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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 ML17313A3131998-03-21021 March 1998 LER 98-001-00:on 980301,surveillance Test Deficiency Found During Qaa Leads to TS 3.0.3/4.0.3 Entry.Caused by Personnel Error.Personnel Responsible for Inadequately Performed SR Were Coached ML17313A2251998-03-0505 March 1998 LER 93-005-00:on 930309,CR Personnel Discovered Missed TS LCO Action & Subsequently Performed Surveillance Satisfactorily.Caused by Personnel Error.Appropriate Disciplinary Action issued.W/980305 Ltr ML17313A2241998-02-26026 February 1998 LER 98-001-00:on 980130,reactor Protection & ESFAS Instrumentation Not Bypassed within one-hour Allowed by TS Occurred.Caused by Inadequate Procedures.Expectation to Detect Alarm Conditions Was Emphasized to CR Personnel ML17313A2081998-02-10010 February 1998 LER 97-007-00:on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA program.W/980210 Ltr ML17313A2041998-02-0505 February 1998 LER 97-006-00:on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program ML17313A1201997-11-12012 November 1997 LER 97-006-00:on 971020,manual Reactor Trip Occurred Due to Vibration & Bearing Temp Increases in Reactor Coolant Pump. Caused by Failed Lower Journal Bearing.Bearing Assembly Was Disassembled,Inspected & Rebuilt ML17312B7181997-10-0707 October 1997 LER 97-003-00:on 970907,inadvertent Loss of Power & EDG Start Occurred Due to Procedural Error.Changed Train a & Train B Edg/Ist ST Procedures to Consistently Reflect Proper Pretest Staging Hand switches.W/971007 Ltr ML17312B7051997-09-26026 September 1997 LER 97-003-01:on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions ML17312B5531997-07-0707 July 1997 LER 97-002-00:on 970528,SR for Core Protection Was Not Performed Due to Inadequate Procedures.Revised Procedures ML17312B5501997-07-0707 July 1997 LER 97-003-00:on 970211,notified of Trevitest Activities Indicating That Total of Seven MSSVs Had as-found Lift Set Pressures Greater than 3 Percent Allowed by TS 3.7.1.1. Investigation Conducted.Seven MSSVs replaced.W/970707 Ltr ML17312B4971997-06-13013 June 1997 LER 97-002-00:on 970531,RT Occurred.Caused by Spurious Opening of All Four Rt Switchgear Breakers.Independent Investigation of Event Being Conducted in Accordance W/Util Corrective Action Program ML17312B1461996-12-17017 December 1996 LER 96-007-00:on 961119,surveillance Test Deficiencies Were Found During GL 96-01 Review Leading to TS 3.0.3 Entries. Caused by Increase in Scope of Required Testing.Supplement Will Be submitted.W/961217 Ltr ML17312A9511996-09-0404 September 1996 LER 96-003-00:on 960809,open Auxiliary Bldg Door Caused Full Bldg Essential Filtration Inoperability.Caused by Personnel Error.C/As Under consideration.W/960904 Ltr ML17312A8641996-07-17017 July 1996 LER 96-001-00:on 960621,inaccurate Gas Calculations for Post Accident Sampling Sys Occurred.Caused by Surveillance Test Worksheet Errors.Independent Investigation of Event Being conducted.W/960717 Ltr ML17300B2541996-06-11011 June 1996 LER 96-001-01:on 960404,inappropriate Grounding of Equipment Resulted in Condition Outside Design Basis of Plant. Established Fire Watches Required for Affected Areas ML17312A8081996-06-0909 June 1996 LER 96-002-00:on 960514,Tech Spec Violation Occurred Due to Erroneous Surveillance Requirement.Caused by Incorporation of C-E Generic Ts.Investigation Being conducted.W/960609 Ltr ML17312A7751996-05-17017 May 1996 LER 96-003-00:on 960122,missed Surveillance for Logic Check of Logs 1 & 2 Safety Excore Bypasses.Caused by Procedural Error.Log Power Functional Test Revised to Check Logs 1 & 2 Bypasses Regardless of Power level.W/960517 Ltr ML17312A7511996-05-0606 May 1996 LER 96-001-00:on 960404,smoke Discovered in Back Boards Area of CR by Security Officer,Performing Hourly Fire Watch Tour. Caused by Improperly Grounded Circuit.Investigation for Inappropriate Grounding of Low Voltage Power Sys Initiated ML17312A7241996-04-25025 April 1996 LER 96-002-00:on 960401,inappropriate Work Practice Resulted in Esfa of Train B Edg.Night Order Was Issued to All Three Units Describing event.W/960425 Ltr ML17312A6861996-04-0606 April 1996 LER 95-007-01:on 950512,determined That Bench Settings of air-operated Letdown & Containment Isolation Valves Adversely Affected Ability of Valves to Perform 10CFR50 App R Safety Function.Affected Valves Modified ML17312A5631996-02-22022 February 1996 LER 95-016-00:on 951212,containment Spray TS Violation Occurred Due to Unrecognized Valve Failure.Shim/Band Was Placed Around Stator of 1JSIBUV665 Motor Operator to Maintain Stator in Correct position.W/960222 Ltr ML17311B3381996-01-0909 January 1996 LER 95-014-00:on 951209,reactor Tripped Following Degradation of Main FW Flow.Caused by Malfunction of Fwcs Power supply,NNN-D11,transfer switch.NNN-D11 Aligned to Normal Power supply.W/960109 Ltr ML17311B3331995-12-31031 December 1995 LER 95-013-00:on 951201,AFW Sys Was Outside Design Basis of Plant.Caused by Design Error.Performed Assessment to Demonstrate That Existing Condition Does Not Pose Addl Safety concerns.W/951231 Ltr ML17311B2801995-11-23023 November 1995 LER 95-011-00:on 951018,identified Procedural Deficiency W/Msiv & FWIV ISTs Due to Personnel Error.Verified Operability of MSIVs & FWIVs.W/951123 Ltr ML17311B2531995-10-20020 October 1995 LER 95-002-00:on 950924,identified That Abnormal Blowdown Valves to Blowdown Flash Tank (Bft) Isolated,Resulting in Reactor Core Power Exceeding 3,800 Mwt Due to Personnel Error.Procedure for Aligning Blowdown to Bft Revised ML17311B1991995-09-21021 September 1995 LER 95-010-00:on 950727,equipment Qualification of Air Handling Unit Caused Essential Cw Pump to Be Inoperable. Used Work Orders to Drill Weep Holes in Motor Lead Connection boxes.W/950921 Ltr ML17311B1741995-09-0404 September 1995 LER 95-004-01:on 950329,containment Electrical Penetration Overcurrent Protective Devices Found Outside Design Basis. Caused by Error on Part of Original Architect Engineer. Modified Affected Circuits Critical to Normal Operational ML17311B1561995-08-27027 August 1995 LER 95-003-00:on 950729,switchyard Voltage Dropped Below Administratively Imposed Limit of 524 Kv for Approx 10 Seconds Due to Transient Grid Voltage.No C/A Taken Since Transmission Sys Transient Short duration.W/950827 Ltr ML17311B1551995-08-25025 August 1995 LER 95-002-01:on 950303,identified That Slb Analyses Failed to Consider as Initial Condition One Percent SDM for All Rods in (ARI) Due to Lack of Coordination & Unclear Div of Responsibilities.Ari Core Data Book SDM Curves Modified ML17311B1211995-08-16016 August 1995 LER 95-005-00:on 950717,RT on Low SG Water Level Was Result Following Degradation of MFW Flow.Completed Evaluation of Event ML17311B0841995-07-28028 July 1995 LER 94-005-01:on 941019,completed TS Required Shutdown Due to Expiration of LCO Time Limit.Design Change Options Identified & Will Be Reviewed to Determine If Valve &/Or Motor Operator Replacement or Mod Necessary ML17311B0721995-07-20020 July 1995 LER 95-004-00:on 950706,identified Four Occassions Between 950407 & 0630 When Conditional Surveillance in TS LCO 3.8.4.1 Action a Not Performed Due to Inattention to Detail. CR Copy of Temporary Procedure 40TP-9ZZ04 Corrected ML17311B0081995-07-0606 July 1995 LER 95-003-00:on 950613,TS LCO 3.0.3 Entered Following Loss of Both Trains of Essential Cw Sys & Both Hydrogen Recombiners.Caused by Spurious Actuations Due to Broken EDG Speed Probe Connector.Connector replaced.W/950706 Ltr 1999-08-27
[Table view] Category:RO)
MONTHYEARML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 ML17313A3131998-03-21021 March 1998 LER 98-001-00:on 980301,surveillance Test Deficiency Found During Qaa Leads to TS 3.0.3/4.0.3 Entry.Caused by Personnel Error.Personnel Responsible for Inadequately Performed SR Were Coached ML17313A2251998-03-0505 March 1998 LER 93-005-00:on 930309,CR Personnel Discovered Missed TS LCO Action & Subsequently Performed Surveillance Satisfactorily.Caused by Personnel Error.Appropriate Disciplinary Action issued.W/980305 Ltr ML17313A2241998-02-26026 February 1998 LER 98-001-00:on 980130,reactor Protection & ESFAS Instrumentation Not Bypassed within one-hour Allowed by TS Occurred.Caused by Inadequate Procedures.Expectation to Detect Alarm Conditions Was Emphasized to CR Personnel ML17313A2081998-02-10010 February 1998 LER 97-007-00:on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA program.W/980210 Ltr ML17313A2041998-02-0505 February 1998 LER 97-006-00:on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program ML17313A1201997-11-12012 November 1997 LER 97-006-00:on 971020,manual Reactor Trip Occurred Due to Vibration & Bearing Temp Increases in Reactor Coolant Pump. Caused by Failed Lower Journal Bearing.Bearing Assembly Was Disassembled,Inspected & Rebuilt ML17312B7181997-10-0707 October 1997 LER 97-003-00:on 970907,inadvertent Loss of Power & EDG Start Occurred Due to Procedural Error.Changed Train a & Train B Edg/Ist ST Procedures to Consistently Reflect Proper Pretest Staging Hand switches.W/971007 Ltr ML17312B7051997-09-26026 September 1997 LER 97-003-01:on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions ML17312B5531997-07-0707 July 1997 LER 97-002-00:on 970528,SR for Core Protection Was Not Performed Due to Inadequate Procedures.Revised Procedures ML17312B5501997-07-0707 July 1997 LER 97-003-00:on 970211,notified of Trevitest Activities Indicating That Total of Seven MSSVs Had as-found Lift Set Pressures Greater than 3 Percent Allowed by TS 3.7.1.1. Investigation Conducted.Seven MSSVs replaced.W/970707 Ltr ML17312B4971997-06-13013 June 1997 LER 97-002-00:on 970531,RT Occurred.Caused by Spurious Opening of All Four Rt Switchgear Breakers.Independent Investigation of Event Being Conducted in Accordance W/Util Corrective Action Program ML17312B1461996-12-17017 December 1996 LER 96-007-00:on 961119,surveillance Test Deficiencies Were Found During GL 96-01 Review Leading to TS 3.0.3 Entries. Caused by Increase in Scope of Required Testing.Supplement Will Be submitted.W/961217 Ltr ML17312A9511996-09-0404 September 1996 LER 96-003-00:on 960809,open Auxiliary Bldg Door Caused Full Bldg Essential Filtration Inoperability.Caused by Personnel Error.C/As Under consideration.W/960904 Ltr ML17312A8641996-07-17017 July 1996 LER 96-001-00:on 960621,inaccurate Gas Calculations for Post Accident Sampling Sys Occurred.Caused by Surveillance Test Worksheet Errors.Independent Investigation of Event Being conducted.W/960717 Ltr ML17300B2541996-06-11011 June 1996 LER 96-001-01:on 960404,inappropriate Grounding of Equipment Resulted in Condition Outside Design Basis of Plant. Established Fire Watches Required for Affected Areas ML17312A8081996-06-0909 June 1996 LER 96-002-00:on 960514,Tech Spec Violation Occurred Due to Erroneous Surveillance Requirement.Caused by Incorporation of C-E Generic Ts.Investigation Being conducted.W/960609 Ltr ML17312A7751996-05-17017 May 1996 LER 96-003-00:on 960122,missed Surveillance for Logic Check of Logs 1 & 2 Safety Excore Bypasses.Caused by Procedural Error.Log Power Functional Test Revised to Check Logs 1 & 2 Bypasses Regardless of Power level.W/960517 Ltr ML17312A7511996-05-0606 May 1996 LER 96-001-00:on 960404,smoke Discovered in Back Boards Area of CR by Security Officer,Performing Hourly Fire Watch Tour. Caused by Improperly Grounded Circuit.Investigation for Inappropriate Grounding of Low Voltage Power Sys Initiated ML17312A7241996-04-25025 April 1996 LER 96-002-00:on 960401,inappropriate Work Practice Resulted in Esfa of Train B Edg.Night Order Was Issued to All Three Units Describing event.W/960425 Ltr ML17312A6861996-04-0606 April 1996 LER 95-007-01:on 950512,determined That Bench Settings of air-operated Letdown & Containment Isolation Valves Adversely Affected Ability of Valves to Perform 10CFR50 App R Safety Function.Affected Valves Modified ML17312A5631996-02-22022 February 1996 LER 95-016-00:on 951212,containment Spray TS Violation Occurred Due to Unrecognized Valve Failure.Shim/Band Was Placed Around Stator of 1JSIBUV665 Motor Operator to Maintain Stator in Correct position.W/960222 Ltr ML17311B3381996-01-0909 January 1996 LER 95-014-00:on 951209,reactor Tripped Following Degradation of Main FW Flow.Caused by Malfunction of Fwcs Power supply,NNN-D11,transfer switch.NNN-D11 Aligned to Normal Power supply.W/960109 Ltr ML17311B3331995-12-31031 December 1995 LER 95-013-00:on 951201,AFW Sys Was Outside Design Basis of Plant.Caused by Design Error.Performed Assessment to Demonstrate That Existing Condition Does Not Pose Addl Safety concerns.W/951231 Ltr ML17311B2801995-11-23023 November 1995 LER 95-011-00:on 951018,identified Procedural Deficiency W/Msiv & FWIV ISTs Due to Personnel Error.Verified Operability of MSIVs & FWIVs.W/951123 Ltr ML17311B2531995-10-20020 October 1995 LER 95-002-00:on 950924,identified That Abnormal Blowdown Valves to Blowdown Flash Tank (Bft) Isolated,Resulting in Reactor Core Power Exceeding 3,800 Mwt Due to Personnel Error.Procedure for Aligning Blowdown to Bft Revised ML17311B1991995-09-21021 September 1995 LER 95-010-00:on 950727,equipment Qualification of Air Handling Unit Caused Essential Cw Pump to Be Inoperable. Used Work Orders to Drill Weep Holes in Motor Lead Connection boxes.W/950921 Ltr ML17311B1741995-09-0404 September 1995 LER 95-004-01:on 950329,containment Electrical Penetration Overcurrent Protective Devices Found Outside Design Basis. Caused by Error on Part of Original Architect Engineer. Modified Affected Circuits Critical to Normal Operational ML17311B1561995-08-27027 August 1995 LER 95-003-00:on 950729,switchyard Voltage Dropped Below Administratively Imposed Limit of 524 Kv for Approx 10 Seconds Due to Transient Grid Voltage.No C/A Taken Since Transmission Sys Transient Short duration.W/950827 Ltr ML17311B1551995-08-25025 August 1995 LER 95-002-01:on 950303,identified That Slb Analyses Failed to Consider as Initial Condition One Percent SDM for All Rods in (ARI) Due to Lack of Coordination & Unclear Div of Responsibilities.Ari Core Data Book SDM Curves Modified ML17311B1211995-08-16016 August 1995 LER 95-005-00:on 950717,RT on Low SG Water Level Was Result Following Degradation of MFW Flow.Completed Evaluation of Event ML17311B0841995-07-28028 July 1995 LER 94-005-01:on 941019,completed TS Required Shutdown Due to Expiration of LCO Time Limit.Design Change Options Identified & Will Be Reviewed to Determine If Valve &/Or Motor Operator Replacement or Mod Necessary ML17311B0721995-07-20020 July 1995 LER 95-004-00:on 950706,identified Four Occassions Between 950407 & 0630 When Conditional Surveillance in TS LCO 3.8.4.1 Action a Not Performed Due to Inattention to Detail. CR Copy of Temporary Procedure 40TP-9ZZ04 Corrected ML17311B0081995-07-0606 July 1995 LER 95-003-00:on 950613,TS LCO 3.0.3 Entered Following Loss of Both Trains of Essential Cw Sys & Both Hydrogen Recombiners.Caused by Spurious Actuations Due to Broken EDG Speed Probe Connector.Connector replaced.W/950706 Ltr 1999-08-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr ML17313A9921999-06-21021 June 1999 Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated ML17313A9911999-06-18018 June 1999 Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys ML17313A9731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A9201999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17300B3071999-03-31031 March 1999 Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee. ML17313A8801999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207H7471999-03-10010 March 1999 1999 Emergency Preparedness Exercise 99-E-AEV-03003 ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A8501999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr ML17313A7791999-02-0505 February 1999 Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies ML17313A8061999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A7381998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML17313A7031998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr ML17313A6701998-11-0404 November 1998 Rev 2 to PVNGS Unit 2 Colr. ML17313A6741998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A6561998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML20151S0941998-08-21021 August 1998 Rev 6 to COLR for PVNGS Unit 3 ML20151S0861998-08-21021 August 1998 Rev 4 to COLR for PVNGS Unit 1 ML20151S0901998-08-21021 August 1998 Rev 1 to COLR for PVNGS Unit 2 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML17313A5401998-08-13013 August 1998 Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated ML17313A5301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A5791998-07-0707 July 1998 to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998. ML17313A5001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4521998-06-19019 June 1998 Rev 5 to COLR for Pvngs,Unit 3. ML17313A4501998-06-19019 June 1998 Rev 4 to COLR for Pvngs,Unit 3. ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A4211998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3691998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 1999-09-30
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gc CZ~RATZD Dl SIIItBUTlON DZMONSTR ON SY STEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR-8908180267 DOC-DATE: 89/08/14 NOTARIZED- NO DOCKET FAt IL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH. NAME AUTHOR AFFILIATION SHRIVER,T.D. Arizona Public Service Co. (formerly Arizona Nuclear Power HAYNES,J.G. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECX PI ENT AFFILIATION
SUBJECT:
LER 89-008-00:on 890429,low level radioactivity found in onsite landfill.
W/8 NOTES'5000528 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR l ENCL RECIPIENT COPIES RECIPIENT L SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
COPIES I
A.
ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 CHAN,T 1 1 DAVXS,M. 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER ACRS WYLXE 1 1 AEOD/DOA AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP DEDRO 1 1 IRM/DCTS/DAB NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 NRR/DOEA/EAB 11 1 1 PB 10 NUDOCS-ABSTRACT 1 1 EG IL 02 RES/DSIR/EIB 1 1 RGN E 01 EXTERNAL EG&G WILLIAMSI S 4 4 FORD BLDG HOY I A L ST LOBBY WARD 1 1 LPDR NRC PDR 1 1 NSIC MAYS,G NSIC MURPHYIG A~ 1 1 NOTES: 1 1 S
D D
S-FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL 42
Arizona Public Service Company P.O. 8OX 53999 ~ PHOENIX, ARIZONA 85092 3999 192-00506-JGH/TDS/RJR August 14, 1989 U. S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528 (License No. NPF-41)
Licensee Event Report 89-008-00 File: 89-020-404 Attached please find Licensee Event Report (LER) No. 89-008-00 prepared and
.submitted pursuant to 10CFR 50.73. In accordance with 10CFR 50.73(d), we are herewith forwarding a copy of the LER to the Regional Administrator of the Region V office.
If you have any questions, please contact T. D. Shriver, Compliance Hanager at (602) 393-2521.
Very truly yours, 5C ~nnA J. G. Haynes Vice President Nuclear Production JGH/TDS/RJR/kj Attachment cc: W. F, Conway (all w/a)
D. B, Karner I E. E. Van Brunt, Jr. I' J. B. Hartin T. J. Polich H. J. Davis A, C. Gehr INPO Records Center
t NAC Form 355 US. NUCLEAR REOULATOAY COEQIISSION
<903)
APPROVED OMS NO. 31$ 001OI LICENSEE EVENT REPORT (LER) EXPIAES.'S<31<SE FACILI'TY NAME (I) POCKET NVMSEA <2) PA Palo Verde Unit 1 0 5 0 0 0 5 2 8 1 oFp TITLE Iil Low Level Radioactivit Found in On-Site Landfill EVENT DATE (5) LER NUMBER (5) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI DAY YEAR YEAR IEOUENVIAL AEVI~ OAY YEAR FACILITYNAMES DOCKET NUMBERISI MONTH NVMOEIV MONTH NVMEEIV Palo Verde Unit 3 o'so o o 530 04 29 89 89 0 0 8 00 08 14 89 N/A 0 5 0 0 0 THIS AEPOAT IS SUBMITTED PVASVANT 7 0 THE AEOUIAEMENTS OF 10 CFA ((t (Corti onr or mocr of tnr fpffornnff (11 OPEAATINO MODE (5) 20A02(ol 20AOB(cl 50.73(r I 12) I Iv) 73.71(5)
~ OWER 20.IOS( ~ l(1(<0 SOW(c)(1) 50.73(v ) (2 l(el 73.71(cl LEVEL p p p 20A05(c I III(III 50.35(cl(2) 50.73(c) (2)(rb) O'THER (Sprcffy in Aptttrct Ortow rnvf In Trrt, Hf<C Form 20AOE(c) I()(EI) 50.73( ~ l(2((I) 50.73(cl(2llv)III(AI SSSA)
'g+'4'~p~: 20AOS(c) (I ) (I v) 50.73<el(2)(EI 50,73(c) (2 I(r All(~ I Voluntary Report M<rn .. ww:. NXco ic Ipm) I 20AOS(el(1) (v) 50.73(c) (2) IIII) 50.73 I ~ ) (2) I c)
LICENSEE CONTACT FOA THIS LEA (12I NAME TELEPHONE NUMBER AREA CODE Timothy D. Shriver, Compliance Manager 60 23 93 2 521 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
EPORTABLE MANVFAC.
CAUSE SYSTEM COMPONENT MANVFAC'VRER TO NPADS :;(jPQjjj@'y~ CAUSE SYSTEM COMPONENT TVRER EPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED (Iil MONTH OAY YEAR EXPECTED SUbMISSION DATE 115)
YEs tff yrt. comptrtr ExpfcyED svFMissiDH DATE) X NO ABSTRACT (Lfmtt to trOO tpecrL I r., rpprorimrtriy fifteen tinofr tprcr typrwnttrn iinrtf (15)
On July 14, 1989 an internal audit revealed that cooling tower sludge contained low level amounts of radioactivity. An investigation determined that cooling tower sludge had been removed from Units 1 and 3 for disposal in an onsite landfill.
As corrective action the company has requested approval from a state agency to dispose of cooling tower sludge in the Landfill. Further the Company proposes to seek authority under 10 CFR 20.302 for onsite disposal of licensed material.
NRC Scvm 355
'f NAC fnrvn 54SA U.S. NUCLEAII IIEOULATOAyCOMMISSION 11451 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPIIOVEO OMS NO SISOWI04 N EXPIAES: SISIIIe PACILITY NAME III OOCKET NUMSEII ISI LEII NUMSEII ISI PACE ISI ega'. 55QUCNTI*L r'ot nay+lyse NUMeen ~ >< navaa ~ ee Palo Verde Unit e
1
~'al IITI o s o o o 52 889 00 8 00 0 2 OF 0 6 TEXT IIIsnore anece neaavesL sane Anannvnei HAC lorna DESCRIPTION OF, WHAT OCCURRED:
A. Initial Conditions:
On July 14, 1989 Palo Verde Unit 1 was in refueling with the reactor core off-loaded. Palo Verde Unit 3 was also in refueling with the reactor core off-loaded.
B. Reportable Event Description (Including Dates and Approximate Ti~me of Hajor Occurrences):
Event Classificationafoluntary Report During an internal guality Assurance audit on friday, July 14, 1989, one of the auditors (utility, non-licensed) became interested in the potential for radioactivity in Unit 1 cooling tower sludge.
This interest stemmed from (1) an event in January 1987 when Unit 1 discovered a Steam Generator tube leak and shutdown for repairs, and (2) NRC Information Notices addressing the potential for radioactivity in sludge (e.g., Nos. 80-10, 85-92 and 88-22). A sample of the Unit 1 cooling tower sludge was drawn and analyzed.
Low level amounts of Cobalt-60, Cesium-137 and Hanganese-54 were discovered and an investigation was promptly initiated.
Thereafter, it was confirmed that cooling tower sludge had been removed from Units 1 and 3 for disposal in an onsite landfill (referred to as the Water Reclamation Facility Sludge Disposal Landfill). In respect to .Unit 1, this had taken place on April 29, 1989, when approximately 120 cubic yards of material were transferred by dump truck from the Unit 1 cooling towers to the Landfill. Unit 3 cooling tower sludge had been disposed of in the Landfill between Harch 14, 1989 and June 24, 1989. In this case, approximately 340 cubic yards of sludge were disposed of in the Landfill.
During the course of investigation, the possibility of cooling tower sludge being disposed in the Rubbish Landfill and other locations at the Palo Verde Nuclear Generating Station was identified. Although there is no basis to conclude that these disposals included licensed material, the investigation will include an evaluation of these possible incidents.
The Landfill is operated subject to the conditions of a Groundwater guality Protection Permit issued by the Arizona Department of Environmental guality (ADEg) on August 21, 1988. Generally, waste disposal of materials in the Landfill is limited to non-hazardous, non-putrescible, non-radioactive wastes in a manner approved by the ADEg.
~ nC aOAM 5444 155)s
NRC Pwca 144A I941l U.S. NUCLEAR REOULATOIIYCOMMISSION LICENSEE EVENT REPORT {LER) TEXT CONTINUATION APPROVEO OMS HO. 11$ 0M104 EXPIRES! S/$ 1/%
PACILITY NAME III OOCKE'T NUMSER l1l LER NUMSER ISI PACE ISI YEAR QP 44OV4HT/AL Hvv 41 4 ge Hvv Ky/4XIH 4A Palo Verde Unit 5'2 88 00 00, 03OF TEXT W Pygmy cfccf H ~. 1 RI/Pcyv//IRC fc ~'4/ UTI o 5 o o o 9 8 0 6 Pursuant to the terms of that Permit, APS had requested approval from that Agency for disposal of cooling tower sludges in the Landfill, which APS believed had been granted on Hay .16, 1989. At the time the disposals in question took place, however, formal approval for the disposal of cooling tower sludge had in actuality not yet been received.
At the time the disposals were made in the Landfill, believed that the sludge possessed radioactive characteristics it was not because'f analytical results obtained through testing of the secondary systems.
C. Status of structures, systems, or components that were inoperable at the start of the event that contributed to the event:
Not applicable - no structures, systems, or components were inoperable which contributed to this event.
D. Cause of each component or system failure, if known:
Not applicable - no component or system failures were involved.
E. Failure known:
mode, mechanism, and effect of each failed component, if Not applicable - no component failures were involved.
F. For failures of components with multiple functions, list of systems or secondary functions that were also affected:
Not applicable - no component failures were involved.
G. For failures that rendered a train of a safety system inoperable, estimated time elapsed from the discovery of the failure until the train was returned to service:
Not applicable - no failures were involved.
H. Method of discovery of each component or system failure or procedural error:
Not applicable - there were no component or system failures or procedural errors.
WRC //IAV )44+
I9 ~ )c
NRC Ferns SSSA 1945 I RI.S. NUCLEAR REOULATORY COMIIISSION LICENSEE EVENT REPORT {LERI TEXT CONTINUATION APPROVEO OMS NO SIEOMIOS EXPIRES: SISIISS FACILITY NAME Ill OOCXET NUMSER Ql LER NUMSER ISI PACE ISI I' 5 ~ OUCNYI*L ~)Fg AEVORIN NVM55A ~~'uusFA Palo Verde Unit TEXT IIIPROF aPeCF N nqueeC uW ~ 1 NIIC FOnn JSM SI Illl o s o o o 5 2 8 8 9 00 8 00, 04oF06 I. Cause of Event:
.APS utilizes a sampling procedure, which includes sample requirements for radioactivity, foi discharge paths to the cooling water canals. Since sampling had not detected radioactivity there was no reason to .believe that radioactivity existed in the-cooling water canals. Thus, no sampling was conducted. of the sludge prior to disposal to the landfill.
The sources of the low levels of radioactivity in the cooling tower sludge is presently theorized to be the process of regeneration of condensate demineralizer resin (SF), steam generator blowdown sumps (WI) and/or discharge of condensate (SD) to the circulating water system (KE). Since extremely low concentrations of..radionuclides may be present in any of these paths, it may not be possible to positively identify the specific path that led to ihe sludge activity buildup.-
J. Safety System Response:
Not applicable - no safety system response was involved.
K. Failed Component Information:
Not applicable - no failed components were involved.
II. ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS OF THIS EVENT:
The sludge was deposited at an on-site landfill. Micro R meter surveys of the affected area have indicated no detectable radiation levels above background. Thus, this event does not adversely affect, the health and safety of the public.
I I I. CORRECTIVE ACTIONS:
A. Immediate; On July 14, 1989, as a precaution, the Water Reclamation Landfill was posted as a CONTROLLED AREA BOUNDARY, RADIOACTIVE MATERIAL STORAGE AREA Radiation Exposure Permit (REP) required for entry.
During the period July 15-17, 1989 preliminary samples were taken by Arizona Public Service of the Unit 1 and Unit 3 cooling towers and the Water Reclamation Facility landfill. Results at each of these locations showed very low levels of radioactivity.
'MAC FOAM 555k 19 S)i
rJ NAC 5etm 454A I945 I U4. NUCLEAN AECULATOIIYCOMMIEEION LICENSEE EVENT REPORT (LER) TEXT. CONTINUATION AIIIIOVEOOM4 NO 4140~IO5 EX9IIIES: 4IEI Ill OOCKET NUMEEA IXI LEII NVMEEA IEI PACE IEI 5\QVEHTIAI. 'm AEVOION HUM55A ~+ NIJM55A Palo Verde Unit 1 o s o o o 52 88 9 00 8 00 05QFO 6 TEXT IITasore soece e nOuied. vw eckaenV lVIIC Form JOEA'5l I ill On July 18, 1989 Arizona Public Service requested the services of Arizona State University for further analysis. This .was done to provide an independent organization with environmental sampling expertise.
On July 18, 1989, samples were obtained of 'the 'Unit 1 and 'Unit 2 cooling tower sludge. The Unit 2 sludge samples were all less than the lower limit of detection for each sample. Further, eleven samples were taken in Area No. 1 of the WRF landfill and two samples were taken from in Area No. 2 of the WRF landfill.
Area 1 is approximately 90 feet by 440 feet and Area 2 is approximately 10 feet by 15 feet. These sites were chosen based on the color differences between the cooling tower sludge and the WRF sludge for area 1. Area 2 consisted of two discrete piles of cooling tower sludge and was identified by the individual who dumped the sludge.
On July 20, 1989, additional samples were taken of the Unit 1 and Unit 2 cooling tower sludge and a single sample of one location at the Water Reclamation landfill was taken for ion exchange resin examination.
Based on the gamma spectroscopic results of the landfill samples taken on July 18 and 20, a total of thirty-four more samples were taken from Area Nos. 1 and 2 on July 24, 1989. On July 27, 1989, eight additional samples were taken in Area No. 1 and 20 samples were taken from a new site in Area No. 1.
The sampling plan continued with an additional thirty samples taken on August 3, 1989 to determine the boundary of the Manganese-54, Cobalt-60, Cesium-134 and Cesium-137 positive indication shown in Area 1 and to confirm whether or not Cobalt-60 activity exists at the new site in Area 1 as previously indicated.
The landfill 'samples -analyzed by Arizona State University have shown positive indications for Manganese-54, Cobalt-60, Cesium-134, and Cesium-137 at one sample location of approximately 40 feet by 40 feet by 1 foot deep in Area 1. At this location Cobalt-60 and Cesium-137 levels were found to have a value of 2E-6 microcuries per gram and Manganese-54 and Cesium-134 were found to have a value of 4E-7 microcuries per gram. All of the other samples from Area 1 and Area 2 have shown lower level of detection values for Manganese-54, Cobalt-60, Cesium-134, and Antimony-125, with the exception of one location of approximately 20 feet by 20 feet by 1 foot deep within Area 1 which gave a value of approximately 3E-8 microcuries per gram for Manganese-54 and approximately 9E-8 microcuries per gram for Cobalt-60. Cesium-137 levels found were similar to those levels detected in the preconstruction environmental soil analysis erformed in 1976.
MAC I TiAM )445 I955i
I ll I
NRC ferrrr 399A I9CITI U,E. NUCLEAR REOULATORY COMMIEEION LlCENSEE EVENT REPORT (LER) TEXT CONTlNUATION AFFROVED OM9 NO 3150&/04 EKFIAES: 9/31/%
fACILITYNAME III DOCKET NUMEER IEI LER NVMEER TEI ~ AOE I3>
,</o SEDUEP/T/AL irKo FEY/4/ON r/UM44R rrUM44 A Palo Verde Unit 1 o s o o o 5 2 8 89 00 80 0 06 0F 0 TExt illmore Iooce rc reocee/E foe r//ormo//Y/Ic /rrerrr JIIEA'4/ Ilt) 6'.
Action to Prevent Recurrence:
The Company has requested that the ADEg act upon its pending request for aproval to dispose of cooling tower sludge in the Landfill. Pending receipt of that approval, no further cooling tower sludge disposals will be .made in the Landfill.
The Company proposes to seek authority under 10 CFR 20.302 for onsite disposal of licensed material, including cooling tower sludge. This approval would enable the Company to leave in place the cooling tower sludge already situated in the landfill, and would accommodate the need for future disposals as the need arises.
Retrieval of the material from the Landfill for eventual off-site disposal is not considered a preferred alternative because the material presents no hazards to human health and the environment.
Such being the case, its disposal in low level radwaste facilities would be considered an inefficient use of available resources.
IV. PREVIOUS SIMILAR EVENTS:
Not applicable - no similar events have'een reported,
~ oQ 4 OAM 4444 I9 9)r