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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
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
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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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INDIANA & MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 September 18, 1986 AEP:NRC:0971A 10 CFR 21:0058 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 DEFECTIVE EMERGENCY HEAD LEVER SUPPLIED FOR AUXILIARY FEED PUMP Mr. James Taylor, Director Office of Inspection a:id Enforcement U.S. Nuclear Regulatory Commission 1717 H Street Washington, D.C. 20555
Dear Mr. Taylor:
This letter is to confirm the telephone conversation of September 12, 1986 vetween Messrs. J. Feinstein, G. Hines, and P. Barrett of American Electric Power Service Corporation and Mr. George Lanik of the Office of Inspection and Enforcement, regarding notification made pursuant to 10 CFR Part 21. Mr. Lanik stated that submission of this letter by September 18, 1986 was acceptable. Based on our safety evaluation of September 12, 1986, we concluded that the subject defect had the potential for causing a substantial safety hazard.
Specifically, we reported that we had received parts for our auxiliary feedwater pump turbines which contained a defect. The parts were two emergency head levers (Part #82262B, Drawing #86205D) supplied by Terry Corporation of Windsor, Connecticut. The levers were improperly machined such that the surface whien seats against the tappet nut was curved instead of being flat.
The defective parts (levers) were never actually insralled in the D. C.
Cook Plant. Thus, there was no adverse safety impact caused by these defective parts on D. C. Cook Plant. With the turbine's mechanical overspeed trip reset, the defective levers could have caused the operating pump to inadvertently trip. This would have prevented a continuous supply of auxiliary feedwater from the Turbine Driven feedwater pump to the plant steam generators in the event it was required.
The defective parts were returned to the manufacturer. Nondefective replacement parts were sent to the D. C. Cook Plant and installed.
We do not have specific knowledge of whether or not defective parts of this type have been supplied to other utilities.
8609230228 860918 CE(pl$
PDR ADOCK 05000315 S PDR I O
/
Mr. Jr.mes Tsylcr AEP:NRC 0971A This document has been prepared following Corporate procedures which incorporate a reasonable. set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very trul your ,
M. P. .exich (t Vice resident cm cc: John E. Dolan W. G. Smith, Jr. -' Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman i
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