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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
[Table view] |
Text
REGULA Y INFORMATION DISTRIBUTI YSTEM (RIDS)
ACCESSION NBR: 870'7170330 DOC. DATE: 87/09/03 NOTARIZED: NO DOCKET FACIL: STN-50-529 Palo Verde Nuclear Stationi Unit 2i Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION BRADISHi T. R. Arizona Nuclear Pouter Prospect (formerly Arizona Public Serv HAYES'. G. Arizona Nuclear Pouter Prospect (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION
SUBJECT:
LER 87-015-00: on 870816'ontrol room essential filtration actuation initiated om Channels A 5 B pl- ESF -actuation sys.
Caused by spurious alarm/trip signal on radiation monitor RU-30. Train B placed in bypass. W/870'703 ltr.
DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR i ENCL TITLE: 50. 73 Licensee Event Report (LER)i Incident g
Rpti SIZE:
etc.
NOTES: Standardized plant. 05000529 REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 LICITRAiE 1 1 DAVIS' 1 INTERNAL: ACRS MI CHELSQN 1 1 ACRS MOELLER AEOD/DOA 1 AEOD/DSP/NAS 1 1 AEOD/DSP/RQAB 2 2 AEOD/DSP/TPAB 1 DEDRQ 1 NRR/DEST/ADS 0 NRR/DEST/CEB 1 NRR/DEBT/ELB 1 1 NR 8 /DE ST/ I C SB 1 NRR/DEST/MEB 1 NRR/DEST/MTB 1, 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB NRR/DQEA/E*B 1 NRR/DREP/RAB 1 P PB NRR/PMAS/ ILRB 1 EG F - 02 1 RES DEPY GI 1 1 RES TELFQRDi J 1 1 RES/DE/EIB 1 RGN5 FILE 01 1 EXTERNAL: EGS.G GROHi M 5 5 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS' 1 1 NSIC MAYSi G 1 1 NOTES:
TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44
NAC Form 344 UA. NUCLEAR REOULATORY COMMISSION (9 03l APPROVED OMB NO. 3)500104 EXPIAES: 4/31(IS LICENSEE EVENT REPORT ILER)
FACILITY NAME (I) DOCKET NUMBER (2) PA Palo Verde Unit 2 0 5 0 0 0 2 1 OF 0 ESF Actuation Caused By Spurious Alarm/Trip Signal on Radiation Monitor RU-30 EVENT DATE (5) LER NUMBER IS) REPORT DATE (7) OTHER FACILITIES INVOLVED(SI SEOVENTIAI. "'Ytcx DAY YEAR FACILITY NAMES POCKET NUMBER(El MONTH DAY YEAR YEAR NVMSEII g'r'yrS NVMSEII MONT~
N A 0 5 0 0 0 1 6 8 7 8 7 0 1 5 PO 09 7 N A 0 5 0 0 0 THIS AEPOAT IS SUBMITTED PURSUANT TO THE REDUIAEMENTB oF 10 cFR g; (cneco one or more ol tne lollowlnpl (11)
OPERATINO MODE ( ~ ) 20. c02 lb) 20.404(el 50.73(c l(2)(iv) 73.71(II)
I(1)(ill) 20.405( ~ I(1) IB SOM(el(I) 50.73(c) (2)(vl 73.71(cl POWER LEVEL 1 p p 20.405( ~ I (I) I 4) 50.34lc)(2) 50.7 34) (2 I (rQ) OTHER ISpecily ln Abttrect belOw end ln Text, HRC Form 20.405( ~ 50.73( ~ I (2) Il) 50.73(el(2)(rill) (Al SFSAI 20AOS Ic III l(lvl 50.7')(2)(5) 50.73(e) (2) (rIEI(SI 20.405( ~ I (I I Iv) 50.73(c) (2)(ill) 50.73(c) (2)(xl LICENSEE CONTACT FOR THIS LEA (12)
NAME TELEPHONE NUMBER AREA COPE Thomas R. Bradish, Compliance Supervisor 602 393- 353 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRI ~ EP IN THIS REPORT (13)
SYSTEM COMPONENT MANUFAC EPORTASLE COMPONENT MANUFAC. EPOATABLE CAUSE TURER TO NPADS CAUSE SYSTEM TURER TO NPRDS kwhr%
SUPPLEMENTAL AEPORT EXPECTED IICI MONTH DAY YEAR EXPECTED SUS MISS ION YES Illyet, complete EXPECTED SUStrttSSIOH DATE)
AssTRAcT (Limit to fe00 tpecet, leepproxlmete!y Bitten clnole tpece typewritten linnl (14)
NO PATE (15) 11 1587 On August 16, 1987 at 0609 MST, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION) at 100 percent power when a Control Room Essential Filtration Actuation (CREFAS) was initiated on Channels A and B of the Engineered. Safety Features Actuation System (ESFAS).
The actuation was in response to a spurious alarm/trip signal on the "B" Control Room Ventilation Intake Noble Gas Monitor (RU-30), and occurred coincident with an attempt to reset a local alarm on the subject monitor with a p'ortable indication and control unit (PIC). An investigation is currently in progress to determine the cause of the event, which will include an evaluation to determine if utilization of the PIC was a contributing factor. The results of the investigation will be provided in a supplement to this report.
As immediate corrective action, the actuated equipment was returned to a normal operations configuration, and the Train "B" CREFAS was placed in bypass pending further evaluation.
Other events involving CREFAS actuations have been reported, however, these events did not involve the sequence of activities noted above and are not considered similar events.
87091 70330 870903 PDR ADOCK 05000M9 8 PDR NRC farm 344
NAC Forrrr 355A U.S. NUCL'EAR AEOULATORY COMMISSION 1583 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPAOVEO OMS NO 3150W105 EXPIRES: SISI/IE!
FACILITY NAME 11I OOCIIET NUMSEA 13)
LEA NUMSEA ISI ~ AOE 131 SEOVENTIAL NVM ER "
gju REVISION NVM 51 Palo Verde Unit TEXT Of mure 5PPIP 15 PIFIPPIE u55 2
r551enV HAC %%drrrr 3NA'IlII Tl 0 s 0 0 o 529 87 015 0 0 02oF0 3 On August 16, 1987 at 0609 MST, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION) at 100 percent power when a Control Room Essential Filtration Actuation (CREFAS)" was initiated on Train "B" of the Engineered Safety Features Actuation System (ESFAS)(JE). The Train "B" CREFAS cross-tripped the Train "A" CREFAS, per design, and all associated equipment operated satisfactorily. The CREFAS was initiated by the "B" Control Room Ventilation Intake Noble Gas Monitor (RU-30)(IL)(RI). The actuations were identified by the control room operators (utility-licensed) as a result of main control board (MCBD) annunciations '(ANN).
Following the ESF actuations, the control room operators (utility-licensed) verified that there were no actual radiation level increases by comparing the RU-30 results to the "A" Control Room Ventilation Intake Noble Gas Monitor (RU-29)(IL)(RI), and by determining that, coincident with the event, a radiation protection (RP) technician (utility-non-licensed) had reset the local alarm on RU-30 by utilizing a portable indication and control unit (PIC)(HIC) with the monitor placed in LOCAL mode.
Based on the above information, the shift supervisor (utility-licensed) determined the alarm/trip to be spurious. At 0622 MST the control room operator (utility-licensed) reset the CREFAS "A" and "B" alarms and the Train "B" CREFAS actuated equipment, and placed the Train "B" CREFAS in bypass pending further investigation. At'634 MST, the shift supervisor (utility-licensed) directed the control room operators (utility-licensed) to reset the Train "A" CREFAS actuated equipment, and at 0712 MST the event was secured. The total duration of the event was approximately 66 minutes.
Subsequent investigation revealed that, prior to the event, the Control Room notified the Radiation Protection office that the local alarm (ALM) on radiation monitor RU-30 was on. The RP technician (utility non-licensed) then verified that RU-30 was not registering an alarm condition on the Display and Control Unit (DCU)(AIC) located in the RP office, and that the specified setpoints (e.g., 2.0 X E-5 micro Curie [Ci]/cubic centimeter [cc]) were in the monitor.
The RP technician then notified the Control Room that the RU-30 local alarm would be reset with a PIC. The reset is accomplished by connecting the PIC to the monitor, switching the PIC from REMOTE to LOCAL mode, and depressing the "ALARM ACK" button. These actions were completed, however, following the alarm reset the PIC may have been disconnected from the radiation monitor while in LOCAL mode. Procedural controls require the PIC to be switched to-REMOTE mode prior to being disconnected from the monitor. This action is believed to have caused a voltage spike on the radiation monitor, which in turn generated a spurious alarm/trip signal.
4IIC IOIIM 555A 15 53>
NRC Form 344A U.S. NUCLEAR REOULATOIIY COMMISSION
<943 I LICENSEE EVENT REPORT (LERI TEXT CONTINUATION API'ROYEO OMS NO 3<40M<94 EXPIRES: S/3<I<6 FACILITY NAME <II OOCKET NUMSEII <El LER NUMSER <SI PACE <3)
II SEQUENTIAL o 4 v I4 IO rr YE A HUM 4R rr<rM to Palo Verde Unit TEXT Nmort 2
totct S ttrrttrE rrto edknonel ArRC Ann 3<E<ASI IITI 0 5 0 0 0 529 87 015 00 03 QF 0 3 The assessment of the event as a spurious alarm/trip was substantiated when, following the event, the RP technician found the alarm/trip setpoint for RU-30 to be at the default value (2.2 X E-6 micro Ci/cc) in lieu of the specified value noted above. The remote indication and control unit (RIC)(AIC) normally downloads the speciiied setpoints to the radiation monitor, however, the default setpoints will be downloaded if the specified values are lost due to a voltage fluctuation or electronic circuit noise.
An investigation is currently in process to determine the cause of the event, which will include an evaluation to determine if utilization of the PIC was a contributing factor. The results of the investigation will be provided in a supplement to this report.
As corrective action the monitor was reset, returning the setpoints to the specified values, and the Train "B" CREFAS returned to service. Corrective action to prevent recurrence will be determined and implemented upon completion of the pending investigation.
Based on the information noted above, no personnel errors have been identified at this time which contributed to the event. No procedural errors contributed to the event, and no structures, systems or components inoperable prior to the event were identified as contributing factors. Based on the actions described above, which included verification that no abnormal radiation levels existed pursuant to the event, there was no effect on the health and safety of the public and no safety impact on the unit. Other events involving CREFAS actuations have been reported, however, these events did not involve the sequence of activities noted above and are not considered similar events.
4IIC l OR>> 344k
<9 93r
Arizona Nuclear Power Project P.O, BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 192-00273-JGH/TRB/KCP September 3, 1987 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No. 50-529 Licensee Event Report 2-87-015-00 File: 87-020-404
Dear Sirs:
Attached please find Licensee Event Report (LER) No. 2-87-015-00 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. R. Bradish, Compliance Supervisor at (602) 393-3531.
Very truly yours, a~2 +
J. G. Haynes Vice President Nuclear Production JGH/KCP/cld Attachment cc: 0. M. DeMichele (all w/a)
E. E. Van Brunt, Jr.
- J. B. Martin R. C. Sorenson
,E. A. Licitra A. C. Gehr INPO Records Center
