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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20029C7321994-04-22022 April 1994 LER 94-004-00:on 940221,discovered Corrosion of Three Nuts on One of Incor Instrumentation Reactor Vessel Head.Caused by Increase of Wet Boric Acid.Leaking Flanges Repaired.W/ 940422 Ltr ML20046B4731993-07-30030 July 1993 LER 93-005-00:on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat exchanger.W/930730 Ltr ML20046A4911993-07-22022 July 1993 LER 93-003-00:on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed. W/930722 Ltr ML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20045G7281993-07-0808 July 1993 LER 93-002-00:on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve opened.W/930708 Ltr ML20045G8661993-07-0808 July 1993 LER 93-004-00:on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant startup.W/930708 Ltr ML20045E7361993-06-29029 June 1993 LER 93-002-01:on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances performed.W/930629 Ltr ML20029B1261991-02-28028 February 1991 LER 91-001-00:on 910129,tubing in Air Start Sys for Emergency Diesel Generator Failed During Seismic Event. Caused by Error in Design of EDG Air Start Sys.Permanent Mod to Sys installed.W/910228 Ltr ML20028H8011991-01-24024 January 1991 LER 90-002-01:on 900116,determined That 891211 Reconstitution of More than One Spent Fuel Assembly Per Time in Violation of Fuel Handling Incident Safety Analysis. Caused by Deficient procedure.W/910124 Ltr ML20044A1861990-06-20020 June 1990 LER 87-002-01:on 861203,section of Thin Wall Found on Main Steam Line W/Readings Below Allowable Min of 0.95 Inches. Caused by Grinding of Edge of Pipe to Achieve Proper fit-up for Welding.Relief from IWB-3610 granted.W/900620 Ltr ML20043G1071990-06-13013 June 1990 LER 89-019-01:on 891128,determined That for Approx 10 Yrs, from 1979-1989,requirement to Lock HPSI Discharge Header Isolation Valves Shut Not Implemented.Caused by Inadequate Mgt Attention.Test Procedures modified.W/900613 Ltr ML20043F1221990-06-0404 June 1990 LER 90-017-00:on 900505,pin Hole Leak Observed in Discharge Piping of Saltwater Pump 13.Caused by Localized Corrosion. Leaking Spool Piece Removed & Blank Flange Installed. W/900604 Ltr ML20043A7871990-05-21021 May 1990 LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr ML20043A3441990-05-14014 May 1990 LER 90-014-00:on 900413 & 19,unit Entered Tech Spec Limiting Condition of Operation 3.0.3 Due to Potential Inoperability of Three Out of Four Reactor Protection Sys Delta T Power Channels.Caused by Lack of Procedure guidance.W/900514 Ltr ML20043A3401990-05-14014 May 1990 LER 90-013-00:on 900413,determined That Axial Shape Index Channels Out of Spec & Inoperable.Caused by Inadequate Understanding of Design Basis for Excore/Incore Comparison. Design Basis for Excore/Incore improved.W/900514 Ltr ML20042G4521990-05-0707 May 1990 LER 90-015-00:on 900407,discovered That Relay Contact Which Actuates Reactor Trip Breaker Shunt Trip Not Adequately Functionally Tested.Caused by Failure to Examine Circuit in Detail When Test developed.W/900507 Ltr ML20042F5801990-05-0404 May 1990 LER 90-012-00:on 900406,identified That Procedure for LOCA Would Not Ensure post-LOCA Core Flush Would Be Initiated in Time to Prevent Boron Precipitation.Caused by Personnel Error.Configuration Mgt Program strengthened.W/900504 Ltr ML20012E9931990-03-29029 March 1990 LER 90-008-00:on 900227,determined That Surveillance Procedure M-280-0 Did Not Include Steps to Fully Test Control Room Recorder for Hydrogen Analyzers.Caused by Personnel Error.Procedure Revised on 900308.W/900329 Ltr ML20012F0001990-03-28028 March 1990 LER 89-006-01:on 890508,containment Iodine Filters Outside Design Basis Due to Equipment Qualification.Recalculation of Total Integrated Radiation Dose to Cables for Filter Fans Demonstrated Cable qualified.W/900328 Ltr ML20012E9951990-03-28028 March 1990 LER 89-014-01:on 890723,determined That Salt Water Header Not Capable of Withstanding Seismic Event Intact.Caused by Inadequate Welding of Blind Spool Pieces in Pipe.Insp Revealed Spools Capable as installed.W/900328 Ltr ML20012E0101990-03-26026 March 1990 LER 90-009-00:on 900224,failure to Meet Action Requirement Re Tech Spec 3.7.12.Caused by Personnel Error.Cables Removed from Doorway in Charging Pump Room & Not Allowed to Be Placed in doorway.W/900326 Ltr ML20012C4971990-03-15015 March 1990 LER 90-007-00:on 900216,discovered That Supervised Circuits Associated W/Fire Detection Instruments Located in Reactor Coolant Pump Bays Not Been Included in Surveillance Test Procedure.Caused by Personnel error.W/900315 Ltr ML20012C4861990-03-12012 March 1990 LER 90-006-00:on 900209,determined That Four Fire Dampers Missing.Caused by Not Identifying Penetrations as Requiring Dampers When Fire Hazards Analysis of Plant Conducted.Hourly Fire Watch Continued.Missing Dampers installed.W/900312 Ltr ML20012B8991990-03-12012 March 1990 LER 89-023-01:on 891220,determined That Pipe Rupture in nonsafety-related Svc Water Subsystem Could Result in Rapid Draining of Subsystems That Serve Auxiliary Bldg.Task Force Formed to Determine Corrective actions.W/900312 Ltr ML20012B4221990-03-0606 March 1990 LER 89-012-01:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed.Caused by Procedural Deficiency.Procedures Revised to Include Valve & Surveillance Test Program Instruction revised.W/900306 Ltr ML20011F2701990-02-27027 February 1990 LER 90-001-01:on 900109,determined That Surveillance Tests Used to Perform Channel Calibr Tests for Acoustic Flow Monitoring Devices Inadequate.Caused by Personnel Error & Inadequate Procedures.Swapped Leads restored.W/900227 Ltr ML20011F2091990-02-27027 February 1990 LER 89-026-00:on 891128,determined That Particulate Levels in Samples Taken from Lower Third of Tanks Exceeded Allowable Limits.Caused by Inadequate Sampling Technique. Tanks Cleaned & Filled W/Clean fuel.W/900227 Ltr ML20006F8601990-02-22022 February 1990 LER 90-004-00:on 900123,discovered Fire Barrier Penetration Seal Open for Indeterminate Time W/O Performing Tech Spec 3.7.12.a Required Actions.Caused by Personnel Error. Temporary Fire Seal installed.W/900222 Ltr ML20006E0521990-02-0808 February 1990 LER 90-001-00:on 891221,discovered That Acoustic Indications for One PORV & One Safety Valve Were Reversed During Surveillance Test.Caused by Personnel Error.Swapped Leads Restored to Proper configuration.W/900208 Ltr ML20006B4801990-01-26026 January 1990 LER 89-022-00:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed,Violating Tech Specs.Caused by Procedural Deficiency.Surveillance Test Procedure Revised to Include Deleted valves.W/900126 Ltr ML19354D8931990-01-17017 January 1990 LER 89-024-00:on 891218,determined That Wires Which Connect Actuation Device Logic Relay Contacts to Remainder of Circuit Not Tested During Channel Calibr Test.Caused by Inadequate Test.Test Program Upgrade underway.W/900117 Ltr ML20005F1921990-01-10010 January 1990 LER 89-025-00:on 891208,Tech Spec Action Statement Entered When Ventilation Ducts Penetrating Fire Barrier Could Not Be Accessed to Determine If Fire Dampers Installed.On 891211, Fire Watch Missed.Caused by Personnel error.W/900110 Ltr ML20005E3971989-12-28028 December 1989 LER 89-019-00:on 891128,discovered That HPSI Discharge Header Isolation Valves Not Locked Shut When RCS in Water Solid Condition,Resulting in Operation Outside Design Basis. Procedure Revised to Require Valves closed.W/891228 Ltr ML19351A4551989-12-13013 December 1989 LER 89-020-00:on 891113,determined That Some Solenoid Valves & Valve Power Supplies for Saltwater Sys May Not Be Able to Perform Design Function After Design Basis Seismic Event. Cause Undetermined.Power Supplies upgraded.W/891213 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML19325F3951989-11-10010 November 1989 LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr ML19325E8221989-11-0303 November 1989 LER 89-007-01:on 890505,evidence of Reactor Coolant Leakage from 120 Pressurizer Vessel Heater Penetrations Discovered. Caused by IGSCC of Inconel 600.All Penetrations Using J-welds & Inconel 600 Visually inspected.W/891103 Ltr ML19324B2511989-10-27027 October 1989 LER 89-012-01:on 890720,discovered That Master Solenoid to Switchgear Room Halon Sys Disconnected Since 890629.Caused by Personnel Error Resulting from Lack of Written Procedure. Procedure Revised to Apply Temporary mods.W/891027 Ltr ML19325C3281989-10-10010 October 1989 LER 89-016-00:on 890908,determined That as-found Condition of Resistance Temp Detectors Did Not Match Tested Configuration.Cause Not Stated.Subj Detectors Will Be Sealed,Per Environ Qualification requirements.W/891010 Ltr ML19325C3701989-10-0909 October 1989 LER 89-017-00:on 890907,determined That Discrepancy in Acceptance Criteria of Surveillance Test Procedure M-452-0 Resulted in Failure to Fully Comply W/Requirements of Tech Spec 3.9.12.Main Cause undetermined.W/891009 Ltr ML20024F3771983-08-25025 August 1983 LER 83-044/03L-0:on 830808,diesel Generator 12 Tripped on Low Jacket Cooling Water Pressure While Verifying Operability.Cause Not Stated.Coolant Jacket Vented & Large Amount of Air Found.No Evidence of leakage.W/830825 Ltr ML20024F5731983-08-25025 August 1983 LER 83-040/03L-0:on 830727,control Room Air Conditioner 11 Discovered W/Damaged Condenser Fan.Caused by Loose Set Screws Securing Fan in Position.Set Screws Restored. W/830825 Ltr ML20024E6761983-08-0404 August 1983 Updated LER 83-011/03X-1:on 830207,during Surveillance Testing ESFAS a Logic Sequencer Failed,Rendering Diesel Generator 12 Inoperable.Caused by Intermittent Operation of Module Test Push Button.Part replaced.W/830804 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20024D0071983-07-0808 July 1983 LER 83-035/03L-0:on 830610,during Normal Power Operation,Esf Actuation Sys Channel Zg Steam Generator Level Tripped. Caused by Failed Vitro Isolator Module.Module Replaced.W/ 830708 Ltr ML20024D0091983-07-0808 July 1983 LER 83-033/03L-0:on 830603,fire Detection Instrumentation in Containment Southeast Electrical Penetration Determined Inoperable.Repair Impossible Due to Inaccessability of Protecto wire.W/830708 Ltr ML20024B8231983-06-23023 June 1983 LER 83-029/03L-0:on 830524,during Normal Operation, Surveillance Testing Indicated Neither Spent Fuel Pool Exhaust Fans 11 or 12 Would Maintain Required Negative Pressure.Caused by Clogged HEPA filters.W/830623 Ltr ML20024C0141983-06-22022 June 1983 Updated LER 81-080/03X-1:on 811116,discovered Weep from Cracked Weld on Spent Fuel Cooling Pump Discharge Vent Line 12.Caused by Inadequate Support of Vent Line.Support Assembly installed.W/830622 Ltr ML20024A8881983-06-16016 June 1983 LER 83-032/03L-0:on 830523,containment Isolation Sys B Logic Module Would Not Actuate.Caused by Defective Vitro Labs Std Logic Module.Module Replaced.Failed Module Returned to Vitro Labs for Repair & testing.W/830616 Ltr 1999-08-23
[Table view] Category:RO)
MONTHYEARML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20029C7321994-04-22022 April 1994 LER 94-004-00:on 940221,discovered Corrosion of Three Nuts on One of Incor Instrumentation Reactor Vessel Head.Caused by Increase of Wet Boric Acid.Leaking Flanges Repaired.W/ 940422 Ltr ML20046B4731993-07-30030 July 1993 LER 93-005-00:on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat exchanger.W/930730 Ltr ML20046A4911993-07-22022 July 1993 LER 93-003-00:on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed. W/930722 Ltr ML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20045G7281993-07-0808 July 1993 LER 93-002-00:on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve opened.W/930708 Ltr ML20045G8661993-07-0808 July 1993 LER 93-004-00:on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant startup.W/930708 Ltr ML20045E7361993-06-29029 June 1993 LER 93-002-01:on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances performed.W/930629 Ltr ML20029B1261991-02-28028 February 1991 LER 91-001-00:on 910129,tubing in Air Start Sys for Emergency Diesel Generator Failed During Seismic Event. Caused by Error in Design of EDG Air Start Sys.Permanent Mod to Sys installed.W/910228 Ltr ML20028H8011991-01-24024 January 1991 LER 90-002-01:on 900116,determined That 891211 Reconstitution of More than One Spent Fuel Assembly Per Time in Violation of Fuel Handling Incident Safety Analysis. Caused by Deficient procedure.W/910124 Ltr ML20044A1861990-06-20020 June 1990 LER 87-002-01:on 861203,section of Thin Wall Found on Main Steam Line W/Readings Below Allowable Min of 0.95 Inches. Caused by Grinding of Edge of Pipe to Achieve Proper fit-up for Welding.Relief from IWB-3610 granted.W/900620 Ltr ML20043G1071990-06-13013 June 1990 LER 89-019-01:on 891128,determined That for Approx 10 Yrs, from 1979-1989,requirement to Lock HPSI Discharge Header Isolation Valves Shut Not Implemented.Caused by Inadequate Mgt Attention.Test Procedures modified.W/900613 Ltr ML20043F1221990-06-0404 June 1990 LER 90-017-00:on 900505,pin Hole Leak Observed in Discharge Piping of Saltwater Pump 13.Caused by Localized Corrosion. Leaking Spool Piece Removed & Blank Flange Installed. W/900604 Ltr ML20043A7871990-05-21021 May 1990 LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr ML20043A3441990-05-14014 May 1990 LER 90-014-00:on 900413 & 19,unit Entered Tech Spec Limiting Condition of Operation 3.0.3 Due to Potential Inoperability of Three Out of Four Reactor Protection Sys Delta T Power Channels.Caused by Lack of Procedure guidance.W/900514 Ltr ML20043A3401990-05-14014 May 1990 LER 90-013-00:on 900413,determined That Axial Shape Index Channels Out of Spec & Inoperable.Caused by Inadequate Understanding of Design Basis for Excore/Incore Comparison. Design Basis for Excore/Incore improved.W/900514 Ltr ML20042G4521990-05-0707 May 1990 LER 90-015-00:on 900407,discovered That Relay Contact Which Actuates Reactor Trip Breaker Shunt Trip Not Adequately Functionally Tested.Caused by Failure to Examine Circuit in Detail When Test developed.W/900507 Ltr ML20042F5801990-05-0404 May 1990 LER 90-012-00:on 900406,identified That Procedure for LOCA Would Not Ensure post-LOCA Core Flush Would Be Initiated in Time to Prevent Boron Precipitation.Caused by Personnel Error.Configuration Mgt Program strengthened.W/900504 Ltr ML20012E9931990-03-29029 March 1990 LER 90-008-00:on 900227,determined That Surveillance Procedure M-280-0 Did Not Include Steps to Fully Test Control Room Recorder for Hydrogen Analyzers.Caused by Personnel Error.Procedure Revised on 900308.W/900329 Ltr ML20012F0001990-03-28028 March 1990 LER 89-006-01:on 890508,containment Iodine Filters Outside Design Basis Due to Equipment Qualification.Recalculation of Total Integrated Radiation Dose to Cables for Filter Fans Demonstrated Cable qualified.W/900328 Ltr ML20012E9951990-03-28028 March 1990 LER 89-014-01:on 890723,determined That Salt Water Header Not Capable of Withstanding Seismic Event Intact.Caused by Inadequate Welding of Blind Spool Pieces in Pipe.Insp Revealed Spools Capable as installed.W/900328 Ltr ML20012E0101990-03-26026 March 1990 LER 90-009-00:on 900224,failure to Meet Action Requirement Re Tech Spec 3.7.12.Caused by Personnel Error.Cables Removed from Doorway in Charging Pump Room & Not Allowed to Be Placed in doorway.W/900326 Ltr ML20012C4971990-03-15015 March 1990 LER 90-007-00:on 900216,discovered That Supervised Circuits Associated W/Fire Detection Instruments Located in Reactor Coolant Pump Bays Not Been Included in Surveillance Test Procedure.Caused by Personnel error.W/900315 Ltr ML20012C4861990-03-12012 March 1990 LER 90-006-00:on 900209,determined That Four Fire Dampers Missing.Caused by Not Identifying Penetrations as Requiring Dampers When Fire Hazards Analysis of Plant Conducted.Hourly Fire Watch Continued.Missing Dampers installed.W/900312 Ltr ML20012B8991990-03-12012 March 1990 LER 89-023-01:on 891220,determined That Pipe Rupture in nonsafety-related Svc Water Subsystem Could Result in Rapid Draining of Subsystems That Serve Auxiliary Bldg.Task Force Formed to Determine Corrective actions.W/900312 Ltr ML20012B4221990-03-0606 March 1990 LER 89-012-01:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed.Caused by Procedural Deficiency.Procedures Revised to Include Valve & Surveillance Test Program Instruction revised.W/900306 Ltr ML20011F2701990-02-27027 February 1990 LER 90-001-01:on 900109,determined That Surveillance Tests Used to Perform Channel Calibr Tests for Acoustic Flow Monitoring Devices Inadequate.Caused by Personnel Error & Inadequate Procedures.Swapped Leads restored.W/900227 Ltr ML20011F2091990-02-27027 February 1990 LER 89-026-00:on 891128,determined That Particulate Levels in Samples Taken from Lower Third of Tanks Exceeded Allowable Limits.Caused by Inadequate Sampling Technique. Tanks Cleaned & Filled W/Clean fuel.W/900227 Ltr ML20006F8601990-02-22022 February 1990 LER 90-004-00:on 900123,discovered Fire Barrier Penetration Seal Open for Indeterminate Time W/O Performing Tech Spec 3.7.12.a Required Actions.Caused by Personnel Error. Temporary Fire Seal installed.W/900222 Ltr ML20006E0521990-02-0808 February 1990 LER 90-001-00:on 891221,discovered That Acoustic Indications for One PORV & One Safety Valve Were Reversed During Surveillance Test.Caused by Personnel Error.Swapped Leads Restored to Proper configuration.W/900208 Ltr ML20006B4801990-01-26026 January 1990 LER 89-022-00:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed,Violating Tech Specs.Caused by Procedural Deficiency.Surveillance Test Procedure Revised to Include Deleted valves.W/900126 Ltr ML19354D8931990-01-17017 January 1990 LER 89-024-00:on 891218,determined That Wires Which Connect Actuation Device Logic Relay Contacts to Remainder of Circuit Not Tested During Channel Calibr Test.Caused by Inadequate Test.Test Program Upgrade underway.W/900117 Ltr ML20005F1921990-01-10010 January 1990 LER 89-025-00:on 891208,Tech Spec Action Statement Entered When Ventilation Ducts Penetrating Fire Barrier Could Not Be Accessed to Determine If Fire Dampers Installed.On 891211, Fire Watch Missed.Caused by Personnel error.W/900110 Ltr ML20005E3971989-12-28028 December 1989 LER 89-019-00:on 891128,discovered That HPSI Discharge Header Isolation Valves Not Locked Shut When RCS in Water Solid Condition,Resulting in Operation Outside Design Basis. Procedure Revised to Require Valves closed.W/891228 Ltr ML19351A4551989-12-13013 December 1989 LER 89-020-00:on 891113,determined That Some Solenoid Valves & Valve Power Supplies for Saltwater Sys May Not Be Able to Perform Design Function After Design Basis Seismic Event. Cause Undetermined.Power Supplies upgraded.W/891213 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML19325F3951989-11-10010 November 1989 LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr ML19325E8221989-11-0303 November 1989 LER 89-007-01:on 890505,evidence of Reactor Coolant Leakage from 120 Pressurizer Vessel Heater Penetrations Discovered. Caused by IGSCC of Inconel 600.All Penetrations Using J-welds & Inconel 600 Visually inspected.W/891103 Ltr ML19324B2511989-10-27027 October 1989 LER 89-012-01:on 890720,discovered That Master Solenoid to Switchgear Room Halon Sys Disconnected Since 890629.Caused by Personnel Error Resulting from Lack of Written Procedure. Procedure Revised to Apply Temporary mods.W/891027 Ltr ML19325C3281989-10-10010 October 1989 LER 89-016-00:on 890908,determined That as-found Condition of Resistance Temp Detectors Did Not Match Tested Configuration.Cause Not Stated.Subj Detectors Will Be Sealed,Per Environ Qualification requirements.W/891010 Ltr ML19325C3701989-10-0909 October 1989 LER 89-017-00:on 890907,determined That Discrepancy in Acceptance Criteria of Surveillance Test Procedure M-452-0 Resulted in Failure to Fully Comply W/Requirements of Tech Spec 3.9.12.Main Cause undetermined.W/891009 Ltr ML20024F3771983-08-25025 August 1983 LER 83-044/03L-0:on 830808,diesel Generator 12 Tripped on Low Jacket Cooling Water Pressure While Verifying Operability.Cause Not Stated.Coolant Jacket Vented & Large Amount of Air Found.No Evidence of leakage.W/830825 Ltr ML20024F5731983-08-25025 August 1983 LER 83-040/03L-0:on 830727,control Room Air Conditioner 11 Discovered W/Damaged Condenser Fan.Caused by Loose Set Screws Securing Fan in Position.Set Screws Restored. W/830825 Ltr ML20024E6761983-08-0404 August 1983 Updated LER 83-011/03X-1:on 830207,during Surveillance Testing ESFAS a Logic Sequencer Failed,Rendering Diesel Generator 12 Inoperable.Caused by Intermittent Operation of Module Test Push Button.Part replaced.W/830804 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20024D0071983-07-0808 July 1983 LER 83-035/03L-0:on 830610,during Normal Power Operation,Esf Actuation Sys Channel Zg Steam Generator Level Tripped. Caused by Failed Vitro Isolator Module.Module Replaced.W/ 830708 Ltr ML20024D0091983-07-0808 July 1983 LER 83-033/03L-0:on 830603,fire Detection Instrumentation in Containment Southeast Electrical Penetration Determined Inoperable.Repair Impossible Due to Inaccessability of Protecto wire.W/830708 Ltr ML20024B8231983-06-23023 June 1983 LER 83-029/03L-0:on 830524,during Normal Operation, Surveillance Testing Indicated Neither Spent Fuel Pool Exhaust Fans 11 or 12 Would Maintain Required Negative Pressure.Caused by Clogged HEPA filters.W/830623 Ltr ML20024C0141983-06-22022 June 1983 Updated LER 81-080/03X-1:on 811116,discovered Weep from Cracked Weld on Spent Fuel Cooling Pump Discharge Vent Line 12.Caused by Inadequate Support of Vent Line.Support Assembly installed.W/830622 Ltr ML20024A8881983-06-16016 June 1983 LER 83-032/03L-0:on 830523,containment Isolation Sys B Logic Module Would Not Actuate.Caused by Defective Vitro Labs Std Logic Module.Module Replaced.Failed Module Returned to Vitro Labs for Repair & testing.W/830616 Ltr 1999-08-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval 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 ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
[Table view] |
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. ,' B ALTIMORE GAS AND ELECTRIC CALVERT CLIFFS NUCLEAR POWER PLANT 1650 CALVERT CLIFFS PARKWAY
- LUSBY. MARYLAND 20657-4702 CHARLES H. CRUSE
^ "
c vin rrs July 30, 1993 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: Document Cc.ntrol Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-317; License No. DPR 53 Licensee Event Report 93-005 TS 3.0.3 Entered, Due to Both Containment Spray Systems Inorerable The attached report is being c o nt to you as required under 10 CFR 50.73 guidelines. Should you have any questions regarding this report, we will be pleased to discuss them with you.
Very truly yours,
-f V CHC/RCG/bj d Attachment cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr. , NRC T. T. Martin, hTC P. R. Wilson, NRC R. I. McLean, DNR J. H. Walter, PSC Director, Office of Management Information and Program Control 9309040253 930730 030040- 3n f#,#j ADOCK 05000317 PDR >
S PDR gg
- N N NRC FORM 366 U. S. NUCLEAR REoVLATORY COMMISSION N *
- ESTMTED EURDEM FER ESFDPRITo COMFLYWITHTK3 NfC3MATION
- ** COLLECRON EOUEsT: 500 HFE FCMAFO COMMDRS EGARDWG Bm ESTmTE Tome EMMTON AND RECORDS MMAGEMENT LICENSEE EVENT REPORT (LER) LVWCH (MNBS 7714). U S NUCLEAR FEGULATORV FNMcW(
WASHirGTOtt DC 20'Hr0001. ANDTo THE PAPOWoHK FE. DUCTION PFulECT (See reverse for reauired number of diaits/ characters for each block) Q1500104) OFFICE OF M4%GEMENT AND BUDGET,WASHirGTOf( DC20'in FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3)
Calvert Clif f s, Unit 1 05000 317 1 OF 07 TITLE (4)
TS 3.0.3 Entered, Due to Both Containment Spray Systems inoperable EVENT DA1E (5) LER NUMBER (6) REPORT DATE (7) OTHER F ACILITIE S INVOLVED (8)
^' I MOMTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NUMBER 05000 06 30 93 93 - 005 -
00 07 30 93 05000 OPERATING THff REPORT tS SUDMfTTED PURSUANT TO THE REOUIREMENT9 OF 10 CFR -(Check one or more) f11)
MODE (9)
I 20.402(b) 20 405(c) 50 73(a)(2)(ev) 73 73 gy POWER 73 7DC)
LEVEL 100 20 405(a)(1)@ w.3c(c)(2) 2 73(a)(2)(vii) X mm CD) X 20.405(a)(1)(iii) 50 73(a)(2)(i) 50.73(a)(2)(viii)(A) (Speedy in Atatract below and in 20.405(a)(1)0v) Text, NRC Form 30/A) 50.73(a)(2)0i) 50.73(a)(2)(viii)(B) 20 405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER Dnclude Area Code)
R. C. Gradle, Compliance Engineer 401 260-3738 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYST E M COMPONENT ABE M CAUSE SYSTEM COMPONENT TURER NPRDS TURER NPRDS B CC V M120 Y SUPPLEME NTAL REPORT f YPECTED (14) EXPECTED MONTH DAY YEAR YES 8 "8 " '**' "
X No (if yes complete FXPFCTFD SUBMISSION DATF) DATE (15)
ABSIRAC1 (LJmit to 1400 spaces,i.e , approxamarely15 single 4p < t, pewntien hnes) (10) on June 30, 1993, at 2:00 p.m., Calvert Cliffs Unit 1 entered Technical Specification 3.0.3 for 45 minutes because both independent Containment Spray (CS) Systems were inoperable. No. 12 CS System was inoperable for scheduled maintenance. No. 11 CS System was determined to be inoperable because the outlet valve for component cooling water supplying its shutdown cooling heat exchanger was broken. Immediate corrective action restored No. 11 CS System to OPERABLE status while the Unit was at 100 percent power. This event l resulted in no public health or safety consequences.
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l The affected valve actuator had disconnected. We believe the actuator connecting linkage separated due to pivot locking plate failure. The replacement plcte subsequently cracked. Similar cracked plates were found on two identical Unit 2 valves. Plate material was a sintered alloy. The cracked plates were replaced with carbon steel plates. We plan to install carbon steel pivot locking plates on similar style valves. This report satisfies 10 CFR Part 21 requirements.
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PRC Form 3E pg5
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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31504104 f! Lea EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE To COMPLY W!TH THIS INFoRMATioN CoufCTloN REQUEST: 50.0 HRS FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARCMG BURDEN ESTIMATE To THE INFoRMATON AND RECORDS MANAGEMENT BRANCH (MNBB 7714L U.S NUCLEAR TEXT CONTINUATION REcutAToRy CoMMssON. WASHINGTON. DC aosssmoi. AND To THE PAPERWORK REDUCTON PROJECT (31sG 0104L oFFCE oF MANAGEMENT AND BUDGET, WASHINGTON. DC 20503 F ACluTY NAME (1) DOCKET NUMBER A LER NUMBER @ PAGE (4)
Calvert Cliffs, Unit 1 05000 3 1 7 93 -
005 - 00 02 OF 07 TtxT y mo. .p.c. w.a. .m on.i wp.= or NRC ro, 38eA3 ci7)
I. DESCRIPTION OF EVENT On June 30, 1993, at 2:00 p.m. Calvert Cliffs Unit 1 entered Technical Specification (TS) 3.0.3 for 45 minutes because both independent Containment Spray (CS) Systems were inoperable. No. 12 CS System was inoperable for scheduled maintenance. No. 11 CS System was subsequently determined to be inoperable because the outlet valve for Component Cooling Water (CCW) supplying its shutdown cooling (SDC) heat exchanger was broken. Immediate corrective action restored No. 11 CS System to OPERABLE status while the Unit was at 100 percent power.
Technical Specification 3.6.2.1 Limiting Condition for Operation (LCO) for the CS System requires that two independent CS Systems and associated SDC heat exchangers be OPERABLE in Modes 1-3. The associated ACTION requirement for this LCO allows one CS System to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ACTION limit for No. 12 CS System was entered on June 30, 1993, at 2:50 a.m.
when No. 12 Saltwater (SW) loop was removed fron service for scheduled maintenance. The removal of No. 12 SW loop also rendered one group of containment air coolers out of service.
On June 27, 1993, at 4:00 a.m., SDC was secured with No. 11 SDC heat exchanger CCW outlet control valve (1-CC-3828-CV) shut. This is the last time this valve was operated prior to June 30, 1993.
On June 30, post-maintenance flow testing of No. 13 CCW pump was in progress.
Control Room operators were aware that Control Room valve position indication for 1-CC-3828-CV was inoperable due to a broken open position indicator limit switch. When 1-CC-3828-CV was opened an expected increase in CCW flow did not occur. Immediate inspection of the valve, revealed that the connecting link from the actuator stem had disconnected from the vane arm. This failure rendered the valve inoperable in the shut position. The Control Room was immediately informed of the valve failure. With both CS Systems inoperable, the Snift Supervisor entered TS 3.0.3 at 2:00 p.m.
Plant engineering and maintenance personnel inspected the valve actuator linkage and discovered that the pivot locking plate, which resembles a square washer, was missing from the pivot screw (see Figure 1). The pivot screw is part of an assembly that connects the actuator connecting link to the valve vane arm.
Emergency maintenance was conducted on 1-CC-3828-CV. Replacement parts were obtained off a similar spare valve actuator and the valve was repaired and returned to service. Technical Specification 3.0.3 was exited at 2:45 p.m.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _.._____.___-__-.__-.__.___m_ _ _ . _ _ _ _ _ - _ _ . _ _ - - - _ .__._
NRC [ORM 36CA U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 per) EXPIRES 5/31/95 l ESTIMATED BURDEN PER RESPONSE To COMPLY WITH THIS INFORMATON CoLLECTON REQUEST 60.0 HRS. FORWARD UCENSEE EVENT REPORT (LER) couuENTs ReGARaNo BURoEN ESTuATE To TwE mroRuATON :
AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U 8. NUCLEAR TEXT CONTINU ATION REGutATony couussON, wAsMuGroN. oC rosssoooi, ANo To THE PAPERWORK REDUCTON PROJECT (315CLO104), OFFICE oF j MANAGEMENT AND BUDGET, WASHINGTON, oC 20603.
F ACILITY NAME (1) DOCKET NUMBER (4 LER NUMBER (3) PAGE (4) ;
Calvert Cliffs, Unit 1 05000 3 1 7 93 -
005 - 00 03 OF 07 TEXT Of more space a requited, use aoMonal copees of NRC Form 366A) (17)
II. CAUSE OF EVENT The immediate cause of this event was the separation of the valve actuator connecting link from the valve vane arm. We believe that the pivot locking .
plate on 1-CC-3828-CV cracked in half allowing the connecting linkage to slip !
free of the vane arm. ,
l On June 30, 1993, a visual inspection was conducted on the identical Unit 2 valves (2-CC-3828-CV and 2-CC-3830-CV). Both valves were found to have cracks in their pivot locking plates. The Shift Supervisor was informed and maintenance orders were issued to replace these pivot locking plates.
Ten other similar style safety-related valves were identified in the Unit 1 and ;
Unit 2 CCW and Service Water (SRW) Systems. These valves were visually inspected on June 30, 1993, and no cracks were found.
On July 9 and 10, 1993, the cracked pivot locking plates on 2-CC-3828-CV and i 2-CC-3830-CV, were replaced. The old cracked plates were mistakenly discarded, i so the opportunity was lost to perform a metallurgical failure analysis. l I
Replacement plates were purchased from the vendor as non-stock commercial grade ;
and were dedicated for use as safety-related items. Critical characteristics for the plate described the material as either carbon steel or sintered iron copper alloy. The same part number (370295-111-779) applies to both materials.
During receipt inspection both plates were verified to be ferrous material.
Discussions with the vendor revealed that they currently supply only carbon steel pivot locking plates with improved ductility characteristics under this part number. They stated that in October 1989, a drawing change was made to include carbon steel as a material for the plates.
On July 2 a small crack in the replacement pivot locking plate for 1-CC-3828-CV was discovered. This plate had been obtained from a similar spare valve assembly on June 30. A maintenance order was issued to replace this pivot locking plate. ,
On July 22, 1993, the cracked pivot locking plate on 1-CC-3828-CV was replaced with a carbon steel pivot locking plate. The replaced plate had two cracks oriented 90 degrees apart and was verified to be sintered alloy material. A detailed failure analysis on the replaced plate identified the brittle nature of the material as susceptible to this type of inservice failure.
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NRC FORM 36CA U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (sea EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE To COMPLY WW THIS INFoRMATON CodICTON REQUEST 50 0 HMS FORWARD ,
LICENSEE EVENT REPORT (LER) CouuEwTS ReoARDiNG BURDEN tsnuATE To THE iNFoRuaTON i AND RECORDS MANAGEMENT BRANCH {MNBB 7714L U.S. NUCLEAR !
TEXT CONTINUATION REovuToRY Couw SSON. WASHINGTON. oC asseooi, AND To ,
THE PAPERWORK REDUCTON PROJECT Cit 60-0104), OFFICE OF j UANAGEMENT AND BODGET, WASHINGTON. DC 20$C3 F ACluTY NAME (1) DOCKET NUMBER (a LER NUMBER (3) PAGE (4)
Calvert Cliffs, Unit 1 05000 3 1 7 93 -
005 -
00 04 0F 07 TEXT y mo,. .o.r a,.o. o .ooit on.i cop or Nrc Form assA) tit) t A review of previous maintenance orders was conducted for the eight similar CCW ;
control valves, but did not identify any previous valve inoperability due to -
failed pivot locking plates. We also conducted two historical queries of the Nuclear Plant Reliability Data System (NPRDS) under the general valve model number (34000) and the valve actuator (Case No. 18L, 37-18), but no pivot t locking plate failures were identified. ,
III. ANALYSIS OF EVENT The CS System is designed to provide sufficient heat removal capability to ,
maintain containment pressure and temperature below established design values i following a loss-of-coolant accident (LOCA). Each CS System consists of a 50 percent capacity pump, a SDC heat exchanger, and a spray header. The SDC heat exchanger is cooled by the CCW System. After a LOCA, suction for the CS pumps is taken directly from the refueling water tank and discharged through the SDC heat exchangers to containment.
The CS System is redundant to the Containment Air Cooling System which consists of two independent groups of containment air coolers, with two units in each ;
group cooled by a SRW System. With three of four cooling units in operation, the Containment Air Cooling System provides the same heat removal capability as ,
the two CS Systems.
The short time that both CS Systems and one group of containment air coolers was inoperable resulted in no public health or safety consequences. The safety significance of this event was minimized based on the following.
The scenario of concern is a LOCA concurrent with a loss of offsite power (IDOP), a highly unlikely scenario. We have identified that 1-CC-3828-CV was shut from the Control Room on June 27, 1993. Thus, the maximum hypothetical time of CS System inoperability concurrent with one group of inoperable containment air coolers is limited to the approximate 12-hour period following the securing of No. 12 SW loop and the restoration of 1-CC-3828-CV to OPERABLE status. The probability of such an event occurring in so short a period of time was extremely low.
This event is considered reportable in accordance with 10 CFR 50.73(a)(2)(1)(B),
10 CFR 50.73(a)(2)(v), and 10 CFR Part 21.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 313 0104 f5 e2) EXPIRES 5/31/95 ESTIMATED BURDEN PER NBPoNSE TO COMPLY WlTH THIS INFoRMATiON COLLECTON REQUEST: SO 0 HRS. FORWARD LICENSEE EVENT REPORT (LER) CouuCNTs REsAmNG BURDEN EsTiuaTE To THE iNroRuAfoN AND RECoRDB MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR TEXT CONTINUATION REGULATORY COMMSSON. WASHWGToN, DC 205554xH, AND TO THE PAPERWORK REDUCTON PROJECT (31500104), oFFtCE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20$03.
F ACluTV NAME (1) DOCKET NUMBER (2) LER HUMBER (3) PAGE (4)
Calvert Cliffs, Unit 1 05000 3 1 7 93 -
005 -
00 05 0F 07 TtxT e mm..p.c ..w.o. .amons cop or NRC r awn on IV. CORRECTIVE ACTIONS Immediate corrective actions are completed as follows:
A. The CCW outlet valve actuator connecting link assembly from No. 11 SDC heat exchanger was replaced and TS 3.0.3 was exited at 2:45 p.m. on June 30, 1993.
B. The pivot locking plates on Unit 2 CCW valves for 21 and 22 SDC heat exchangers were replaced with carbon steel pivot locking plates on July 9 and 10,1993.
C. The appropriate maintenance personnel were sensitized to the importance of retaining the replaced, cracked pivot locking plate ;
for failure analysis.
Actions to prevent recurrence include:
A. On July 22, 1993, a carbon steel pivot locking plate was installed on 1-CC-3828-CV. I 1
B. Sintered alloy plates will be replaced with carbon steel pivot locking plates on other similar style safety-related valves in the plant.
C. The stock description for this pivot locking plate has been revised I such that only carbon steel pivot locking plates will be accepted in the future.
D. An Issue Report was generated concerning the inadvertent discarding of the cracked locking plates for 2-CC-3828-CV and 2-CC-3830-CV.
Corrective action to preclude this problem from recurring will be taken in accordance with our corrective action process. )
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' NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 maa EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE To COMPLY WITH THIS INFoRMATION COLLECTION REQUEST: 20 HRS. FORWARD UCENSEE EVENT REPORT (LER) CouuENTs REcAFoNG BuRoEN tsTiuATE To THE iNroRMATiON AND RECORDS MANAGEMENT BRANCH (MNB0 7714), U.S. NUCLEAR TEXT CONTINUATlON REGULATORY COMMISS40N, WASHINGTON, DC 2055540, AND To THE PAPERWORK REDUCTION PROJECT (3150 c104). OFFICE oF MANAGEMENT AND BUDGET, WASHINGTON, DC 23503, F ACILITY NAME (1) DOCKET NUMBER (33 LER NUMBER (3) PAGE (4)
Calvert Cliffs, Unit 1 05000 3 1 7 93 -
005 - 00 06 0F 07 TEXT pf more space is requued, peo addMkmal copese of NRC Form 36eA) (17)
V. ADDITIONAL INFORMATION A. Identification of Components and Systems referred to in this LER:
IEEE 803A/83 IEEE 805/84 Component or System Function ID System ID Containment Spray System N/A BE Component Cooling Water System N/A CC Saltwater System N/A BI Service Water System N/A BI' Containment Fan Cooling System N/A BK Pump P N/A Valve V N/A ;
Heat Exchanger HX N/A Cooler CLR N/A B. Previous Similar Events: I There has been one previous similar event involving entry into TS <
3.0.3 due to a concurrent inoperability of both CS Systems, but the !
cause is not related to this event. Details of the previous event I were provided in LER 318/92-002.
The valves which experienced pivot locking plate cracking are Masonellan model number 37-34211. The part number for the pivot locking plate is 370295-111-779. The vendor stated that carbon steel pivot locking plates have square edges and pivot locking plates made of sintered iron carbon alloy have rounded edges.
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HRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO.3150-0104 as21 EXPIRES 5/31/95 ESTIMATED BUFOEN PER e4ESPONSE TO COMPLY WriH THIS it#0RMATON COLLECTON REQUEST: 50 o HHS. FORWARD LICENSEE EVENT REPORT (LER) coMuEurs REaAroNo suRDEN EsTiMAtt TO THE wORuATON AND RECORDS MANACEMENT BRANCH (MNBB 7714) U.S. NUCLEAR TEXT CONTINUATION HEGULATORY COMMIC3ON WWUNGTON. DC 20555@01, AND TO THE PAPERWORK REDUC'ON PROJECT (31BC104). OFFCE OF MANAGEMENT AND BUDGET. W ASHINGTON. DC 20$03.
F ACluTY NAME (9) DOCKETNUMBER Q LER NUMBER (3) PAGE l4)
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FIGURE 1 34000 Butterfly Valves with 1-1/2" -- 4" Stroke Actuators PARTS REFERENCE No. Part Name No. Part No. No. Part No.
- 1. Body 13 Lock Washer 25. Clevis I
- 2. Vane 14. Body Cap Screw 26. Lock Nut
'3. Elastorner Liner 15 Bushing 27. Actuator Stem
- 4. Vane Shaft 16. Setscrew 28. Actuator Mounting Plate
- 5. Teper Pina 17. Key 29. Cap Screw
'6. Vane Shaft Bushing 18. Vane Arm 30. Lock Washer
'7. Pm nng 19. Pivot Screw 31. Nut
- 8. Pe:6ng Box Gland 20. Pivot Locking Plate 32. Cotter Pin
- 9. Gland Flange Stud 21. Castle Nut
- 10. Giand Fiange 22. Cotter Pan
- 11. Gland Flange Nut 23 Connecting Lie -
- 12. Actuator Mounting Bracket 24 Clevis Psn
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