on 891005,Tech Spec Violation Occurred When Licensed Group Shift Supervisor Left Control Room W/O Informing Operating Supervisor.Caused by Personnel Error. Individual Involved counseled.W/891106 Ltr
ML19351A4161989-10-13013 October 1989
LER 89-020-00:on 890915,operator Trainee Identified That Knife Switch Used to Select Dc Control Power Source for 480 Volt Ac Unit Substation 1B2 Was Selected.Caused by Procedural Inadequacy.Lineup Sheet used.W/891013 Ltr
ML19327A8081989-10-11011 October 1989
LER 89-019-00:on 890911,emergency Diesel Generator Became Inoperable.Caused by Dirt on Wiper of Motorized Potentiometer in Peaking Load Control Circuit & Latent Heat Expansion of Engine.Fuel Injectors replaced.W/891011 Ltr
ML19327B4961989-09-23023 September 1989
LER 89-021-00:on 890922,false High Reactor Pressure Vessel Water Level Caused Turbine Generator Trip & Reactor Scram. Caused by Personnel Not Following Surveillance Procedure.All Involved Instruments Calibr checked.W/891023 Ltr
ML20028G4431983-01-28028 January 1983
LER 82-063/03L-0:on 821227,operability of Control Rod Drive Pump a Not Demonstrated During 1-month Period.Caused by Breakdown in Administrative Controls for Surveillance Test Program.Surveillance Completed
ML20028G2361983-01-28028 January 1983
LER 82-064/03L-0:on 821230,containment Spray Sys 1 Declared Inoperable Due to High Baffle Plate Differential Pressure Readings on 1-2 Hx.Caused by HX Fouling.Hx Inspected & Cleaned & Chlorination Sys for Emergency Svc Water Repaired
ML20028E7741983-01-20020 January 1983
LER 82-061/03L-0:on 821216,offgas Isolation Valve Failed to Close Fully on Independent Closure Signal.Caused by Defective Pilot Solenoid Valves Due to Foreign Matter on Solenoid Valve Seat Prohibiting Termination of Air Supply
ML20028C7991982-12-29029 December 1982
LER 82-058/03L-0:on 821128,main Steam Line Drain Valves V-1-106 & V-1-110 Failed to Close Fully.Cause Unknown. Investigation Will Continue During Next Outage
ML20028C7541982-12-27027 December 1982
LER 82-059/03L-0:on 821124,reactor Circulation Pump a Taken Out of Svc.Caused by Indications of Leaking Seals.Seal Confirmed to Be Leaking During Subsequent Shutdown. Cartridge Assembly Replaced
ML20027B9151982-09-16016 September 1982
LER 82-046/03L-0:on 820815,controls Keeping Main Line Drain Valves Deactivated in Isolation Position Were Defeated Prior to Temp Dropping Below 212 F.Caused by Personnel Error.Personnel Reinstructed
ML20052E6541982-05-0303 May 1982
LER 82-021/01T-0:on 820416,containment Oxygen Concentration Not Reduced within 24-h After Run Mode & Drywell to Torus Differential Pressure Greater than 1 Psi.Caused by Loss of 6-h Inerting Time Due to Insufficient Nitrogen
ML20052E2161982-04-28028 April 1982
LER 82-017/03L-0:on 820325,normal Auxiliary Power Bus 1C Relay Failed Totally & Svc Water Pump Trip Time Delay Relay SK8A Failed to Operate within Tech Spec Limits.Power Bus Failure Caused by Normal End of Life
ML20052B0941982-04-16016 April 1982
LER 82-020/01T-0:on 820328,MSIV Leak Rate Testing Disclosed Deterioration of Valve Internals on NS03-A & Packing Leak on Outboard Valve NS04-A.Caused Not stated.NS03-A Disassembled & repaired.NS04-A Repacked
ML20052G0011982-04-16016 April 1982
LER 82-021/01P:on 820416,primary Containment Atmosphere Not Reduced to Less than 5% Oxygen within 24-h After Reactor Mode Selector Switch Placed in Run Position.Caused by Insufficient Nitrogen & Blown Rupture Disc
ML20050D9091982-03-29029 March 1982
LER 82-013/03L-0:on 820128,low Voltage Annunciator Relay Setting for Main Station Batteries B & C & Diesel Generator 2 Battery Relay & Setting Found Below Tech Specs Limit. Caused by Annunciation Setpoints Out of Spec
ML20050A5051982-03-19019 March 1982
LER 82-008/03L-0:on 820210,monthly Channel Check of Secondary (Thermocouples) Safety & Relief Valve Position Monitoring Sys Not Performed as Required by Tech Spec. Caused by Lack of Administrative & Procedural Controls
ML20042B2951982-03-15015 March 1982
LER 82-012/01P-0:on 820226,air Operated Vacuum Breaker V-26-18 Exceeded Allowable Leak Rate.Caused by Improper Alignment of Valve Shaft & Operator Due to Inadequate Maint Instructions.Valve Realigned & Procedures Will Be Revised
ML20042B3141982-03-12012 March 1982
LER 82-009/03L-0:on 820210,overload Trip Occurred on Standby Gas Treatment Sys Exhaust Fan 1-8.Apparently Caused by Change in Breaker Trip Setpoint.Further Testing Underway
ML20042A6281982-03-10010 March 1982
LER 82-011/03L-0:on 820208,three Hydraulic Snubbers Were Inoperable & Accelerated Surveillance of Tech Spec 4.5.0.3 Was Not Performed.Caused by Component Failure.Snubbers Replaced W/Certified Operable Snubbers
ML20042A2941982-03-0505 March 1982
LER 81-071/01T-0:on 811231,radwaste Liquid Effluent Monitor Found Inoperable.Proper Surveillance Not Performed.Caused by Personnel Error & Lack of Administrative & Procedural Controls.Control Procedures Written & Parts Replaced
ML20042A1131982-03-0404 March 1982
LER 82-010/01T-0:on 820218,deluge Sys for Reactor Bldg Elevation 51 Ft Actuated Due to Smoke from Overheated Bearing in Cleanup Sys Auxiliary Pump Motor.Caused by Inadequate Electrical Sealing Techniques
ML20052G0281982-03-0101 March 1982
LER 82-012/01P:on 820226,reactor Bldg to Suppression Chamber Vacuum Breaker Valve V-26-18 Found Improperly Installed. Caused by Inadequate Procedure.Valve Shaft Realigned
ML20041D8071982-02-26026 February 1982
LER 82-006/01T-0:on 811203,one Trip Sys in Automatic Depressurization Sys Rendered Inoperable by Removal of Dc Control Power Fuses.Caused by Nonrating of Microswitches Inside IA83-A Replacement.All EMRV Switches Replaced
ML20041D8021982-02-25025 February 1982
LER 82-007/03L-0:on 820126,main Steam Line High Flow Sensor RE-22H Tripped at Greater Value than Given in Tech Specs. Caused by Instrument Repeatability & Drift.Sensor Reset & Setpoints Lowered
ML20041D7821982-02-25025 February 1982
LER 82-005/03L-0:on 820125,during Load Surveillance Test, Diesel Generator 1-1 Tripped on Engine Fault.Caused by Reduction of Water Inventory in Cooling Sys as Result of Radiator Tube Leak.Leaky Tubes Plugged
ML20041D4681982-02-22022 February 1982
LER 82-004/03L-0:on 820121,reactor Bldg Closed Cooling Water Drywell Isolation Valve V-5-167 Failed to Fully Close.Caused by Lack of Stem/Stem Nut Lubrication &/Or Packing Problem. Stem,Stem Nut & Bearing Lubricated & Valve Repacked
ML20041D5801982-02-19019 February 1982
LER 82-002/03L-0:on 820118,installation of Mod Could Have Led to Possible Failure to Maintain Primary Containment Integrity.Change Defeated Automatic Withdrawal Function 3 & 4 TIP Detectors.Caused by Inadequate Safety Review
ML20041D3791982-02-19019 February 1982
LER 82-003/03L-0:on 820122,containment Spray High Drywell Pressure Indicating Switch IP25B Found to Trip at Value Greater than Tech Spec Limits.Caused by Instrument Repeatability.Switch Reset
ML20041A2231982-02-0505 February 1982
LER 81-061/03L-0:on 811223,nine Snubbers on Core Spray, Containment Spray,Isolation Condenser & Shutdown Cooling Sys Determined Inoperable Due to Oil Leakage.Cause to Be Determined.Snubbers Replaced W/Operable Spares
ML20040F5301982-02-0101 February 1982
LER 82-001/03L-0:on 820128,during Testing,Containment Spray High Drywell Pressure Indicating Switches IP15A,IP15B & IP15C Found to Trip at Values Greater than Tech Spec Limits. Caused by Instrument Repeatability.Switches Reset
ML20040F4831982-01-28028 January 1982
LER 81-070/03L-0:on 811231,isolation Condenser Isolation Pipe Break Sensor IB11A1 Tripped Above Tech Spec Limit. Caused by Instrument Repeatability.Setpoint Lowered.Switches Will Be Replaced During Future Refueling Outage
ML20040F5201982-01-28028 January 1982
LER 81-072/03L-0:on 811229,core Spray Sys I Parallel Isolation Valve V-20-15 Became Inoperable in Partially Open Position.Caused by High Motor Current Drawn When Valve Close Signal Inadvertently Intiated During Valve Stroking
ML20040E4281982-01-26026 January 1982
LER 81-069/03L-0:on 811230,during Surveillance Testing,Core Spray High Drywell Pressure Switches RV-46A,RV-46B & RV-46D Tripped.Caused by Instrument Repeatability.Switches Reset. Setpoint Changed to Reflect Inherent Design Error
ML20040D7551982-01-20020 January 1982
LER 81-067/03L-0:on 811220,during Maint Testing,Scram Pilot Solenoid Valve 118 (for Control Rod Drive 14-23) Failed When Rod Was Individually Scrammed.No Plausible Cause Could Be Postulated.All Scram Solenoids Will Be Verified Operable
ML20040C6631982-01-18018 January 1982
LER 81-068/03L-0:on 811218,reactor Triple Low Water Level Indicator Switch RE18A Tripped at Monometer Reading Exceeding Tech Spec Limit.Caused by Instrument Drift.Switch Reset.Setpoint Sensors Will Be Replaced
ML20040B1501981-12-31031 December 1981
LER 81-066/03L-0:on 811201,during Surveillance Testing,Main Steam Line High Flow Sensors RE22C,RE22E & RE22F Tripped at Values Greater than Tech Specs Limit.Caused by Instrument Repeatability & Drift.Sensors Reset
ML20039G0981981-12-23023 December 1981
LER 81-065/01T-0:on 811209,shutdown Commenced to Investigate a Isolation Condenser Isolation Valve V-14-30 811203 & 04 Failure to Operate Properly.Caused by Excessive Stress on Valve Backseat & Damage to Stem Nut
ML20039G1891981-12-23023 December 1981
LER 81-062/03L-0:on 811125,core Spray Hi Drywell Pressure Switch RV46C Tripped in Excess of Tech Spec Limit.Caused by Sensor Repeatability.Sensor Recalibr
1993-07-01
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With
ML20211P6731999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With
ML20211A7051999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With
ML20209G0631999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With
ML20212H5491999-06-18018 June 1999
Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool
ML20195E7961999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With
ML20206N7431999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With
ML20205P5401999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With
ML20204C8201999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With
ML20199E4671998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With
ML20195E8321998-12-31031 December 1998
10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With
ML20198D2091998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With
ML20195J8591998-11-12012 November 1998
Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan
ML20195C4271998-11-0606 November 1998
Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle
ML20155J3021998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With
ML20154R4981998-10-20020 October 1998
Core Spray Sys Insp Program - 17R
ML20154L3051998-10-14014 October 1998
Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage
ML20154Q3371998-09-30030 September 1998
Rev 8 to Oyster Creek Cycle 17,COLR
ML20154L5571998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With
ML20151V6311998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With
ML20237D5691998-08-31031 August 1998
Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification
ML20237D5711998-08-18018 August 1998
Rev 0 to SE-000222-002, Core Plate Wedge Installation
ML20237B0131998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station
ML20236R0511998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Oyster Creek Nuclear Generating Station
ML20249B2981998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Oyster Creek Nuclear Station
ML20248F3531998-05-21021 May 1998
Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted
ML20247F1891998-05-0505 May 1998
Risk Evaluation of Post-LOCA Containment Overpressure Request
ML20247G0581998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Oyster Creek Nuclear Generating Station
ML20216K0341998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Oyster Creek Nuclear Generating Station
ML20151Y4651998-03-31031 March 1998
Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept
ML20217A4631998-03-23023 March 1998
Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively
ML20212E2291998-03-0404 March 1998
Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected
ML20216J0841998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Oyster Creek Nuclear Generating Station
ML20203B2781998-02-16016 February 1998
10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures
ML20203A3801998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Oyster Creek Nuclear Generation Station
ML20198P1791997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Oyster Creek Nuclear Station
ML20217C7591997-12-31031 December 1997
1997 Annual Environmental Operating Rept for Oyster Creek Nuclear Generating Station
ML20197E9131997-11-30030 November 1997
Monthly Operating Rept for Nov 1997 for Oyster Creek Nuclear Station
ML20199E4561997-11-13013 November 1997
Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant
ML20199D4381997-10-31031 October 1997
Monthly Operating Rept for Oct 1997 for Oyster Creek Nuclear Station
ML20202E8511997-10-21021 October 1997
Rev 0 to Scenario 47, Gpu Nuclear Oyster Creek Nuclear Generating Station Emergency Preparedness (Nrc/Fema Evaluated) 1997 Biennial Exercise. Pages 49 & 59 of Incoming Submittal Were Not Included
ML20211M9481997-10-0303 October 1997
Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification
ML20198J7361997-09-30030 September 1997
Monthly Operating Rept for Sept 1997 for Oyster Creek Nuclear Generating Station
ML20211B7461997-09-24024 September 1997
Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl
ML20210V0181997-08-31031 August 1997
Monthly Operating Rept for Aug 1997 for Oyster Creek Nuclear Generating Station
ML20210L2961997-07-31031 July 1997
Monthly Operating Rept for Jul 1997 for Oyster Creek Nuclear Station
ML20149F9961997-07-18018 July 1997
Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station
ML20196H0111997-07-11011 July 1997
Special Rept 97-001:on 970620,removed High Range Radioactive Noble Gas Effluent Monitor (Stack Ragems) from Service to Allow Secondary Calibr IAW Master Surveillance Schedule. Completed Calibr on 970628 & Returned Stack Ragems to Svc
ML20210L3081997-06-30030 June 1997
Corrected Page to MOR for June 1997 for Oyster Creek Nuclear Generating Station
ML20141H2051997-06-30030 June 1997
Monthly Operating Rept for June 1997 for Oyster Creek Nuclear Station
1999-09-30
[Table view] |
Text
~
U.1. NUCLEAR REtULATCGY COMMISSION N2C FO)[M }64 (7 771 * --
LICENSEE EVENT REPORT CCNTRCL BLOCK. l l l ! l l
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O l C ! P l141 l@l yqEt43EE CODE 15 0l Ol -l 0 UCENSEl 0l 0N6Me l 0ERl 0 l - l 0 l 025 l@l 24 411 uCENSEl1 l1 l140l@l 97 Gl T 64l@
TYPE Cos T g3:,," 3 l L l@l 0 l 5 l0 l0 10 l2 l1 l9 @l 1l 2 l 0 l 4 l 8 l 0 @l1121280 l318 l0 Felil 74 7S 7 8 60 68 QQCK ET NWUS ER 68 69 EVENT CAfg MEPORT QATE EVENf CESCRIPTION AND PRC8AELE CCNSECUENCES h Ie 1:l t During surveillance testing, the Main Stea:n Line high flow senscrs.. I
,o,3, l RE-22C and R'E-22G tripped at values greater than the limit of 97.5 psig I g o ,, , ; given in the Technical Specifications, Table 3.1.1, iten B.2. 'Ihe trip I i333, ; point values were 98.5 psig for both sensors. The safety significance I ic !e ! i is considered nuninal because the redundant switches RE-22D and RE-22H I
- c ; ; ; would have actuated at the desired level to initiate the required nnin [
,,,3, ; steam isolation functions. l x< sc SYSTEM CAUSE CAUSE COM8 VALV E 0003 .CCOE 3680002 00MP:NE*:7 000E Sut:0:5 ty200 t ioi9i l C l C l@ lX l@ l Z l@ lI lN lS lT lR IU l h l E l @ (Z _j h 20 7 a 2 13 tt 12 13 16 19
, SECU ENTI AL CCCUARENCE RE' CAT 4 EvtS6CN gge so EVENT YEAR REPORT NC. COOE TYPE N O.
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_si 22 :s 24 26 27 :s :s :o 22 fAEN 'a'CTY84 oui ET 57ESE' wouas #5:^dEE s Pc'"$$s. "sO',8EI' uSUs*2CEIEa l;JE l@l34 Cl@ l35 Zl@ lZl@
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42 43 44 47
- CAusE CESCRIPTICN AND CORRECTIVE ACTIONS h i
[i;ol l The cause of the occurrence was due to instrument repeatability. Sensor I
[,,,, ;RE-22C was reset tc trip within the desired level, yet sensor RE-22G had 1
, , , , , ,to have a microswitch replaced before it would reset to trip at the I i
- ,, ,,, gproper value. 'Ihe PORC has reuawaded that these switches be replaced I
- ,, , , , ;with a suitable qualified model. . ;
I 80 7 8 9 f A %PCWER CTHER STATUS isCO R DISCOVERY 0ESCRIPTTON h L,'_L5J l E l@ l 0l 9 l 432l@ln NA l [B_j @ l Surveillance Test l e ,g, , 4 * * . '
.EuAsE LoCAneN o .EuA E @ 1 li Is l W @o ePat u Astl AucuNT NA Zl@l eP AcuviTY es l
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@ NA l l 7 8 9 to it 30 i *ERSONNEL EXPCSURES I NupeER TYPE OESCMtPTICN 39 l1171 l 0 l 0 l 0 l@l Z l@l NA l ;
, PSPSONNEt tNJU IES Nywegm 3 ESCRIPTICN NA l 11 l'4 l l 0 l 0 l 011l@l12 7 8 9 30
' LCSS 08 Cm CAMAGE TO PAQUTY Q TY'E OEScal* TION N/
NA ITTT1 4 9 l Z l@l10 l 7 30
- ,ssu 1 : I o f (_Y.jt
@TEScai, Weekly Tic,@News Release J01050 M i NRC USE ONLY .
j l lII!li1ll1I!!5 go . -
A a 9 to 68 49 Michael J. Fitzgerald (609) 693-6038 NAME OF P9E8ARER PHONE: 3