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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors ML17335A5171999-02-11011 February 1999 LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted ML17335A5141999-02-10010 February 1999 LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405 ML17335A5011999-02-0101 February 1999 LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr ML17335A4951999-01-29029 January 1999 LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr ML17335A4961999-01-27027 January 1999 LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr ML17335A4921999-01-19019 January 1999 LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components ML17335A4721999-01-0606 January 1999 LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing ML17335A4691999-01-0606 January 1999 LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr ML17335A4661999-01-0505 January 1999 LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing ML17335A4631999-01-0404 January 1999 LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr ML17335A4481998-12-30030 December 1998 LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr ML17335A4581998-12-28028 December 1998 LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process ML17335A4281998-12-22022 December 1998 LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event ML17335A4111998-12-17017 December 1998 LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr ML17335A4141998-12-16016 December 1998 LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122 ML17335A4181998-12-16016 December 1998 LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria ML17335A3871998-12-11011 December 1998 LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing ML17335A3821998-12-0808 December 1998 LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr ML17335A3781998-12-0707 December 1998 LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr ML17335A3771998-12-0303 December 1998 LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned ML17335A3741998-12-0202 December 1998 LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3 1999-09-17
[Table view] Category:RO)
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors ML17335A5171999-02-11011 February 1999 LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted ML17335A5141999-02-10010 February 1999 LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405 ML17335A5011999-02-0101 February 1999 LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr ML17335A4951999-01-29029 January 1999 LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr ML17335A4961999-01-27027 January 1999 LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr ML17335A4921999-01-19019 January 1999 LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components ML17335A4721999-01-0606 January 1999 LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing ML17335A4691999-01-0606 January 1999 LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr ML17335A4661999-01-0505 January 1999 LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing ML17335A4631999-01-0404 January 1999 LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr ML17335A4481998-12-30030 December 1998 LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr ML17335A4581998-12-28028 December 1998 LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process ML17335A4281998-12-22022 December 1998 LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event ML17335A4111998-12-17017 December 1998 LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr ML17335A4141998-12-16016 December 1998 LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122 ML17335A4181998-12-16016 December 1998 LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria ML17335A3871998-12-11011 December 1998 LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing ML17335A3821998-12-0808 December 1998 LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr ML17335A3781998-12-0707 December 1998 LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr ML17335A3771998-12-0303 December 1998 LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned ML17335A3741998-12-0202 December 1998 LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3 1999-09-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17335A5631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr ML17335A5621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr ML17335A5481999-09-30030 September 1999 Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3). ML17335A5451999-09-28028 September 1999 Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios. ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1481999-09-17017 September 1999 Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2. ML17326A1211999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr ML17326A1201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17335A5461999-08-0202 August 1999 Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates. ML17326A0871999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr ML17326A0861999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0511999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr ML17326A0501999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17326A0061999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr ML17326A0071999-05-31031 May 1999 Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17335A5301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr ML17335A5291999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5491999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr ML17325B5441999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B5671999-03-0202 March 1999 Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218. ML17325B4631999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr ML17325B4621999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors 1999-09-30
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k.C CELERY'Ig@DLR 2'9l DI RKQl%RA~N RIDgiYSTEM ACCESSION NBR:8810130119 DOC.DATE: 88/09/30 NOTARIZED:
NO DOCKET'ACIL:50-315 Donald C.Co'ok Nuclear Power Plant, Unit 1, Indiana&05000315 AUTH.NAME AUTHOR AFFILIATION POSTLEWAIT,T.K.
Indiana Michigan Power'Co.(formerly Indiana&Michigan Ele SMITH,W.G.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION p g W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR
~ENCL J SIZE: TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.NOTES: SUB ECT: LER 88-007-00:on 880908,ice build-up in ice condense" flow assa es due to sublimation.
ltr.D'ECIPIENT ID CODE/NAME PD3-1 LA STANGPJ INTERNAL: ACRS MICHELSON ACRS WYLZE AEOD/DSP/NAS AEOD/DSP/TPAB DEDRO NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES TELFORDPJ RES/DSIR/EIB EXTERNAL: EG&G WILLIAMSgS H ST LOBBY WARD NRC PDR NSIC MAYS,G COPIES.LTTR ENCL 1 1 1 1 1 1 1.1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 4 4 1 1 1 1-1 1 RECIPIENT ID CODE/NAME PD3-1 PD ACRS MOELLER AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB
- 10 NRR/DREP/RAB 1'0 NRR DRZS/SIB 9A 02 RES/DSIR DEPY RGN3 FILE 01 FORD BLDG HOY,A LPDR NSIC HARRZSgJ COPIES LTTR'ENCL 1 1 2 2 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D D'TOTAL NUMBER OF COPIES REQUIRED: LTTR'46 ENCL 45 NRC Form 355 (943)LICENSEE EVENT REPORT{LER)US.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3150010l EXPIAES: SISIISS FACILITY NAME (I)D.C.Cook Nuclear Plant-Unit 1 TITLE (Sl DOCKET NUMBER (2)PA 0 5 0 0 03 151OF1 5 Ice Build-Up in Ice Condenser Flow Passages Due to Sublimation EVENT DATE (5)LFR NUMBER (5)REPORT DATE It)OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR SEQUENTIAL NUMBER MONTH OAY NUMBER YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 0 9088 8 88 0 0 7 00 0 9 30 8 8 0 5 0 0 0 OPE RAT INC MODE (9)POWER LEvEL 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 50.73(s)(2Hlv) 50.73(s H2 Hv)50.734)(2)(vS I 50.73(e)(2)(vill)IAI 50.73(s)l2)(vI5 I (5)50.73(s)(2)(s) 20A05(cl 50.35(c)(Il 50.35(cl(2) 50.73(e)(2)(ll 50.73(e)(2)(5)50.734)(2)(III)20.402(bl 20A05(~l(1)(l)20.S05(s)(I IIII)20A05(~l(1 Hill)20AOS (s I (I I (I v)20AOS(el(1)(vl LICENSEE CONTACT FOR THIS LER (12I 0 THE REDUIREMENTB oF 10 cFR (Il Icnecc one or more of the Ioriowinol (11 73.71DI)73.71(c)OTHER ISpeclfy in Abrovct below end In Test, NIIC Form 366AI NAME T.K.Postlewait-"Technical Engineering Superintendent TELEPHONE NUMBER AREA CODE 616465-5901 COMPLETE ONE LIME FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER r I EPORTABLE'3 4: TO NPADS;.6y.N.IRMA!CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTABLE TO NPRDS XVPMa ke%m SUPPLEMENTAL REPORT EXPECTED (Icl YES III yer, complere EXPECTED SUBMISSION DATE)NO AssTAAGT ILimlt to Ierx)rpecet, I.e., epprocimetely fifteen elnole specs typewrltren lined (1st MONTH OAY EXPECTED SUBMISSION OATS (15)YEAR On September 8, 1988, with Unit 1 in Mode 4 (Hot Shutdown), flow passage inspections of the ice condenser revealed frost and ice buildup on the lattice frames of greater than 3/8 inch in a total of thirty-six flow passages in nine of the twenty-four ice condenser bays.Technical Specification (T/S)4.6.5.1.b.3 limits frost or ice buildup in flow passages to a nominal thickness of'3/8 inch.According to this T/S, buildup exceeding this limit in two or more flow passages per bay is evidence of abnormal degradation.
Though our evaluation has concluded that the degradation is not serious, we believe issuance of this voluntary LER is appropriate'since some degradation has been.identified.
Actions taken to correct the abnormal degradation included manual cleaning of the flow passages.In addition an internal investigation of the event was conducted.
The results of T/S Surveillances regarding frost and ice that forms in the flow passages is being monitored to ensure that any adverse trends in the amount of ice and frost buildup between surveillances will be identified.
The impact of frost and ice buildup in the flow passages is also being studied in conjunction with the other utilities with ice condenser containments.
NRC Form (903)8810130119 880'7)30 S 355 NRC FBOB 3BBA (983)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3)50-OIBB EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER IB)Q5(SBOVENTIAL NUMBER ,'gbP REVISION NVMBBR PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///mate g>>CB/B nqakaf, BBB atCL5Wal HRC FBNR 388AS/I Ill 0 5 0 0 0 3]5 8 8 0 0 7 0 0 020" 15 Conditions Prior to Occurrence Unit 1 in Mode 4 (Hot Shutdown)Descri tion of Event The as-found visual inspection of ice condenser (EIIS/COND) flow passages conducted on September 8, 1988, identified frost and ice accumulation greater than 3/8 inch in two flow passages in Bay 1, two flow passages in Bay 2, four flow passages in Bay 3, two flow passages in Bay 4, four flow passages in Bay 6, two flow passages in Bay 8, two flow passages in Bay 12, two flow passages in Bay'14 and two flow passages in Bay 15.Subsequently, the inspection was expanded to include at least twenty additional flow passages in each affected bay.This inspection revealed an additional two flow passages in Bay 2, six flow passages in Bay 3 and six flow passages in Bay 4 with more than 3/8 inch frost and ice buildup.A total of thirty-six flow passages were affected.There are a total of 3072 flow passages in the Ice Condenser.
Attachments 1 through 11 graphically describe the geometry of the flow passages and the location of the ice/frost accumulation.
Technical Specification (T/S)4.6.5.l.b.3 requires that the ice condenser be determined operable at least once per 9 months byverifying, via visual inspection of at least two flow passages per ice condenser bay, that accumulation of frost or.ice on flow passages between ice baskets (EIIS/COND-BSKT), past lattice frames (EIIS/COND-FRM), through the intermediate and top deck floor grating, or past the lower inlet plenums support structures (EIIS/COND-SPT) and turning yanes is restricted to a nominal thickness of 3/8 inch.If one flow passage per bay-is found to have an accumulation of frost or ice greater than this thickness, a representative sample of twenty additional flow passages from the same bay shall be visually inspected.
If these additional flow passages are found acceptable, the surveillance, program may proceed considering the single deficiency as unique and acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation-of the ice condenser.
The affected flow passages were manually cleaned to remove the accessible frost and ice buildup.NRC FORM 3BBA 19'83)*U.S.GPO:1985.0824 538/455 NRC Form 368A (84)3)LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.S.NUCLEAR REGUI.ATORY COMMISSION APPROVEd OMS NO.3I50-0(04 EXPIRES: 8/31/88 FACILITY NAME l)I OOCI(ET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL NUMBER REVISION NUMBER PAGE (3)D.C.Cook Nuclear Plant-U 1 TEXT/$/IRBB g>>CB 4I/BEN)BIS uW~NRC%%drm 38543/(17)3 1 5 8 8 0 0 7 0 0 0 3 5 Additional factors considered as possible contributors to the frost and ice accumulation included: 1)during the surveillance interval prior to the September 8, 1988 test, several of the 60 air handling units (AHU)(EIIS/AHU)(used to maintain ice condenser temperature) were intermittently inoperable for maintenance and/or repair.In addition, as the result of a personnel error, most of the AHU's were inoperable for a period of about four days at the end of July;however, it has been concluded that the inoperability of the AHU's did not significantly contribute to the frost and ice formation experienced; 2)during the Unit shutdown immediately preceding this surveillance, it was discovered that a secondary side steam leak had occurred inside containment, possibly'affecting the humidity in the ice condenser; however, it has been concluded that the steam leakage did not significantly contribute to the frost and ice formation experienced, as the formation was very similar to that experienced in the past (the only apparent effect of the steam leak on the ice condenser was minor amountsof frost/ice formation on the intermediate deck doors).With the exception of the AHU's, there were no inoperable structures, components or systems that contributed to this event.Cause of Event It is believed that sublimation of ice or high humidity in the containment air could have contributed to this problem.Further investigation of this event.is ongoing.Anal sis of Event The Westinghouse evaluation indicated that latti'ce frost/ice formation of up to 20 percent of the total flow passage area could be present without the peak Ice Condenser Compartment Pressure exceeding the design limit.Since the frost/ice buildup identified in Bays 1, 2, 3, 4, 6, 8, 12, 14 and 15 constitute a total flow blockage area which is less than 20 percent limit, this situation is bounded by the Westinghouse evaluation.
Our evaluation indicates that the amount of flow blockage due to frost and ice buildup noted in the Iee Condenser can be tolerated without adversely affecting the Ice Condenser function during a Loss of Coolant Accident.Based on the above information and the Westinghouse evaluation, it is concluded that the abnormal degradation event does not constitute an unreviewed safety question as defined in 10CFR50.59(a)(2), nor does it adversely impact health and safety.Though-our evaluation has concluded that the degradation is not serious, we believe issuance of this voluntary LER is appropriate since some degradation has been identified.
NRC FORM SSBA (94)3)*U.S.GPO:1086.0.624 538/455 NRC Form 35EA (983)LICENSEE ENT REPORT (LER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150-0(94 EXPIRES: 8/31/88 ACIUTY NAME ul DOCKET NUMBER (3)YEAR I.ER NUMBER (5)SEOUENTIAI.
Pc%<NUMBER 4'EV/SION NUMBER PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///'/m//s g>>ce/4/q/o///w/, I/FEE///////dna/HRC Form 35543/(17)0 5 0 0 0 3]5 8 00 7--0 0 0 4 1 5 Corrective Actions The corrective action was to manually clean the flow passages to remove the accessible frost and ice buildup.The results of Technical Specification Surveillances regarding frost and ice that forms in the flow passages is being monitored to ensure that any adverse trends in the amount of ice and frost buildup between surveillances will be identified.
The impact of frost and ice buildup in the flow passages is also being studied in conjunction with the other utilities with ice condenser containments.
Failed Com onent Identification No component failures were identified during this event.Previous Similar Events LER 50-316/85-013 LER 50-316/87-002 LER 50-315/87-013 LER 50-316/87-010 LER 50-315/88-002 LER 50-316/88-005 NRC FOAM SSEA ($83)*U.S.GPO:)988.0-834 538/455 NRC Fono 388A ($83)LICENSE ENT REPORT ILER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3150-0104 EXPIRES: 8/31/(8 FACIUTY NAME (1)COCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL.Njb'UMBER REVISION NUMBER PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT/PIIRBB Rpoco/t Beta)BI/, Boo////Ooo///RC Fontt 36843/(17)0 5 0 0 0 3]5 8 8 0 0 7-0 0 0 5 OF 1 5 ATTACHMENT 1 Description of Flow Passage Blockage by Category (affected Flow Passages are indicated by the boxed areas on the following attachments).
~Cate or A Maximum Flow Passage Ice/Frost Blockage greater than 75 percent.Maximum Flow Passage Ice/Frost Blockage between 50 and 75 percent.Maximum Flow Passage Ice/Frost Blockage between 25 and 50 percent.D Maximum Flow Passage Ice/Frost Blockage less than 25 percent (but greater than 3/8" buildup).*NOTE: These are generalized categories which reflect the maximum.ice/frost blockage found in a particular flow passage and in general was limited to one or two lattic'e frameworks in the flow passage.This does not indicate that the flow passage was blocked its entire length.Lattice Framework is located at the positions'of cruciforms in the ice basket.Cruciforms are installed every six feet within the 48 foot ice basket (for convention the"top" lattice framework is referred to as number 1, etc.).The specific lattice frameworks affected are indicated on the individual Bay drawings (Attachments 3-11).NRC FORM BBBA (94)31*U.S.GPO:1988.0.824 538/455 NRC Form 388A (983)~LICENSEE ENT REPORT (LER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1)COCKET NUMBER (1)YEAR LER NUMBER (8)SEQUENTIAL NUMBER REVISION NVM BR PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//P neo BPdcd b/IO/ror/rrro dr/d/I/ooo/NRC Forrrr 3854'c/(17)0 5 0 0 0 3 1 5 8 0 0 7 0 0 0 6 OF 1 5 ATTACHMENT 2 Representative Diagram of Ice/Frost Buildup in Two Flow Passages Technical Specification nominal thickness (3/8 inch)Lattice Framework Scale: 1/2 inch equals 1 inch NRC FORM SBBA (94)3)o U.S.GPO.'1986.0.624 538/455 NRC Form 366A ($83),, LICENSEE ENT REPORT (LER)TEXT CONTIN ION US.NUCLEAR REOULATORY COMMISSION APPROVED OMS NO.3150-0104 EXPIRES: 8/3)/88 FACILITY NAME (Il D.C.Cook Nuclear Plant-Unit 1 DOCKET NUMBER (2)o.s o o o 3 1 5 YEAR 8 8 LER NUMSER (6)$8/~SEOUENTIAL Ni<)NUMSER 0 0 7 REVISION NUMBER 0 0 PACE (3)0 7 oF 1 5 TEXT//P R>>m<<>>ce/8 mqUPEc/II48~HRC%%dmI 38543/(17)ATTACHMENT 3 Bay 1 (of 24 total)Azimuthal Row (Basket)C(7)Radial 5 Row (Row)Note: The lattice frameworks affected are indicated in parenthesis after the catepory description number (see Attachment 1).NRC FORM 366A (84)3)~.~*U 8 QPO 1988 0 824 538/455 NRC Form 3BSA (943)i LICENSE ENT REPORT (LER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3150-OIOi EXPIRES: 9/31/SS FACIUTY NAME (1)OOCKET NUMBER (2)YEAR LER NUMBER (9)SEQUENTIAL NUMBER 0?N'EVISION NUMBER PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//Frrxro<<>>co/F r)q/rorL I/ro////Or>>/NRC Forrn36//49/(17) o s o o o 3 1 5 8 8 0 0 7 0 0 0 8 QF 1 5 ATTACHMENT 4 Bay 2 (of 24 total)Azimuthal Row (Basket)6 7 D(8)Radial 5.Row (Row)D(3)8 Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 3OOA (943).*U.S.GPO:19BB.O 624 BSJVABS NRC Form 3SSA (94)3)'ICENSEE EVENT REPORT (LER)TEXT.CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3159WI04 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (5)SEQUENTIAL QXj NVMBBR".N REVISION NVMBBII PACE (3)D.C.Coo'k Nuclear Plant-Unit 1 TEXT//F moro<<Poco/4/4//rkorL Ir<<B S/S/ooo/kRC Fomr 35843/(17)0 5 0 0 0 3]8 8-0 0 7 0 0 0 9 OF 1 5 ATTACHMENT 5 Bay 3 (of 24 total)Azimuthal Row (Basket)C(2 and 3)1 2'(2 and 3): 5 6 2 Radial Row (Row)D(3)Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FOAM SBBA (94)3)<<U.S.GPO:1988.0 824 538/455 NRC FFNR 388A ($83)LICENSEE EVENT REPORT (LER1 TEXT CONTINU ION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-010S EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (8)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///mao<<>>co/s rsqo)orL l>>F~NRC Form 38843/(17)YEAR, g@o s o o o 31588 SEOUENTIAL NUMSSR 0 0 7 gp" REvrsloN-0 0 1 OoF 1 5 ATTACHMENT 6'BAY 4 (OF 24 TOTAL)Azimuthal Row (Basket)5 6 Radial'Row (Row)D(3)D(3 Note: The lattice frameworks affected are indicated in parenthsis after the category description number (see Attachment 1).NRC FORM SSSA (9<<3)*U,B.GPO;1988 0 824 838/48$
RC Form 366A" ($4)3)LICENSEE ENT REPORT (LER)TEXT CONTIN ON U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150-0)04 EXPIRES: 8/3)/88 FACILITY NAME tl)DOCK ET NUM 8 E R (2)LER NUMSER (6)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///mac 4FSSF/4 F6I4)Sat, IIFF aSSSWone//YRC
%%dmI 35549/(17)0 5 0 0 0 3 1 5 YEAR 8 8 SEOVSNTIAL kW'EVISION
'VMSSR:IPS NUMBER 0 0 7-0 0 1 1 OF 1 5 ATTACHMENT 7 Bay 6 (of 24 total)Azimuthal Row (Basket)Radial 5 Row (Row)D(3)Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 366A (94)3)*U.S.GPO:I 986 0-624 538/455' NRC FONB 300A (BB3)>LICENSEE VENT REPORT ILER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3180M)04 EXPIRES: 8/31/88 FACIUTY NAME (1)DOCKET NUMBER (2)LER NUMBER (8)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TACT/4/Ieee g>>ce/4 Ieqekaf, I>>e//8/0/>>/NRC Fo/In SSBAB/((7)o s o o o3 15 YEAR gg 8 8 SEQUENTIAI NUMBER%Cr 0 0 7 REV IS ION NUMBER 0 0 1 2 QF I.5 ATTACHMENT 8 Bay 8 (of 24 total)Azimuthal Row (Basket)Radial Row (Row)\I I D(3)Note: The.1'attice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 300A ($43)*U.S.GPO:1088.0.024 538/45S NRC~388A (94)3)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3150-OI04 EXPIRES: 8/31/BS FACILITY NAME (1)OOCKET NUMBER (2)YEAR LER NUMBER (8)SEOVENT/AL NVMBER').N0 REVIS lON NVMSER PAGE I3)D.C.Cook Nuclear Plant-Unit 1 TEXT/P//N/tu 4pecu/4/FEVEud, u44//I/FR4/HRC Form 35543/(IT)o s o o o 3 1 5 8 8 0 0 7 0 0 1 3 OF ATTACHMENT 9 Bay 12 (of"24 total)Azimuthal Row (Basket)A 7)Radial 5 Row (Row)I I I 7'ote: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 388A (94)3)*U,S.GPO:1988 0 624 538/455 RC Form 366A (983)LICENSEE ENT REPORT (LER)TEXT CONTINU ION US.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO..'3)EO-0104 EXPIRES: 8/31/88 FACILITY NAME (Il DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//F rrrors 4/roro/4 t/r//roo L oro 44I/one/NRC
%%dnn 35549)(IT)o s o o o 3 1 5 YEAR@P 8 8 SSOUSNTIAL NUMSSR 0 0 7 REVOION'>:55vr NUMSSR 0 0 1 4 OF 1 5 ATTACHMENT 10 Bay 14 (of 24 total)Azimuthal Row (Basket)4 5 Radial 5 Row (Row)8 D(2)Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 366A (943)*U.S.GPO:1955.0 524 4638/455 NRC Form 368A (943)~LICENSEE VENT REPORT (LER)TEXT CONTIN TION US.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3150-01(M EXPIRES: 8/31/85 FACIUTY NAME l1)OOCKET NUMBER 12)YEAR LER NUMBER (6)SBOUENTIAL NUMBBR REVISION NUMBBR PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//FmBm BPBBB lI BqIA)BI/, IIFF 9//dBBB/HRC
%%dmI 35549/l)T)os000315 8 8 0 0 7 0 0 1 5 QF 1 5 ATTACHMENT ll Bay 15 (of 24 total)Azimuthal Row (Basket)D(2)1 Radial 5 Row (Row)6 Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM SBBA (943)*U.S.GPO:(988 0 624 538/455 Indiana Michlga Power Company Cook Nuclear Plant P.O.Box 458 Bridgman.Ml 49106 616 465 5901 Z MAMBA MCHJGQH PQ'uV22 September 30, 1988 United States Nuclear Regulatory'ommission Document Control Desk Washington, D.C.20555 Operating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:
88-007-00 Sincerely, W.G.Smith, Jr.Plant Manager WGS:clw Attachment cc: D.H.Williams, Jr.A.B.Davis, Region III M.P.Alexich P.A.Barrett J.E.Borggren R.F.Eroeger NRC Resident Inspector J.F.Stang, NRC.R.C.Callen G.Charnoff, Esp.-Dottie Sherman, ANI Library D.Hahn INPO PNSRC A.A.Blind S.J..Brewer/B.P.Lauzau