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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17334B8201998-06-23023 June 1998
Part 21 Rept Re Defective & Missing Welds Found on Ice Basket Bottom Cross Bar & Bottom Basket Grids During Insp of Unit 1 Ice Condenser.Investigation Ongoing.Defective Ice Basket Bottom Rims Will Be Repaired or Replaced
ML20217K5191997-10-24024 October 1997
Part 21 Rept Re Five Valves That May Have Defect Related to Possible Crack within Forging Wall at Die Flash Line.Caused by Less than Optimal Forging Temperatures.Newer Temperature Monitoring Devices at Forging Area Heating Ovens Procured
ML17333A8651997-04-22022 April 1997
Part 21 Rept Re Defective Double Pole Torque Switch.Caused by Missing Spacer.Limitorque Instituted Addl Insp Check of Double Pole Torque Switches During Assembly & Licensees Must Review All Installed & in-stock Torque Switches
ML17333A8441997-04-0909 April 1997
Part 21 Rept Re Limitorque Torque Assembly Used in SMB-00 Valve Actuators That Were Missing Spacer.Replaced or Repaired Defective Assemblies by Addition of Spacer
ML17333A9041997-03-19019 March 1997
Part 21 Rept Re Spacer Missing from Torque Switch Assembly for MOV 2-MMO-421 Which Allows Torque Switch Shaft to Rotate Slightly Along Length of Shaft.Defective Assemblies Replaced or Repaired by Addition of Spacer
ML17333A8161997-03-19019 March 1997
Part 21 Rept Re Missing Spacers from Standard SMB-00 Torque Switch Assemblies.Caused by Defective Lot Received from Limitorque Facility.Replaced or Repaired Defective Assemblies by Addition of Spacer
ML20059F2631994-01-0707 January 1994
Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical
ML20035E4861993-04-0707 April 1993
Part 21 Rept Re K-400 Circuit Breaker Failed to Meet Certain Rating Requirements Based on ANSI C37.16.Licensees Scheduled Tests on Modified Arc Chutes in Several Different Modes at KEMA-Powertest Lab in Chalfont,Pa
ML20126J5961992-12-31031 December 1992
Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl
ML20126F8081992-12-22022 December 1992
Part 21 Rept Re Possible Condition of Gag Plug in Cap of Valves That Cause Valves Not to Lift to Requirement for Providing Full Capacity.Affected Customers Notified.Removal of Caps &/Or Gag Plugs Recommended
ML20127P5861992-11-23023 November 1992
Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl
ML13316A0821991-11-15015 November 1991
Part 21 Rept Re Incorrect transmitter-to-bracket Mounting Socket Cap Screws.Cap Screws May Fail Under Seismic Dynamic Tensile & Shear Loads.Ltr Sent to Customers Encl. Weed Instrument Co Notified on 911108
NRC-90-3481, Part 21 Rept Re Westinghouse Class 1E Thermal/Magnetic molded-case Circuit Breakers Tripping During Attempts to Start Motor.Initially Reported on 900105.Vendor Requesting That Utils Verify Proper Breaker Performance1990-01-0909 January 1990
Part 21 Rept Re Westinghouse Class 1E Thermal/Magnetic molded-case Circuit Breakers Tripping During Attempts to Start Motor.Initially Reported on 900105.Vendor Requesting That Utils Verify Proper Breaker Performance
ML17328A2281989-12-12012 December 1989
Followup Part 21 Rept Re Westinghouse molded-case Circuit Breakers Observed to Trip Before Allowable Time Band,Per Generic Ltr 88-10.Initially Reported on 891207.Breakers Purchased Prior to 1989 Purchase Order Not Subj to Problems
ML17326B6001989-04-10010 April 1989
Part 21 Rept Re Level III Examiner Personnel Not Certified Per ANSI N45.2.6-1978.Initially Reported on 890406.Stop Work Order Issued to Prevent Addl Insps from Being Performed by Unqualified Personnel & Qualification Procedure Revised
ML17326B5501989-03-0303 March 1989
Followup Part 21 Rept Re Failures of Closing Mechanisms in Two Bbc Brown Boveri,Inc,Type 5HJK250 Circuit Breakers Installed in Safety Sys at Plant.Initially Reported on 890301.Maint Procedure Will Be Revised
ML13316A0321988-12-22022 December 1988
Part 21 Rept Re Spot Welds on DB-50 Reactor Trip Breaker Secondary Contact Bracket Observed to Be Separated.Initially Reported on 881213.Utils Have Been Advised That Secondary Contact Bracket May Be Modified by Drilling Holes in Welds
ML17326B3661988-04-0404 April 1988
Part 21 Rept Re Environ Qualification of Torque Switches Designed by Limitorque Corp.Initially Reported on 880330. Design Not Qualification Tested for Nuclear safety-related Svc.Untested Torque Switches Will Be Replaced
ML17325A2691987-08-26026 August 1987
Part 21 Rept Re Metallic Beads Discovered in Reliance Electric Co motor-operated Valves Installed on Limitorque SMB-000 Valve Operators.Initially Reported on 870821.Caused by Abrasive Cleaning Process.Limitorque Refurbished Motors
ML17334B1331987-08-26026 August 1987
Part 21 Rept Re Defective Torque Switches for in Valve Motor Operator Supplied to Plant by Limitorque Corp. Initially Reported on 870821.Caused by Inadequate Design of Double Torque Switch.Defective Switches Replaced
ML17325A2331987-07-31031 July 1987
Part 21 Rept Re Corrosion on Leads to Transformers Supplied by Brown Boveri Corp.Initially Reported on 870727.Corrosion Sufficient to Create Safety Hazard Had Transformers Been Installed W/O Repair.Brown Boveri Corp Encl
ML20203N2351986-09-18018 September 1986
Part 21 Rept Re Defective Terry Corp Emergency Head Lever Supplied for Auxiliary Feed Pump.Defective Parts Never Installed in Facility & Returned to Mfg.Replacement Parts Installed
ML20210F4741986-09-16016 September 1986
Part 21 Rept Re Possible Sticking in Closed or Partially Open Position on Dresser 3050 Diaphragm Valves.Initially Reported on 850118.Disc Caps,Including Chamfers on Outside Diameter,Will Be Modified
ML20206S0841986-06-30030 June 1986
Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires
NRC-86-3095, Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified1986-01-0909 January 1986
Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified
ML20136H0721985-12-20020 December 1985
Part 21 Rept Re Supply of Weld Electrodes W/Incomplete Flux Coating.Initially Reported on 851217.NDE Records & Welder Interviews Revealed Rods Not Used in Facility.No Safety Hazard Identified.Details Encl
ML20100B7201985-03-22022 March 1985
Part 21 Rept Re Error in TOODEE2 Code Used in LOCA-ECCS Analysis for DC Cook Unit 1.Initially Reported on 850315. Analysis Affected by Coding Error Reperformed Using Corrected Version of TOODEE2
ML20094H9341984-08-0303 August 1984
Part 21 Rept Per 840720 Request Re Effects of Superheated Steam Following Postulated Main Steam Line Break.Util Will Participate in Westinghouse Owners Group Activities & Involvement Expected to Suppl Internal Review
ML20092D9711984-06-15015 June 1984
Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified
ML20091K6911984-05-25025 May 1984
Part 21 Rept Re Programming Error in Detector Code,Supplied by Shanstrom Nuclear Assoc,Inc.Initially Reported on 840523. Software Enhanced.Nmfm Procedure 7 Will Be Revised by 841231.LER Will Be Submitted
ML20091G2071984-05-24024 May 1984
Part 21 Rept Re Bug in Detector Computer Code Resulting in Possible Miscalculation of Tech Spec Parameters for Enthalpy Rise Peaking Factor.Problem Corrected & Responsible Parties Notified
ML20092P6691984-05-24024 May 1984
Potential Part 21 Rept Re Bug in Detector Computer Code for in-core Detectors.Bug Incorrectly Calculated Enthalpy Rise Peaking Factor.Bug Corrected
ML20085K7291983-10-14014 October 1983
Interim Deficiency Rept Re Calibr Technique for Temp Compensation on Barton Transmitters.Westinghouse Part 21 Rept Described Undefined Errors at Abnormal & Accident Temps.Next Rept in 14 Days
ML20072N9891983-07-0808 July 1983
Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl
ML20070C7631982-12-10010 December 1982
Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested
ML20039D5181981-12-21021 December 1981
Part 21 Rept Re Design Defect on Micro Computer Printed Circuit Board of Micro computer-based Radiation Monitoring Sys.Vendor Will Supply Board W/Latch Which Prevents Interrupt Data from Changing While Being Read
ML17326A8531981-02-27027 February 1981
Final Deficiency Rept Re Possible Svc Water Leak in Ventilation Unit of Lower Vol Containment,Initially Reported 810220.Drip Pan Pipe Had Become Plugged.Drip Pan Overflowed. No Leak Exists.Requests Notification of Withdrawal
1998-06-23
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEAR05000315/LER-1999-024, :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.With1999-10-18018 October 1999
- 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
05000315/LER-1999-023, :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 & Implemented1999-10-0707 October 1999
- 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
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With
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)
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios
05000315/LER-1999-022, :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 Necessary1999-09-17017 September 1999
- 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
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With
05000315/LER-1999-021, :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 Developed1999-08-27027 August 1999
- 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
05000315/LER-1999-020, :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 ACs1999-08-26026 August 1999
- 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
05000315/LER-1999-019, :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 1-41999-08-16016 August 1999
- 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
ML17326A0801999-08-0909 August 1999
Safety Evaluation Accepting Licensee Request for Approval Under Provisions of 10CFR50.55a(a)(3),to Use ASME B&PV Code,Section Ix,Code Cases 2142-1 & 2143-1 for Fabrication & Installation of Unit 1 Replacement SG Lower Assemblies
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
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With
05000315/LER-1999-018, :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 Valves1999-07-29029 July 1999
- 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
05000315/LER-1999-017, :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.With1999-07-26026 July 1999
- 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
05000315/LER-1999-016, :on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With1999-07-13013 July 1999
- on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With
05000315/LER-1999-004, :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 Written1999-07-0101 July 1999
- 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
05000315/LER-1999-015, :on 990408,RM Sys Was Not Tested IAW TS Srs. Caused by Inadequate Implementation of TS SRs in Plant Surveillance Procedures.Channel Functional Testing of RM Sys Unit Vent Effluent RMs Was Successfully Completed1999-07-0101 July 1999
- on 990408,RM Sys Was Not Tested IAW TS Srs. Caused by Inadequate Implementation of TS SRs in Plant Surveillance Procedures.Channel Functional Testing of RM Sys Unit Vent Effluent RMs Was Successfully Completed
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With
05000315/LER-1999-014, :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 Modified1999-06-18018 June 1999
- 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
05000315/LER-1999-013, :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 Developed1999-06-0101 June 1999
- 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
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With
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
05000315/LER-1998-037, :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 Made1999-05-24024 May 1999
- 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
05000316/LER-1998-004-01, :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 Made1999-05-24024 May 1999
- 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
05000315/LER-1999-012, :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 Developed1999-05-20020 May 1999
- 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
05000316/LER-1999-002-01, :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 Revised1999-05-10010 May 1999
- 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
05000315/LER-1999-011, :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 Prepared1999-05-0404 May 1999
- 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
05000315/LER-1999-010, :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 Design1999-05-0303 May 1999
- 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
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With
05000315/LER-1999-006, :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 Hold1999-04-16016 April 1999
- 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
05000315/LER-1999-009, :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 Investigation1999-04-12012 April 1999
- 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
05000315/LER-1999-008, :on 990115,plant Operators Reported Excessive Piping Vibration in RHR Rooms.Cause Unknown.Update to LER Will Be Submitted1999-04-0909 April 1999
- on 990115,plant Operators Reported Excessive Piping Vibration in RHR Rooms.Cause Unknown.Update to LER Will Be Submitted
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
05000315/LER-1999-007, :on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures1999-04-0101 April 1999
- 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
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With
05000316/LER-1999-001, :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 Ongoing1999-03-29029 March 1999
- 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
05000315/LER-1999-005, :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 Developed1999-03-18018 March 1999
- 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
ML17325B5171999-03-15015 March 1999
1999 Financial Assurance Requirements Rept for Decommissioning Nuclear Power Reactors
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
1999-09-30
[Table view] |
Text
RATED31BUTIONDEMONSTRONSYSTEMREGULATOR~NFORMATIONDISTRIBUTIONTEM(RIDS)4ACCESSIONNBR:8912200198DOC.DATE:89/12/12NOTARIZED:NODOCKETFACIL:50-315DonaldC.-CookNuclearPowerPlant,Unit1,Indiana60500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana605000316AUTH.NAMEAUTHORAFFILIATIONALEXICH,M.P.IndianaMichiganPowerCo.(formerlyIndiana6MichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)
SUBJECT:
Part21reptremoldedcasecircuitbreakersthattrippedbeforeallowabletime.'IDISTRIBUTIONCODE:IE19DCOPIESRECEIVED:LTRENCLSIZE:TITLE:Part21Rept(50DKT)NOTES:ID(RECIPIENTIDCODE/NAMEPD3-1LAGIITTERgJ.INTERNAL:AEOD/DOAIRMTECHADVNRRVARGAiSNRR/DOEA/OGCB11N-8E2EGFIL01RRGN3RGN5EXTERNAL:INPORECORDCTRNRCPDRCOPIESLTTRENCL10111111111111111111111111RECIPIENTIDCODE/NAMEPD3-1PDAEOD/DSP/TPABNRRCRUTCHFIELDNRR/DLPQ/LPEB10NRR/DRIS/RVIB9DNUDOCS-ABSTRACTRES/DSIR/EIBRGN2RGN4LPDRNSICSILVER,ECOPIESLTTRENCL111'11111111111111l.1111hhTOTALNUMBEROFCOPIESREQUIRED:LTTR24ENCL23
~'~0IIIl,Pw IndianaMichiganPowerCompanyP.O.Box16631Columbus,OH43216RAEP:NRC:0971G10CFR21.21DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-7410CFR21REPORT:WESTINGHOUSEFB3125LMOLDED-CASECIRCUITBREAKERSU.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyDecember12,1989
DearDr.Murley:
Introduction(10CFR21.21(b)(3)(i),(ii)and(iii))Thisletterconstitutesafollow-upreport,asrequiredby10CFR21.21,ofinformationprovidedtoyourstaffviatelephoneonDecember7,1989.ThisreportisbeingsubmittedbyIndianaMichiganPowerCompany,P.0.Box16631,Columbus,Ohio43216.The10CFR21reportconcernsWestinghouseFB3125L(125-amp)molded-casecircuitbreakers,whichhavebeenobservedtotripbeforetheallowabletimebandgiventhetime-currentcharacteristicscurveforthisbreaker.ThesubjectcircuitbreakerswerepurchasedfromWestinghousein1989toreplacenon-traceablecircuitbreakersidentifiedinourreviewperNRCBulletinNo.88-10,"NonconformingMolded-CaseCircuitBreakers."TherearefiveoftheseFB3125Lcircuitbreakersinstalledinsafety-relatedapplicationsattheDonaldC.CookNuclearPlant.A125-ampcircuitbreakerfeedingturbineroomsumppump¹2failedduetoalooseconnection.ThefailedcircuitbreakerwasreplacedwithanFB3125Lcircuitbreakerfromstock.Thenewcircuitbreakerwouldnotholdonstartingofthesumppump.Twomorebreakersweredrawnfromstockandsubsequentlyfailedtoholdonstartingofthesumppump.Allthreeofthecircuitbreakersthatwouldnotholdonstartingofthesumppumpwerepurchasedundertheabove1989Westinghousepurchaseorder.Finally,the125-aropcircuitbreakerfeedingturbineroomsumppump¹3wasexchangedwiththecircuitbreakerinstalledinthecircuitforsumppump¹2.Afterexchange,thecircuitbreakerfeedingsump8~ia00iWSBei2i2PDRADQCI(05000315SPNU
~~C~E Dr.T.E.Murley-2-AEP:NRC:0971Gpump¹2heldonstartingandthepumpwasreturnedtoserviceaftersatisfactorytesting.Thecircuitbreakernowfeedingsumppump¹3wouldnotholdonstarting,ashadoccurredduringtestingwiththecircuitbreakerfeedingsumppump¹2.AfterthreeFB3125Lcircuitbreakerstrippedwhilestartingaturbineroomsumppump,twoofthethreecircuitbreakerswerebenchtestedatCookNuclearPlant.BenchtestingoverarangeofinputcurrentsledustoconcludethatbothcircuitbreakersweretrippingbeforethetimespangivenbytheWestinghousetime-currentcharacteristicscurveforthiscircuitbreaker.InordertodeterminewhethertheaboveproblemwasgenerictoallWestinghousecircuitbreakerspurchasedwiththe1989purchaseorder,asampleofcircuitbreakers,includingavarietyofcurrentratings,wastestedatCookNuclearPlant.Thisin-housetestingindicatedthattheFB3090L(90-amp)circuitbreakerswerealsotrippingbeforetheirallowabletimeband.Sincefieldtestingisnotconsideredanaccuratemeasurefordeterminingthetime-currentcharacteristics(perNEMAstandards),thecircuitbreakerswerereturnedtoWestinghouseforverificationofourtestresults.OnDecember5,1989,twoFB3125LandtwoFB3090Lcircuitbreakersweretestedbythecircuitbreakermanufacturerattheirfacilities.Thistestingledtotheconclusionthat:1)TheFB3090L(90-amp)circuitbreakerswereperformingsatisfactorily.2)TheFB3125L(125-amp)circuitbreakersweretrippingearlierthanthetimebandgivenbytheWestinghousetime-currentcharacteristicscurveforthisbreaker.OnDecember6,1989,theresultsofWestinghousecircuitbreakertestingwasreviewedandtheconditionwasdeterminedtobereportableper10CFR21.TheattachmenttothislettershowstheobservedtrippingtimesforthetwoFB3125LcircuitbreakersduringWestinghousetesting.Thedatashowthatthecircuitbreakerstrippedbeforetheallowabletimebandintherangeof400tto500%ofratedcurrent.Wecanpostulatetwosafetyhazardsthatcouldbecreatedbytheaboveproblem:1)Thecircuitbreakercouldtriponstartingofasafety-relatedload,precludingtheaccomplishmentofasafetyfunction.2)Breakercoordinationmaybelostforcertainfaultcurrents.
Dr.T.E.Murley-3-AEP:NRC:0971GDiscussion(10CFR21,21(b)(3)(vi)and(vii))TherearefiveFB3125Lcircuitbreakersfromthe1989Westinghousepurchaseorderinstalledinsafety-relatedapplicationsatCookNuclearPlant.Inallcases,theloadsfedbythebreakerarebalanceofplant(BOP).Sincethebalanceofplantloadsarefedfromsafety-relatedelectricalbuses,thesafetyfunctionofthebreakeristoprotectthebusfromfaultsontheBOPloads.Therefore,trippingearlyisnot,asafetyconcernatCookNuclearPlant.Furthermore,thefiveinstalledcircuitbreakershavenottrippedwhileenergizingtheirattendantloads.Specifically,theFB3125Lcircuitbreakersareinstalledinthefollowingapplications:Unit~sseemExhaustfanforauxiliarybuildingventilationControlaircompressorAuxiliary]acketwaterheaterforCDdieselgeneratorExhaustfanforauxiliarybuildingventilationFreezeprotectionheaterforrefuelingwaterstoragetankWestinghouseFB3125LcircuitbreakersbeingmaintainedasstoredsparesatCookNuclearPlanthavebeenplacedon"temporaryhold."WearepursuingresolutionoftheproblemwithWestinghouse.Conclusion(10CFR21.21(b)(3)(viii))WestinghouseFB3125Lcircuitbreakershavebeendemonstratedtotripbeforethetimebandgivenbythetime-currentcharacteristicscurveinthe400-500%ratedcurrentregion.Therefore,ifthisbreakerisusedtofeedamotorwithastartingcurrentinthisregion,theproblem-describedinthis10CFR21reportmaybeencountered.WebelievethatWestinghouseisplanningtoissuesomeformofpublicationtonotifyapplicablelicenseesofWestinghousefindingsandrecommendationsregardingtheconcernaddressedbythis10CFR21report.Todate,wehavenoreasontosuspectthatWestinghouseFB3125Lcircuitbreakerspurchasedpriortoour1989purchaseorderaresub]ecttotheproblemdescribedinthis10CFR21report.
Dr.T.E.Murley-4-AEP:NRC:0971GThisdocumenthasbeenpreparedfollowingCorporateproceduresthatincorporateareasonablesetofcontrolstoensureitsaccuracyandcompletenesspriortosignaturebytheundersigned,Sincerely,M,P.Alexi.VicePresidentMPA/ehAttachmentcc:D.H.Williams,Jr.A,A.Blind-BridgmanR,C.CallenG.CharnoffNFEMSectionChiefA.B.DavisNRCResidentInspector-Bridgman ATTACHMENTTOAEP:NRC:0971GTIME-CURRENTCHARACTERISTICSCURVESFORWESTINGHOUSEFB3125LCIRCUITBRF~ERSHOVINGTRIPPOINTSFORTWOCIRCUITBREAKERSTESTEDATWESTINGHOUSEFACILITIES
,I~rhApttl(cationData29-161Page14Yqr,,7eSVS'lI/)Tg,II/I'SII~Yr;tY:,I(J:0!IV0IOOO-xIOIOOCJ~000'/I000000CircuitBreakerTime/CurrentCurvesTypesEB.EHB,FB,HFBBreakers,TwoandThreePolesWestinghouseElectricCorporationForapplicationandcoordinationpurposesonly.Basedon40'Cambient,coldstart.Connectedwithfour(4)festofratedwire(60/75'Cupto100amps.75'Cabove100amps)perterminal.Testedinopenairwithcu~rentinallpoles.IMaximumVoltsBreakerAcVolts,DcType60HzMaximumMinimumABDE-iQNCircuitBreakers@~p+~~ehp~$ba~kqTypesEB,EHB:90-100Amperes,2and3PolesTypesFB,NIARK76TypeHFB:90.160Amperes,2and3PolesTe'HTCr'4/5/~CurrentInPercentofBreakerTripUnitRatingssrssiI)I$)IEBIIIiiilii)ss~00IMaximumSinglePoleTripTimesat25'CO~~EBEHBFB,HFB240480600125/250250250BreakerRatingsBreakerContinuousTypeAmperesInstantaneousTrip,AmperesEB,EHB90100SeeCurveFB,HFB90150SeeCurveInterruptingRating(ULListed)BreakerSymmetricalRMSAmperesDcAmps240Volts480Volts600Voits250VoltsEB10,000........5,000(125/250)EH818,00014,000...,.10,000.F818.00014.00014,00010,000HF865,00025,00018,00010.000O~Singlepoletestdataat25'CbasedonNEMAProceduresforverifyingperfor-manceofMoldedCaseCircuitBreakers.IIOK3~0O3OIcnJ~III~'~lhIQ.OI~I'aximumInterruptingTime,/rt.InterruptingRating(SeeTabulatioOlnAbove)Jg("Qx'bOIIi~~~0Yh~iloagkCa+&(&los00I~~s'I~~QOIIAIOStsass)Currentl>>IIII)(l>(IinPercentofBreakerTripUnitRatingCurveNo.SC351177December,1989 0til 0~\~ApplicationData29-16'tl'ge14p83)pztTerra~Jor(QABDE-IONCircuitBreakersgaCAM<8-7ht..~l7~+~IDOOOX~000~>0000CircuitBreakerTime/CurrentCurvesTypesEB,EHB,FB.HFBBreakers,TwoandThreePotesWestinghouseElectr)cCorporationa'lew1i~~0Forapplicationandcoordinationpurposesonly.Basedon40'Cambient.coldstart.Connectedwithfour(4)feetofratedwire(60175'Cupto100amps.75'Cabove100amps)perterminal.Testedinopenairwithcurrentinallpoles.iL~LTypesEB,EHB:90.100Amperas,2and3PolesTypesFB,MARK75TypeHFB:90-150Amperes,2and3PolesCurrentinPercentofBreakerTripUnitRatingsassaiII)())IBJIIiii)II)ls~)s~)'IIs/5/pqOJOAIOI~0x0000OCIID~0.MaximumMinimum'tIIr:I.J.IIW~~,il,MaximumSinglePoleTripTimesat25'C(l)MaximumVoltsBreakerAcVolts.Type60HtEB240EHB480FB,HFB600BreakerRatingsBreakerContinuousTypeAmperesEB,EHB90100FB,HFB90150Dc)25i250250250InstantaneousTrip.AmperesSeeCurve-SeeCurveDcAmps250Volts5,000(125250)10,00010.00010,000I~InterruptingRating(ULListedlBreakerSymmetricalRMSAmperes240Volts480Volts600VoltsEB10,000EH818,00014,000FB18,00014,00014,000HF865,00025,00018,000ISinglepoletestdataat25CbasedonNEMAProceduresforverifyingparlor.manesofMoldedCaseCircuitBreakersiOtniO00OaIOil~WIII~IIii...II0<<00Ol0~tI'~iMaximumInterruptingTimeIItInterruptingRatingISeeTabulationAbove)~~i~.ls01000Ii100I~000~~~1~~0<<ws<ssif~iai!)sr'ii>CurrentinPercentofBreakerTrip<<IX0~III)SilI(UnitRating~~~~JO0~I~~~~Iii~IQt)CC4,Q~-ID<<)iDDJOtDA.DgCurveNo.SC3511.77December,1988 0C1Jh
