Similar Documents at Perry |
---|
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
[Table view] |
Text
' '
ff :d
~
[ , . -
a n 7 7
x,
.b'~ % ' 8 ,
r E* iTHELCLEVELAND; ELECTRIC ILLU911NATING COMPANY .
1
' P.O. BOX. 97 5 , PERRY, OHIO 44061 ; 5 ' TELEPHONE (216) 269 3737' 5- ADDRESS 10 CENTER ROAD FROM CLEVELAND: 479 1200 A . TELEX: 241599 :
ANSWERBACK: CEI PRYO -
. Al Kaplan; Serving The Best Location h the Nation k PERRY NUCLEAR POWER PLANT
( YCE PRESIDENT : r y L i
.. NUCLEAR GROUP '
January 5~ 1990 PY-CEI/NRR-1117 L' b
.s i
U
- U.S. Nuclear Regulatory Commission-g- : Document Control Desk l l g. ~ Washington,..D.C. . ~20555' r
- Perry Nuclear Power Plant;
_ Docket No.'50-440
~.l LER 89-031
Dear Sir:
. . . 1 Enclosediis Licensee Event Report 89-031 for the ' Perry Nuclear Power Plant.
'Verytruly.yours{
i
-$? &
Al Kaplan. ;
Vice President <
Nuclear Group I*
AK/nje
'I
Enclosure:
LER 89031 i cc:. T..Colburn NRC Resident Inspector U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 ftL%
' f hil S
106 900105 I OCK 05000440 ,
PDC l
+ w -
+g- y w -y ,. w --- . we e -em.mv er
h es#C PORM 308 U.S. CUCLE A A E E1ULATORY CDeeMesS60ef LAS) apPROVt0 OMG NO. 31604104 J' ., . EKPl7.18 C/30/92
$$7meAf tD SURDEN PGA RESPONSE TO COMPLY WTH THis to,fa'.'?"Ala #r'LA 'f "T*L'AtC"* * "oi LICENSEE EVENT REPORT (LER) "E "."!Ts'Uc*
V ORY 188 Nw H GT N 66 AND THE PaPfftwoRK REDUCTION PROJECT (31604104L OFFICE OF MANaottetNT AND BUDGET, WASHINGTON,0C 20603.
- ACILITY esaadt HD DOCKET esuaESER (21 PAGE '31
' Perry Nuclear Power Plant, Unit I o ls t o lo l o l 4l4 l0 1 loFl0 l 4 T"
Design Limitations Result in High Differential Flow and High Differential Temperature Reactor Water Cleanup System Containment Isolations tyENT DAff (Si LER NURABER 461 REPORT DAf t 171 OTMER F ACILITIES terv0LV4D let MONTH DAY YEAR YtAR -
"'g0 h"' "'ug L'.ONTM OAV YEAR C8LaTv maases DOCKET NUMS$R4SI O 15101010 1 1 I Ij 2 8 9 0l 6 8l9 0l3l1 0l0 0l1 0l 5 9l0 o isto go ici l l
,,,,,,,,,, Tum REPORT M svenuTTio evReUANT TO T e RiovimeMeNT De se C,R t <C s ., .< a w.a.s on M004 tel I 30.402M 30 400tel - g 08.734 sit 2H.I 73.714tl powgm 30. deb 4sH1Hil 08.38tsH11 00.734sH3Het 72.714sl
'!7.P 1r 0 g 0 meesmnHe
"="'"""
[ nauHai
[ es.n wH H.c
[ g gs g y ys,e,
%LFW M ' '3 ,
e 30mteH1HM 84.73teH2Hal 00.73tsH3Hissimi
~*
30.eGS4sil1Het 98.78tsH2Hl4H 08.734eH2Hel LICENSEE CONTACT FOR THl4 LIR litt NJ.ME TELEPHONE NUhetER ARtA CODE Henry Hegrat, Compliance Engineer, Extension 6855 2 g 1; 6 2 i 5,9, ;3 i7 93 l7 ,
COMPL 78 Om uNa ,OR sACn COMPONaNT AiLuR oneCRiseo iN tuis Ap0RT n3i l
"^gc-CAun systeu COMPOwNt' "'W C- "ig,!!' .
, CAuse sv Tsu COMPONiNT agg,!^j;5 1 sN s i
' ' i i l I I I I I '
I i t i l l l 1
l I l l 1 l l '
I I I I I I I '
-i SUPPLEteENTAL HPORT EMPtCTED lien MONTH DAY YEAR SUtusseON
~i] vu in ,.s. . anceTro sUewss,Oa, oA fas lo 0 (3 0 l6 910 i AaGr AACT I& eave so f 400 assew. ata, aseresansepay reressa sapeassee typewnnen enes, 006 On December 6, 1989 and on December 15, 1989, Reactor Water' Cleanup (RWCU) System containment isolations occurred due to high differential temperature in the RWCU Pump Room ventilation. On December 8, 1989, an RWCU System isolation occurred due to indicated high differential flow. Af ter all three events, Operations verified that no actual RWCU leakage occurred and returned the system to service.
The cause of the December 6 and December 15, 1989 events was a design deficiency.
An engineering evaluation has determined that the location of leak detection thermocouples outside of the RWCU pump rooms resulted in excessive differential temperature readings during normal operation. As a result, increases in l differential temperature caused by minor ventilation or system fluctuations resulted in unnecessary RWCU System containment isolations. The cause of the l December 8, 1989 event is a previously identified design deficiency in the leak l detection / differential flow circuitry setpoint and/or time delay during RWCU system startup.
In order to prevent recurrence of the differential temperature isolations, leak detection thermocouples have been relocated to enhance the validity of differential temperature measurement. A comprehensive evaluation of potential RWCU system design changes and operating procedure revision is being performed to prevent l unnecessary system containment isolations due to indicated high di'ferential flow.
- A supplemental report will be provided upon completion of this evaluation and l determination of appropriate corrective action.
N,,C F.rm 300 (6498
v
, cos g,- .
. u Nucu.. ...U6. ,,,,,,,,,,,,,,,,,,,,,
E x,in t5. 4130'92 LICENSEE EVENT REPORT (LER) '#l",','.',%'dOdCo"'!?o"'d,'%'f7A' N.".'",'!
TEXT CONTINUATION !?""A",'o'.WM'"?ai3Cf%RE"','!JG".'
, 0*f*fi Wu,T,' .".'4M&Sa'.=WalH6N010h. DC 20603.I? %
0F MANAGEME NT AND SuDOET
,aCskl1T HAMS 04 DOCIL47 seUMet. GI Lt. NUM.t. qel PA06 tai via= " 5.W. -
"'L*.T Perry Nuclear Power Plant. Unit I o l5 l0 l0 lo l 4l4 l 0 8l 9 -
013l 1 -
0l 0 0l2 or 0 l4 YtXT M mese apen e #sen.gst, ese espesasi NRC perm W W HM On December 6, 1989, at approximately 1034, and on December 15, 1989, at approximately 1725, Reactor Water Cleanup (RWCU) [CE] System containment isolations occurred due to high differential temperature in the RWCU Pump' Room ventilation. Da December 8, 1989, at approximately 2225, an RWCU System containment isolation occurred due to indicated high differential flow. At the !
times of the events, the plant was in Operational Condition 1 (Power Operation) l at approximately 100 percent of rated thermal power. The Reactor. Pressure Vessel
[RPV) was at saturated conditions at approxinintely 1000 psig.
Prior to the December 6, 1989 event, RWCU was in operatian and the Auxiliary Building Ventilation System was using the "B" Supply and Exhaust fans. The Equipment Area Differential Temperature Recorder points, which monitor RWCU Pump Room 1 and 2 differential temperatures, were bypassed due to differential temperatures exceeding alarm setpoints; as a result, operators were monitoring the temperatures every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. At approximately 1034, during the performance of control room surveillance activities, an RWCU Pump Room 2 differential temperature switch [TDS] caused a temperature signal spike when the operator was taking his reading. This resulted in an inboard containment isolation of the RWCU System. At approximately 1059, after verifying that no steam leak existed, operators returned both RWCU pumps to service, and shifted ventilation Supply and Exhaust fans to reduce differential temperature.
Prior to the December 8, 1989 event, the RWCU system was shut down for maintenance. At approscimately 2225, while starting RWCU pump A, suction flow exceeded discharge flow by more than the 68 gpm setpoint for longer than the 45 second delay time, which resulted in an RWCU system containment isolation due to I high differential flow, despite efforts by the operators to manually trip the pump prior to exceeding the time delay setpoint. On December 9, 1989, at approximately 0255, the RWCU system was restarted with no further difficulty.
4 Prior to the December 15, 1989 event, the RWCU system was h service when both r Auxiliary Building Ventilation supply fans tripped on lov temperature resulting l in a high differential temperature in RWCU pump room 2 and subsequently an outboard RWCU system containment isolation at approximately 1725. The loss of ventilation had caused the RWCU pump room temperature to increase enough to exceed the dif ferential temperature setpoint but not the arabient temperature setpoint. At approximately 1745, operators closed the inboard RWCU system containment isolation valves. Investigation revealed the ventilation supply plenum roughing [FLT] filters to be covered with snow. The snow was removed and at 1840 a supply fan was restarted. At approximately 1955 RWCU was returned to service and at approximately 2200 all Auxiliary Building Ventilation supply plenum roughing filters were replaced.
l
)
N Cferm 305A 5498
. - - - . - _____._____s
p .
L
~
.;,, . .. Nuca. ..o m o.. .
e ,,. . . . ;
UCENSEE EVENT REPORT (LER) ',3,^','?,#"R.M",o*'!Po?'dTT%'f'lit.' &"J"4 ;
TEXT CONTINUATlON PJ".' *,MP.'Z'fi .,n"P."Jfle'0/MiPu".'
"Ei f! !
Of MAhAGEMENT 0F M .".'Ji""EUDG(t,WA.MINGTON AND.T",o*N !=GVWA t eWi DC 20603 9 ACatal, NAML til DocktY.evas.t. up t.. NUMet t.l l
,a0Ebl
.... u we n.$ a-l . Perry Nuclear Power Plant. Unit 1 0 l6 l0 l0 l0 l 4l 4l0 49 --
0l 3l 1 -- 0l0 0l 3 0F 014
" TII*c"a N T YiEe Te*EeTbE'6 and December 15, 1989 events was a design deficiency.
A temperature survey of the RWCU pump room area revealed that temperature inside i the pump rooms were within the normal expected range and that the ventilation system inside the rooms was operating properly. Further engineering evaluations determined that the high differential temperatures (close to setpoint) were due to the location of installed leak detection system thermocouples. The location of the thermocouples outside the pump rooms resulted in an excessive indication of ventilation system differential temperature under normal operating conditions, j Additionally, as a result of previous operational problems, a 1 second time delay had been installed in the leak detection temperature trip circuitry to eliminate unnecessary isolation caused by spikes when temperatures are being read. During .
the December 6 event, with the pump room differential temperature very close to j the trip setpoint, the time delay was insufficient to prevent the signal spike from causing a spurious isolation signal. The actual differential temperature did not exceed the trip setpoint.
During the December 15, 1989 event, a severe snow storm was in progress resulting in snow intrusion into the Auxiliary Building Ventilation System and the resulting trip of system supply fans on low temperature. Because the Pump Room differential temperatures were approaching trip setpoints due to the design characteristics described above, the interruption of the Auxiliary Building Ventilation caused the trip setpoints to be exceeded before operator action could ,
be implemented to restore flow.
The cause of the December 8, 1989 event is a previously identified design deficiency in the leak detection / differential flow circuitry setpoint and/or time delay during RWCU system startup. Although several design improvements have been made, it is still difficult to obtain consistent and accurate flow measurment, for leak detection purposes, during dynamic startup conditions. This is due to i' the wide range of flows, process fluid temperatures, other system parameters and plant conditions present during RWCU system startups.
The RWCU system is used to control reactor water chemistry, reduce reactor water i inventory during startup and shutdown, and minimize temperature gradiente when y recirculation pumps are not operating. An RWCU containment isolation occurring at high reactor power will allow reactor coolant conductivity to slowly increase until the system is returned to service. The RWCU pump rooms differential temperature instrumentation is part of the Leak Detection system, designed to isolate the RWCU containment penetrations should an RWCU system leak develop in the RWCU pump room. Since no system leakage or actual RWCU Pump Room high differential temperature conditions existed and the system responded as designed, the events on December 6 and December 15, 1989 are not considered to be safety significant.
The Differential Flow portion of the Leak Detection System compares RWCU suction 1
flow to both the flow returning to the reactor vessel and blowdown flow to radwaste or the main condenser. All three flows are summed to generate an indication of differential flow. An RWCU high differential flow signal indicates the suction flow entering the system is not being discharged via normal flow paths (reactor vessel, and blowdown to radwaste or main condenser). This could N.C Penn 306A (6491 I i
POntp300A U.S. NWCLEA wt9WLATOR f C0edM8009du
- E no,,ls .m, LICENSEE EVENT REPORT (LER) 'Ss",!,",dugNyo"'j3*vnT'*, 'f**,'l ,T.".M TEXT CONTINUATION !?,""A*lA%5.'",fd M'.M','eOll37 'v"/ *'Cft" f!
u t ta^l = 2 ".",'*4? W ! E n ? % *4 0 M i,Ci Of uANAGlutNT AND supGtt.naswiNOTON. DC 20503.
8 AC,41YY haast IM DOCEtt NutdSSR E2) LlR NUMSER t4) PAQt (3)
! "aa "Ot.W.',' : "'Jf,T:
Perry Nuclear Power Plant. Unit 1 o l6 j o lo lo l4 l 4l0 49 - q 3l 1 -
0l 0 q4 0F 0l4 TEXT W nesse apose a soesseel, var sessener N#C 7e= JmeU qth be the result of a line break in the RWCU system. High differential flow of greater than 68 gpm for a duration of 45 seconds generates an isolation signal from the Leak Detection System. The 45 second time delay normally allows for system flow transients when changing operational configurations. Since no RWCU high differential flow existed due to a leak and the systems did respond as designed to the high indicated differential flow, the December 8, 1989 event is not considered to be safety significant.
Other events involving RWCU System Containment 1solations due to high differential flow have been discussed in LER's89-025, 88-039,88-013, 88-002 and i 87-074. Other events involving RWCU System Containment Isolations due to high differential temperature or Auxiliary Building Ventilation System problems have been discussed in LER's88-010 and 89-004.
After the December 6, 1989 event, operators were instructed to bypass the leak detection isolation logic when performing channel checks on the temperature instrumentation until design improvements could be implemented. A design modification was developed and implemented to change the locations of the thermocouples monitoring temperatures outside of the pump rooms, improving the validity of differential temperature instrumentation measurements without j compromising the ability to detect actual leakage conditions. Additionally potential improvements to prevent snow intrusion for the Auxiliary Building Ventilation System supply plenum are being investigated.
To prevent recurrence of the event on December 8, 1989, a setpoint/ time delay change is being evaluated; however, this would necessitate changes to Technical Specifications. Because significant progress has been made over the last few years on reducing the number of spurious RWCU isolations due to differential flow 4 signals, and because the most recent events have occurred during system startup, a comprehensive evaluation of potential corrective actions is being performed.
These potential solutions include system design modifications and operating
( procedure revisions in addition to the previously mentioned Technical Specification changes. A supplemental report will be provided upon completion of this evaluation and determination of appropriate corrective actions.
Energy Industry Identification System Codes are identified in the text as [XX].
NMC f orm 306A 16491