Similar Documents at Cook |
---|
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 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 ML17325B3641990-01-0909 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 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 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 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 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 870526 Ltr 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 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 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 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 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
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
[Table view] |
Text
RATED 31 BUTION DEMONSTR ON SYSTEM REGULATOR~ NFORMATION DISTRIBUTION TEM (RIDS) 4 ACCESSION NBR:8912200198 DOC.DATE: 89/12/12 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.- Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Part 21 rept re molded case circuit breakers that tripped before allowable time.
'I I
DISTRIBUTION CODE: IE19D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Part 21 Rept (50 DKT) D (
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 1 1 h GIITTERgJ. 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 '1 IRM TECH ADV 1 1 NRR CRUTCHFIELD 1 1 NRR VARGAiS 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OGCB11 1 1 NRR/DRIS/RVIB9D 1 1 N - 8E2 1 1 NUDOCS-ABSTRACT 1 1 EG FIL 01 1 1 RES/DSIR/EIB 1 1 R 1 1 RGN2 1 1 RGN3 1 1 RGN4 1 l.
RGN5 1 1 EXTERNAL: INPO RECORD CTR 1 1 LPDR 1 1 NRC PDR 1 1 NSIC SILVER,E 1 1 h
TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 23
~ '~
0I II l,
Pw
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 R
AEP:NRC:0971G 10 CFR 21.21 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 10 CFR 21 REPORT: WESTINGHOUSE FB3125L MOLDED-CASE CIRCUIT BREAKERS U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley December 12, 1989
Dear Dr. Murley:
Introduction (10 CFR 21.21(b)(3)(i), (ii) and (iii))
This letter constitutes a follow-up report, as required by 10 CFR 21.21, of information provided to your staff via telephone on December 7, 1989. This report is being submitted by Indiana Michigan Power Company, P. 0. Box 16631, Columbus, Ohio 43216. The 10 CFR 21 report concerns Westinghouse FB3125L (125-amp) molded-case circuit breakers, which have been observed to trip before the allowable time band given the time-current characteristics curve for this breaker. The subject circuit breakers were purchased from Westinghouse in 1989 to replace non-traceable circuit breakers identified in our review per NRC Bulletin No. 88-10, "Nonconforming Molded-Case Circuit Breakers."
There are five of these FB3125L circuit breakers installed in safety-related applications at the Donald C. Cook Nuclear Plant.
A 125-amp circuit breaker feeding turbine room sump pump ¹2 failed due to a loose connection. The failed circuit breaker was replaced with an FB3125L circuit breaker from stock. The new circuit breaker would not hold on starting of the sump pump. Two more breakers were drawn from stock and subsequently failed to hold on starting of the sump pump.
All three of the circuit breakers that would not hold on starting of the sump pump were purchased under the above 1989 Westinghouse purchase order. Finally, the 125-arop circuit breaker feeding turbine room sump pump ¹3 was exchanged with the circuit breaker installed in the circuit for sump pump ¹2. After exchange, the circuit breaker feeding sump 8~i a00iWS Bei2i2 PDR ADQCI( 05000315 S PNU
~ ~
C ~
E
Dr. T. E. Murley AEP:NRC:0971G pump ¹2 held on starting and the pump was returned to service after satisfactory testing. The circuit breaker now feeding sump pump ¹3 would not hold on starting, as had occurred during testing with the circuit breaker feeding sump pump ¹2.
After three FB3125L circuit breakers tripped while starting a turbine room sump pump, two of the three circuit breakers were bench tested at Cook Nuclear Plant. Bench testing over a range of input currents led us to conclude that both circuit breakers were tripping before the time span given by the Westinghouse time-current characteristics curve for this circuit breaker.
In order to determine whether the above problem was generic to all Westinghouse circuit breakers purchased with the 1989 purchase order, a sample of circuit breakers, including a variety of current ratings, was tested at Cook Nuclear Plant. This in-house testing indicated that the FB3090L (90-amp) circuit breakers were also tripping before their allowable time band.
Since field testing is not considered an accurate measure for determining the time-current characteristics (per NEMA standards), the circuit breakers were returned to Westinghouse for verification of our test results. On December 5, 1989, two FB3125L and two FB3090L circuit breakers were tested by the circuit breaker manufacturer at their facilities. This testing led to the conclusion that:
- 1) The FB3090L (90-amp) circuit breakers were performing satisfactorily.
- 2) The FB3125L (125-amp) circuit breakers were tripping earlier than the time band given by the Westinghouse time-current characteristics curve for this breaker.
On December 6, 1989, the results of Westinghouse circuit breaker testing was reviewed and the condition was determined to be reportable per 10 CFR 21.
The attachment to this letter shows the observed tripping times for the two FB3125L circuit breakers during Westinghouse testing. The data show that the circuit breakers tripped before the allowable time band in the range of 400t to 500% of rated current.
We can postulate two safety hazards that could be created by the above problem:
- 1) The circuit breaker could trip on starting of a safety-related load, precluding the accomplishment of a safety function.
- 2) Breaker coordination may be lost for certain fault currents.
Dr. T. E. Murley AEP:NRC:0971G Discussion (10 CFR 21,21(b)(3)(vi) and (vii))
There are five FB3125L circuit breakers from the 1989 Westinghouse purchase order installed in safety-related applications at Cook Nuclear Plant. In all cases, the loads fed by the breaker are balance of plant (BOP). Since the balance of plant loads are fed from safety-related electrical buses, the safety function of the breaker is to protect the bus from faults on the BOP loads. Therefore, tripping early is not, a safety concern at Cook Nuclear Plant. Furthermore, the five installed circuit breakers have not tripped while energizing their attendant loads. Specifically, the FB3125L circuit breakers are installed in the following applications:
Unit ~sseem Exhaust fan for auxiliary building ventilation Control air compressor Auxiliary ]acket water heater for CD diesel generator Exhaust fan for auxiliary building ventilation Freeze protection heater for refueling water storage tank Westinghouse FB3125L circuit breakers being maintained as stored spares at Cook Nuclear Plant have been placed on "temporary hold." We are pursuing resolution of the problem with Westinghouse.
Conclusion (10 CFR 21.21(b)(3)(viii))
Westinghouse FB3125L circuit breakers have been demonstrated to trip before the time band given by the time-current characteristics curve in the 400-500% rated current region. Therefore, if this breaker is used to feed a motor with a starting current in this region, the problem-described in this 10 CFR 21 report may be encountered. We believe that Westinghouse is planning to issue some form of publication to notify applicable licensees of Westinghouse findings and recommendations regarding the concern addressed by this 10 CFR 21 report.
To date, we have no reason to suspect that Westinghouse FB3125L circuit breakers purchased prior to our 1989 purchase order are sub]ect to the problem described in this 10 CFR 21 report.
Dr. T. E. Murley AEP:NRC:0971G This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned, Sincerely, M, P. Alexi.
Vice President MPA/eh Attachment cc: D. H. Williams, Jr.
A, A. Blind - Bridgman R, C. Callen G. Charnoff NFEM Section Chief A. B. Davis NRC Resident Inspector - Bridgman
ATTACHMENT TO AEP:NRC: 0971G TIME-CURRENT CHARACTERISTICS CURVES FOR WESTINGHOUSE FB3125L CIRCUIT BRF~ER SHOVING TRIP POINTS FOR TWO CIRCUIT BREAKERS TESTED AT WESTINGHOUSE FACILITIES
, I~
rh Y
Yqr,, ,I Apttl(cation Data I/I'S II ~
29-161 r Page 14 AB DE-iQN Circuit Breakers @ ~p 7eSV S'lI /)T
+~~eh p~$ b g a~kq
- tY
- ,I(J:0!
Types EB, EHB: 90-100 Amperes, 2 and 3 Poles Types FB, NIARK 76 Type HFB: 90.160 Amperes, 2 and 3 Poles Current In Percent of Breaker Trip Unit Rating Te'H TCr '4/5/~
J ssrssi I )I $ ) IEBI I I i iilii) s s IV Circuit Breaker Time/Current Curves 0
'/ Types EB. EHB, FB, HFB Breakers, Two and Three Poles x
~ 000 IOOO I
Westinghouse Electric Corporation 00 0000 IOIO O C
For application and coordination purposes only. Based on 40'C ambient, cold start.
Connected with four (4) fest of rated wire (60/75'C up to 100 amps. 75'C above 100 amps) per terminal. Tested in open air with cu~rent in all poles.
I Maximum Maximum Volts Minimum Breaker Ac Volts, Dc Type 60 Hz EB 240 125/250 EHB 480 250 FB, HFB 600 250 Maximum Single
~
I 00 at 25'CO~ ~
Pole Trip Times Breaker Ratings Breaker Type Continuous Amperes Instantaneous Trip, Amperes IIO
~0 K
3 EB, EHB 90 100 See Curve O FB, HFB 90 150 See Curve Interrupting Rating (UL Listed)
Breaker Symmetrical RMS Amperes Dc Amps EB EH 8 10,000 18,000 240Volts 480Volts 600Voits 250Volts 14,000 5,000 (125/250) 10,000
. F8 18.000 14.000 14,000 10,000 HF8 65,000 25,000 18,000 10.000 O~ Single pole test data at 25'C based on NEMA Procedures for verifying perfor-mance of Molded Case Circuit Breakers. 3 O
I cn J ~
I~
' l I Q.
I I ~ h OI I 'aximum Interrupting Time
~
, /rt Ol
. Interrupting Rating (See Tabulatio n Above) Jg("Qx'b OI ~i loagkCa+ &(&los I i ~ ~ ~ 0 Yh I
00 I
~~
s
~ ~
Q OII A IOS l
t sass) > >
IIII)(l>(I Current in Percent of Breaker Trip Unit Rating Curve No. SC 3511 77 December, 1989
0 t
il
0 ~
\~
Application Data 29-16't l'ge 14 p8 3)pzt Terra~ Jor(Q AB DE-ION Circuit Breakers gaCAM< 8 - 7ht..~l 7~+~
Types EB, EHB: 90.100 Amperas, 2 and 3 Poles Types FB, MARK 75 Type HFB: 90-150 Amperes, 2 and 3 Poles Is/5/pq Current in Percent of Breaker Trip Unit Rating
'lew s~)'I s assai I I ) () )IBJ I I i i i)II) l s~
) OJ IDOOO OAIOI
~0 Circuit Breaker Time/Current Curves X Types EB, EHB, FB. HFB Breakers, Two
~ 000 and Three Potes
~>
Westinghouse Electr)c Corporation xO 0000 0000 C
a i
1
~ ~ 0 For application and coordination purposes only. Based on 40'C ambient. cold start.
Connected with four (4) feet of rated wire iL~ L (60175'C up to 100 amps. 75'C above 100 amps) per terminal. Tested in open air with current in all poles.
. Maximum Maximum Volts Minimum' Breaker Ac Volts. Dc Type 60 Ht EB 240 )25i250 EHB 480 250 FB, HFB 600 250
, Maximum Single Pole Trip Times Breaker Ratings at 25'C(l) Breaker Continuous Instantaneous Type Amperes Trip. Amperes t EB, EHB 90 100 See Curve II
.J. FB, HFB 90 150 -See Curve I IW ~ ~
Interrupting Rating (UL Listedl I
r: I ,il Breaker Symmetrical RMS Amperes 240Volts 480Volts 600Volts 250 Volts Dc Amps ID EB 10,000 5,000 (125 250)
EH 8 18,000 14,000 10,000 FB 18,000 14,000 14,000 10.000 HF 8 65,000 25,000 18,000 10,000 I Single pole test data at 25 C based on
~ 0 NEMA Procedures for verifying parlor.
manes of Molded Case Circuit Breakers iO tn iO 00 O
I ~ a IO il~ W I
i... <<
~
I II iI I
I 0 t I ' ~
i Maximum Interrupting Time 00 I It 01 Ol 0 ~ Interrupting Rating ISee Tabulation Above) 00
~ ~ i ~. l s
0 I Q t)CC4, i ~ i 00 I 1
~ -ID<<)i DDJOt DA. Dg
<<IX Q~
000 ~ ~ ~ ~ ~ ~ ~ JO0 0
1 ~ ~ 0 << ~ I ~ I ~ ~ ~ ~
II a
w s <ssif i! )sr'ii>
Current in Percent of Breaker Trip Unit Rating
) SilI(
i iI ~ I Curve No. SC 3511.77 December, 1988
0 C 1
J h