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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18011A5401994-08-10010 August 1994 LER 94-017-00:on 940711,automatic Isolation of RHR Sys Shutdown Cooling Suction Outboard Containment Isolation Valve Occurred Due to Inadequate Work Order.Work Order Process for I&C Work Orders Will Be reviewed.W/940810 Ltr ML20046C5721993-08-0606 August 1993 LER 93-015-00:on 930709,unexpected RRP Fast to Slow Speed Downshift Occurred Due to Failure of Both RRP Suction Temp Rtd.Replaced & Returned RTD to Mfg for Failure Analysis. W/930806 Ltr ML20046B7811993-08-0202 August 1993 LER 93-014-00:on 930703,TS 3.0.3 Entered Due to Failure of Racs Power Supply.Replaced 5 Volt Power Supply in Racs cabinet.W/930802 Ltr ML20045G7201993-07-0808 July 1993 LER 93-013-00:on 930608,control Room HVAC Sys Train a Supply Fan Tripped on Overcurrent,Resulting in Both Sys Trains Being Unavailable.Caused by Motor Winding Insulation Failure.Motor Repaired by mfg.W/930708 Ltr ML20045G2171993-07-0707 July 1993 LER 93-012-00:on 930607,noted That HPCS Initiation Signal Resulted in Auto Start of Div 3 DG & ESW Sys.Caused by Failure of Div 3 Reserve Battery Charger.Procedures Used for Insp & Maint of Battery Being modified.W/930707 Ltr ML20044F2161993-05-19019 May 1993 LER 93-011-00:on 930419,identified That Excessive Strainer Differential Pressure Across RHR Suction Strainers Could Have Compromised Long Term Cooling During LOCA Operation. Caused by Inadequate Program requirements.W/930519 Ltr ML20044B6771993-02-22022 February 1993 LER 93-004-00:on 930121,MOV Testing of Main Steam Line Drain & Bypass Outboard Isolation Valve Indicated That Thrust Less than Design Thrust to Close Valve Under Accident Conditions. Review,Per GL 89-10 in progress.W/930222 Ltr ML20029B6431991-03-0808 March 1991 LER 91-007-00:on 910209,pressure Switch Instrument Drift Caused Automatic Start of Annulus Exhaust Gas Treatment Sys. Caused by Component Failure.Switch Recalibrated to Adjust Setpoints to Proper value.W/910308 Ltr ML20029B0971991-03-0101 March 1991 LER 91-006-00:on 910202,inboard Isolation Valves Closed on RWCU Delta Flow High Signal During Removal of RWCU Filter from Svc.Caused by Personnel Error.Sys Operating Instruction Being revised.W/910301 Ltr ML20029A6451991-02-22022 February 1991 LER 91-005-00:on 910129,discovered That Two Power Supplies Had Excessive Ripple Effect When All Rods Pushbutton Depressed,Resulting in Loss of Scram Accumulator Fault Indication.Caused by Personnel error.W/910222 Ltr ML20029A3321991-02-15015 February 1991 LER 91-004-00:on 910120,three Reactor Water level-high (Level 8) Channels Inoperable Due to Blown Fuse.Caused by Voltage Spike.Circuitry Associated W/Trip Relays Modified. W/910215 Ltr ML20028H7521991-01-25025 January 1991 LER 90-041-00:between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo issued.W/910125 Ltr ML20024F7421990-12-14014 December 1990 LER 90-033-00:on 901120,Train B of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode.Caused by Inadequate Instruction.Procedure Revised Re Correct Guidance During Loss of Power to Bus K-1-N ML20024F7411990-12-14014 December 1990 LER 90-032-00:on 901116,disconnecting Wires to Test Relay Contact Resulted in RHR a Shutdown Cooling Sys Isolation. Caused by Procedure Deficiency & Inadequate Instructions. Personnel Trained Re Review of Work Orders ML20028G9181990-09-28028 September 1990 LER 90-020-00:on 900831,maint Activities on Control Room Emergency Recirculation Sys Resulted in Tech Spec Violation & Compromise of Safety Sys.Caused by Program Deficiency. Maint Acitivities & Insp Being revised.W/900928 Ltr ML20044B1021990-07-13013 July 1990 LER 90-013-00:on 900619,discovered That Main Steam Line Radiation Monitor C Inoperable for Greater than Time Allowed by Tech Specs 3.3.1.a & 3.3.1.b.Caused by Personnel Error. Personnel counseled.W/900713 Ltr ML20043H4801990-06-20020 June 1990 LER 90-011-00:on 900521,discovered That Divisional LPCI & LPCS Sys Inoperable in Excess of Tech Spec Action Limits Between 871119-23 & 891218-22.Caused by Procedural Deficiency.Sys Operating Instruction revised.W/900620 Ltr ML20043H5251990-06-20020 June 1990 LER 90-010-00:on 900521,Tech Spec Action Requirements Not Implemented for Inoperable Control Rod Scram Accumulators. Caused by Inadequate Procedures & Malfunctioning Transformer.Analyzer Reset & Leakage monitored.W/900620 Ltr ML20043H3841990-06-18018 June 1990 LER 90-009-00:on 900517,RHR Sys B HX Bypass Valve Failed to Reposition on Demand,Rendering RHR Sys Train Operable for Containment Spray Cooling Mode of Operation.Caused by Failure of Valve Stem Nut.Stem Nut replaced.W/900618 Ltr ML20043E5711990-06-0808 June 1990 LER 89-030-01:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Failure of Two Control Rods Caused by Improper Seat Matl in Associated Scram Pilot Solenoid Valves.Instructions revised.W/900608 Ltr ML20043A7801990-05-18018 May 1990 LER 90-007-00:on 900418,ruptured Seal on Outer Door of Upper Containment Airlock Occurred Causing Loss of Containment Integrity.Caused by Inadequate Communications & Equipment Failure.Seal on Outer Door Replaced ML20043A8451990-05-18018 May 1990 LER 90-008-00:on 900420,unexpected Isolation of RWCU Sys Occurred.Caused by Component Failure.Faulty Transmitter Transmitter Identified & Replaced ML20042G7731990-05-11011 May 1990 LER 90-006-00:on 900411,control Room Emergency Recirculation Sys Found to Be Inoperable & Tech Specs 3.0.3 Entered on Three Occasions.Caused by Operator Error & Component Failure,Respectively.Personnel retrained.W/900511 Ltr ML20012D8151990-03-24024 March 1990 LER 90-003-00:on 900222 & 23,discovered That Stroke Time Measurements Not Performed in Both Directions for motor- Operated Valves in safety-related Sys.Caused by Program Deficiency.Procedural Enhancement implemented.W/900323 Ltr ML20011E1861990-02-0202 February 1990 LER 90-001-00:on 900107,reactor Scram Occurred After Improper Transfer of 480-volt Ac Power Supplies Resulted in Total Loss of Feedwater Flow & Power Interruption.Caused by Personnel Error.Operator Counseled & Instructions Revised ML20011E1871990-02-0202 February 1990 LER 90-002-00:on 900107,RCIC Sys Isolated Due to High Differential Temp Signal Detected Across RCIC Room Cooler Following Reactor Scram Due to Loss of Feedwater Flow. Caused by Design Deficiency.Procedures Re Flow Rate Revised ML19354E0961990-01-19019 January 1990 LER 89-032-00:on 891228 & 900105,HPCS Sys Declared Inoperable Due to Inoperability of Div 3 Battery.Caused by Low Pilot Cell Voltage,Cell W/Slow Electrolyte Leak & Blown Power Fuse.Fuse & Hydromotor Pump replaced.W/900119 Ltr ML20005E6851990-01-0505 January 1990 LER 89-031-00:on 891206,08 & 15,RWCU Sys Isolations Occurred.Caused by Design Deficiency & Deficiency in Leak Detection/Differential Flow Circuitry Setpoint &/Or Time Delay.Leak Detection Thermocouples relocated.W/900105 Ltr ML20005E0821989-12-26026 December 1989 LER 89-030-00:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Caused by Failure to Return Scram Pilot Valves Used for Rods to Mfg After Recall. Surveillance Instruction revised.W/891226 Ltr ML19354D5991989-12-17017 December 1989 LER 89-029-00:on 891117,heater Bay/Turbine Bldg Vent Gaseous Effluent Particulate & Iodine Samples Not Continuously Collected as Required by Tech Spec 3.3.7.10.Caused by Procedure Deficiency.Procedure revised.W/891217 Ltr ML19325E5901989-11-0303 November 1989 LER 89-028-00:on 891008,concluded That Operation of Fuel Pool Cooling & Cleanup Sys to Upper Containment Pools Caused Containment Vacuum Breaker Actuations.Caused by Unrecognized Sys Interaction.Operating Instruction revised.W/891103 Ltr ML19324B1241989-10-27027 October 1989 LER 89-024-01:on 890723,entry Into Operational Condition 2 Completed W/Suppression Pool Makeup Sys Inoperable & on 890725,vent Valve on Ref Leg Found Open & Uncapped.Caused by Personnel Error.Personnel counseled.W/891027 Ltr ML19325D5121989-10-20020 October 1989 LER 89-027-00:on 890925,loss of Control Power to Emergency Svc Water Sys Pump Discharge Valve a Rendered Sys Inoperable.Caused by Personnel Error Re Jumper Placement. Involved Technicians counseled.W/891020 Ltr ML19325D1581989-10-13013 October 1989 LER 88-025-01:on 880618,reactor Protection Sys (RPS) Bus Inadvertently Deenergized,Resulting in Full RPS Actuation. Caused by Personnel Error W/Contributing Factor of Poor Human Factors Design.Info Tag Installed on Power Switch ML19325D1591989-10-13013 October 1989 LER 89-026-00:on 890913,reactor Thermal Power Level Exceeded That Specified in OL Due to Unexpected Recirculation Sys Flow Control Transient.Caused by Component Failure.Failed Isolation Solenoid Valve Replaced ML19325D9331987-03-27027 March 1987 LER 87-010-00:on 870228,operators Failed to Place at Least One Reactor Protection Sys Trip Sys in Tripped Condition within 1 H.Caused by Personnel Error & Deficient Procedure. Personnel Counseled & Procedures Revised ML19325C1171987-03-27027 March 1987 LER 87-009-00:on 870227,failure of Two Control Air Solenoid Valves Rendered Div I & II Diesel Generators Inoperable. Cause Unknown.Solenoid Valves Replaced & Plant Administrative Procedure PAP-1705 revised.W/870327 Ltr 1994-08-10
[Table view] Category:RO)
MONTHYEARML18011A5401994-08-10010 August 1994 LER 94-017-00:on 940711,automatic Isolation of RHR Sys Shutdown Cooling Suction Outboard Containment Isolation Valve Occurred Due to Inadequate Work Order.Work Order Process for I&C Work Orders Will Be reviewed.W/940810 Ltr ML20046C5721993-08-0606 August 1993 LER 93-015-00:on 930709,unexpected RRP Fast to Slow Speed Downshift Occurred Due to Failure of Both RRP Suction Temp Rtd.Replaced & Returned RTD to Mfg for Failure Analysis. W/930806 Ltr ML20046B7811993-08-0202 August 1993 LER 93-014-00:on 930703,TS 3.0.3 Entered Due to Failure of Racs Power Supply.Replaced 5 Volt Power Supply in Racs cabinet.W/930802 Ltr ML20045G7201993-07-0808 July 1993 LER 93-013-00:on 930608,control Room HVAC Sys Train a Supply Fan Tripped on Overcurrent,Resulting in Both Sys Trains Being Unavailable.Caused by Motor Winding Insulation Failure.Motor Repaired by mfg.W/930708 Ltr ML20045G2171993-07-0707 July 1993 LER 93-012-00:on 930607,noted That HPCS Initiation Signal Resulted in Auto Start of Div 3 DG & ESW Sys.Caused by Failure of Div 3 Reserve Battery Charger.Procedures Used for Insp & Maint of Battery Being modified.W/930707 Ltr ML20044F2161993-05-19019 May 1993 LER 93-011-00:on 930419,identified That Excessive Strainer Differential Pressure Across RHR Suction Strainers Could Have Compromised Long Term Cooling During LOCA Operation. Caused by Inadequate Program requirements.W/930519 Ltr ML20044B6771993-02-22022 February 1993 LER 93-004-00:on 930121,MOV Testing of Main Steam Line Drain & Bypass Outboard Isolation Valve Indicated That Thrust Less than Design Thrust to Close Valve Under Accident Conditions. Review,Per GL 89-10 in progress.W/930222 Ltr ML20029B6431991-03-0808 March 1991 LER 91-007-00:on 910209,pressure Switch Instrument Drift Caused Automatic Start of Annulus Exhaust Gas Treatment Sys. Caused by Component Failure.Switch Recalibrated to Adjust Setpoints to Proper value.W/910308 Ltr ML20029B0971991-03-0101 March 1991 LER 91-006-00:on 910202,inboard Isolation Valves Closed on RWCU Delta Flow High Signal During Removal of RWCU Filter from Svc.Caused by Personnel Error.Sys Operating Instruction Being revised.W/910301 Ltr ML20029A6451991-02-22022 February 1991 LER 91-005-00:on 910129,discovered That Two Power Supplies Had Excessive Ripple Effect When All Rods Pushbutton Depressed,Resulting in Loss of Scram Accumulator Fault Indication.Caused by Personnel error.W/910222 Ltr ML20029A3321991-02-15015 February 1991 LER 91-004-00:on 910120,three Reactor Water level-high (Level 8) Channels Inoperable Due to Blown Fuse.Caused by Voltage Spike.Circuitry Associated W/Trip Relays Modified. W/910215 Ltr ML20028H7521991-01-25025 January 1991 LER 90-041-00:between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo issued.W/910125 Ltr ML20024F7421990-12-14014 December 1990 LER 90-033-00:on 901120,Train B of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode.Caused by Inadequate Instruction.Procedure Revised Re Correct Guidance During Loss of Power to Bus K-1-N ML20024F7411990-12-14014 December 1990 LER 90-032-00:on 901116,disconnecting Wires to Test Relay Contact Resulted in RHR a Shutdown Cooling Sys Isolation. Caused by Procedure Deficiency & Inadequate Instructions. Personnel Trained Re Review of Work Orders ML20028G9181990-09-28028 September 1990 LER 90-020-00:on 900831,maint Activities on Control Room Emergency Recirculation Sys Resulted in Tech Spec Violation & Compromise of Safety Sys.Caused by Program Deficiency. Maint Acitivities & Insp Being revised.W/900928 Ltr ML20044B1021990-07-13013 July 1990 LER 90-013-00:on 900619,discovered That Main Steam Line Radiation Monitor C Inoperable for Greater than Time Allowed by Tech Specs 3.3.1.a & 3.3.1.b.Caused by Personnel Error. Personnel counseled.W/900713 Ltr ML20043H4801990-06-20020 June 1990 LER 90-011-00:on 900521,discovered That Divisional LPCI & LPCS Sys Inoperable in Excess of Tech Spec Action Limits Between 871119-23 & 891218-22.Caused by Procedural Deficiency.Sys Operating Instruction revised.W/900620 Ltr ML20043H5251990-06-20020 June 1990 LER 90-010-00:on 900521,Tech Spec Action Requirements Not Implemented for Inoperable Control Rod Scram Accumulators. Caused by Inadequate Procedures & Malfunctioning Transformer.Analyzer Reset & Leakage monitored.W/900620 Ltr ML20043H3841990-06-18018 June 1990 LER 90-009-00:on 900517,RHR Sys B HX Bypass Valve Failed to Reposition on Demand,Rendering RHR Sys Train Operable for Containment Spray Cooling Mode of Operation.Caused by Failure of Valve Stem Nut.Stem Nut replaced.W/900618 Ltr ML20043E5711990-06-0808 June 1990 LER 89-030-01:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Failure of Two Control Rods Caused by Improper Seat Matl in Associated Scram Pilot Solenoid Valves.Instructions revised.W/900608 Ltr ML20043A7801990-05-18018 May 1990 LER 90-007-00:on 900418,ruptured Seal on Outer Door of Upper Containment Airlock Occurred Causing Loss of Containment Integrity.Caused by Inadequate Communications & Equipment Failure.Seal on Outer Door Replaced ML20043A8451990-05-18018 May 1990 LER 90-008-00:on 900420,unexpected Isolation of RWCU Sys Occurred.Caused by Component Failure.Faulty Transmitter Transmitter Identified & Replaced ML20042G7731990-05-11011 May 1990 LER 90-006-00:on 900411,control Room Emergency Recirculation Sys Found to Be Inoperable & Tech Specs 3.0.3 Entered on Three Occasions.Caused by Operator Error & Component Failure,Respectively.Personnel retrained.W/900511 Ltr ML20012D8151990-03-24024 March 1990 LER 90-003-00:on 900222 & 23,discovered That Stroke Time Measurements Not Performed in Both Directions for motor- Operated Valves in safety-related Sys.Caused by Program Deficiency.Procedural Enhancement implemented.W/900323 Ltr ML20011E1861990-02-0202 February 1990 LER 90-001-00:on 900107,reactor Scram Occurred After Improper Transfer of 480-volt Ac Power Supplies Resulted in Total Loss of Feedwater Flow & Power Interruption.Caused by Personnel Error.Operator Counseled & Instructions Revised ML20011E1871990-02-0202 February 1990 LER 90-002-00:on 900107,RCIC Sys Isolated Due to High Differential Temp Signal Detected Across RCIC Room Cooler Following Reactor Scram Due to Loss of Feedwater Flow. Caused by Design Deficiency.Procedures Re Flow Rate Revised ML19354E0961990-01-19019 January 1990 LER 89-032-00:on 891228 & 900105,HPCS Sys Declared Inoperable Due to Inoperability of Div 3 Battery.Caused by Low Pilot Cell Voltage,Cell W/Slow Electrolyte Leak & Blown Power Fuse.Fuse & Hydromotor Pump replaced.W/900119 Ltr ML20005E6851990-01-0505 January 1990 LER 89-031-00:on 891206,08 & 15,RWCU Sys Isolations Occurred.Caused by Design Deficiency & Deficiency in Leak Detection/Differential Flow Circuitry Setpoint &/Or Time Delay.Leak Detection Thermocouples relocated.W/900105 Ltr ML20005E0821989-12-26026 December 1989 LER 89-030-00:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Caused by Failure to Return Scram Pilot Valves Used for Rods to Mfg After Recall. Surveillance Instruction revised.W/891226 Ltr ML19354D5991989-12-17017 December 1989 LER 89-029-00:on 891117,heater Bay/Turbine Bldg Vent Gaseous Effluent Particulate & Iodine Samples Not Continuously Collected as Required by Tech Spec 3.3.7.10.Caused by Procedure Deficiency.Procedure revised.W/891217 Ltr ML19325E5901989-11-0303 November 1989 LER 89-028-00:on 891008,concluded That Operation of Fuel Pool Cooling & Cleanup Sys to Upper Containment Pools Caused Containment Vacuum Breaker Actuations.Caused by Unrecognized Sys Interaction.Operating Instruction revised.W/891103 Ltr ML19324B1241989-10-27027 October 1989 LER 89-024-01:on 890723,entry Into Operational Condition 2 Completed W/Suppression Pool Makeup Sys Inoperable & on 890725,vent Valve on Ref Leg Found Open & Uncapped.Caused by Personnel Error.Personnel counseled.W/891027 Ltr ML19325D5121989-10-20020 October 1989 LER 89-027-00:on 890925,loss of Control Power to Emergency Svc Water Sys Pump Discharge Valve a Rendered Sys Inoperable.Caused by Personnel Error Re Jumper Placement. Involved Technicians counseled.W/891020 Ltr ML19325D1581989-10-13013 October 1989 LER 88-025-01:on 880618,reactor Protection Sys (RPS) Bus Inadvertently Deenergized,Resulting in Full RPS Actuation. Caused by Personnel Error W/Contributing Factor of Poor Human Factors Design.Info Tag Installed on Power Switch ML19325D1591989-10-13013 October 1989 LER 89-026-00:on 890913,reactor Thermal Power Level Exceeded That Specified in OL Due to Unexpected Recirculation Sys Flow Control Transient.Caused by Component Failure.Failed Isolation Solenoid Valve Replaced ML19325D9331987-03-27027 March 1987 LER 87-010-00:on 870228,operators Failed to Place at Least One Reactor Protection Sys Trip Sys in Tripped Condition within 1 H.Caused by Personnel Error & Deficient Procedure. Personnel Counseled & Procedures Revised ML19325C1171987-03-27027 March 1987 LER 87-009-00:on 870227,failure of Two Control Air Solenoid Valves Rendered Div I & II Diesel Generators Inoperable. Cause Unknown.Solenoid Valves Replaced & Plant Administrative Procedure PAP-1705 revised.W/870327 Ltr 1994-08-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER PY-CEI-NRR-2289, Monthly Operating Rept for May 1998 for Perry,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Perry,Unit 1 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 PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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' N 6 . l THE CLEVELAND ELECTRIC ILLUMINATING COMPANY j P.O. DOX 97 e PERRY OHC 440s1 W TELEPHONE G18) 2664737 9 ADDRESS-10 MNTER ROAD !
FROM CLEVELAND: 4 4 1300 3 TELEX: 24160s ';
ANSWERBACK: CEtPRYO ;
Al Kaplan Serving The Best location in the Nation PERRY NUCLEAR POWER PLANT ;
ver catsain ,
NUCtl AR GHOUP . }
Jsuuary 19, 1990 l
'PY-CEI/NRR-1123 L' l k
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U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant !
Docket No. 50-440 l LER 89-032 !
Dear Sirs i
. . ?
Enclosed is Licensee Event Report 89-032 for the Perry Nuclear Power Plant. l r
e Very truly yours,.
5' Al Kaplan
~
Vice President .
Nuclear Croup AK/njc Enclosure LER 89032 ,
ect T. Colburn NRC Resident inspector +
.i U.S. Nuclear: Regulatory Commission !
799 Roosevelt Road >
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'"" " Division 3 Battery Low Electrolyte Temperature Cause High Pressure Core Spray Svarem Innnerability iv4Nt oats e ita Nuessen e nerontoave m ovata eaCitatits sNvoLvso ni i h00NtM DAY Yt&M VtAR (' b MONtM OAV Te&R I AC84'T ' awls DOCEtt NWW94 Rill ol51010lcl l l >
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On December 22, 1989, and on January 5, 1990, Unit 2 Division 3 battery electrolyte temperature was discovered to be below Technical Specification limits. Because Unit 1 Division 3 battery was inoperable due to maintenance being performed, Plant Technical Specifications required the High Pressure Core Spray (HPCS) system to be declared inoperable. Operators took actions to raise battery room temperature and declared the HPCS system operable when battery electrolyte temperatures returned to acceptable levela.
The cause of the December 22, 1989 event was Equipment Failure, specifically, a blown fuse in the battery room ventilation duct heater circuitry. Loss of the heater combined with the low heat load in the Unit 2 Division 3 battery room result'ed in the b:ttery electrolyte temperature decrease. The January 5, 1990 event was caused by a temperature control valve malfunction which allowed excess cooling water to the b:ttery room ventilation system at a time when cooling water was not desired. This also resulted in the decrease of battery electrolyte temperature.
To prevent recurrence, the blown fuse for the ventilation duct heater was replaced and the heater checked to ensure proper operation. The temperature control valve actuator hydromotor pump was replaced and the valve checked for proper operation. Additionally, operators revised the plant equipment round procedure to include checking battery room temperature once per shift, and a design change proposal to install low temperature clarm instrumentation for the battery rooms is presently being evaluated. As part of the established requalification training program, all plant licensed operators will be inst ructed on the lessons lentned f rom thin event.
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I On December 22, 1989, and on January 5, 1990, the High Pressure Core Spray [BG)
(HPCS) system was declared inoperable due to the inoperability of the associated -
Division 3 battery [EJ). At the time of both events, the plant was in Operational Condition 1 (Power Operation) at approximately 100 percent of rated ,
thermal power with the Reactor Pressure Vessel [RPV) at saturated conditions at I
approximately 1000 psig. The Unit 1 Division 3 battery [BTRY) was inoperable due to a low pilot cell voltage and a cell with a slow electrolyte leak.
On December 22, 1989, at 1027, Unit 2 Division 3 battery electrolyte temperature i was discovered to be approximately 69 degrees Fahrenheit (F). In accordance with ,
Technical Specification action requirements associated with D.C. electrical power sources, operators declared High Pressure Core Spray (HPCS) system and the Division 3 Diesel Generator inoperable and initiated troubleshooting efforts to determine the cause of the low temperature. Maintenance troubleshooting revealed -
a blown power fuse [FU) in a heater circuit for the MCC, Switchgear, and Miscellaneous Electrical Equipment Areas HVAC system [VI). The fuse was replaced and HPCS/ Division 3 operability was declared on December 23, 1989 at 0445, after the battery electrolyte tempeneture increased above 72 degrees F. All action statements of associated Technical Specifications were satisfied.
On January 5, 1990, at 0241, train "B" of the battery room ventilation system was shifted to recirculation mode due to Unit 2 Division 3 battery room temperature decreasing to 73 degrees F. The ventilation system shift was ineffective due to a malfunctioning temperature control valve [TCV) which, unknown to operators, was the initial cause of the decrease in battery room temperature. The temperature control valve remained closed approximately 50 percent instead of 100 percent as it was supposed to. The failure of the temperature control valve to completely close allowed cooling water to continue flowing to the ventilation system cooler while temperature conditions required cooling flow to be secured. As a result, the Unit 2 Division 3 battery room temperature continued to drop instead of increase as was intended. At approximately 1010, the Unit 2 Division 3 battery room temperature was discovered to be below 72 degrees F and the battery electrolyte temperature was also below 72 degrees F. Operators declared the HPCS system inoperable at that time. At 1024 operators shifted the battery room ventilation system to train "A" in recirculation mode which caused battery room temperature to increase. On January 5, 1990 at approximately 2130 Unit 2 Division 3 battery electrolyte temperature had risen to 72.9 degrees F and battery room temperature had risen to 76 degrees F. Operators then declared Unit 2 Division 3 battery, Diviaton 3 diesel s generator and HPCS system operable. ,
The cause of the December 22, 1989 event was equipment failure, specifically, a blown power fuse in the ventilation duct neater circuitry. The loss of the heater combined with the low heat load in the Unit 2 Division 3 battery room resulted in the battery electrolyte temperature decreasing below the Technical Specification limit. The absence of a battery room low temperature alarm to alert operators to low temperature conditions is: considered to be a contributing 5 factor.
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UCENSEE EVENT REPORT (LER) No'1".'. *.'"..'".9" "*.TL",",T%.#'fX &"J."i1 TEXT CONTINUATION %""#,'?IA "'.*.*."*,2.n'"f'." !T.c"'/MU".' "',EN! I
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The cause of the January 5, 1990 event was equipment malfunction. A temperature '
control valve in the Control Complex Chilled Water (KH] (CCCW) system did not close completely when its control signal required full closure. Although operators were aware of decreasing Unit 2 Division 3 battery room temperature and took action to shift to the recirculation mode which should have prevented exceeding the Technical Specification limit for electrolyte temperature, the ,
valve malfunction resulted in continued cooling of the Unit 2 Division 3 battery ,
room. Again the absence of a battery room low temperature alarm to alert ,
operators to low temperature conditions is considered to be a contributing factor as this would have provided more time to evaluate system conditions and take corrective action. >
The objective of the Division 3,125-volt de power system is to provide a 5
continuous and independent 125-volt de source of control and motive power as ;
required for HPCS system logic, HPCS diesel generator control and protection, and ,
all Division 3 related 125-volt de control. Upon loss of these control power t systems, the HPCS system is required by Technical Specification to be declared inoperable. '
i The HPCS system pumps water through a peripheral spray ring sparger mounted above ,
the reactor core. Coolant is supplied over the entire range of system operation t
pressures. The primary purpose of HPCS is to maintain reactor vessel inventory i
, after small breaks which do not depressurize the reactor vessel. HPCS also ;
provides spray cooling heat transfer during leaks in which core uncovery is.
l l calculated. During the periods of time the HPCS system was declared inoperable, l the Automatic Depressurization System and Low Pressure Core Spray, as well as the ;
l Low Pressure Coolant injection Systems were operable ensuring adequate core ,
cooling as described in Chapter 15 of the Updated Safety Analysis Report. ]
Additionally, although the batteries were required to be declared inoperable, the ,
HPCS system was not removed from service and would have automatically initiated i if required. Engineering calculations indicate that the Unit 2 Division 3 ;
battery would perform its intended function with electrolyte temperature as low i
as 65 degrees F. Therefore, these events are not considered to be safety '
significant. '
(
One other previous event involving low battery electrolyte temperature was l documented by LER 87-008. A faulty thermostat had caused Division 1 battery l electrolyte temperature to be less than 72 degrees F. The Division 1 battery room thermostat was replaced. Additionally, to address a delay by maintenance personnel in notifying the control room of their findings, maintenance personnel I were counseled to ensure prompt notification of the Unit Supervisor if Technical ;
Specification acceptance criteria is exceeded. These corrective actions could not have prevented the December 22, 1989 and January 5, 1990 events.
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Ol0 0l4 0F 0 14 rexto . = m necsei amewnn To prevent recurrence, on December 23, 1989, the blown power fuse for the battery room ventilation duct heater circuit was replaced and voltage and current readings were taken to ensure the heater was working as designed. On January 12, 1990, the CCCW temperature control valve actuator hydromotor pump was replaced due to internal leakage, and subsequently the temperature control vt,1ve was ,
tested satisfactorily in the system. Additionally, operators revised the plant i equipment round procedure to include checking battery room temperatures once per :
l shift. Finally, a previously submitted design change proposal to install low l temperature alarm instrumentation for the battery-room is presently being evaluated. As part of the established requalification training program, all '
plant licensed operators will be instructed on the lessons learned from this event.
Energy Induwtry Identification System Codes are identified in the text as [XX]. t t
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