ML20063D921
ML20063D921 | |
Person / Time | |
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Site: | Fermi |
Issue date: | 08/18/1982 |
From: | Wells D DETROIT EDISON CO. |
To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
References | |
10CFR-050.55E, 10CFR-50.55E, EF2-59386, NUDOCS 8208300080 | |
Download: ML20063D921 (1) | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARNRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997
[Table view]Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected NRC-97-0005, Part 21 Rept Re 961113,EDG 11 Failed Surveillance Test 24.307.01 for LOP Coincident W/Loca.Avr Board Rev B Was Sent Offsite to an Independent Engineering Test Facility. CA Include More Analysis & Testing of AVR Board1997-02-0606 February 1997 Part 21 Rept Re 961113,EDG 11 Failed Surveillance Test 24.307.01 for LOP Coincident W/Loca.Avr Board Rev B Was Sent Offsite to an Independent Engineering Test Facility. CA Include More Analysis & Testing of AVR Board NRC-94-0072, Part 21 Rept Re Improper Installation of Thermo-Lag Fire Barrier Matl Furnished & Delivered by Thermal Science,Inc. Eight of Ten Thermo-Lag Fire Barriers Installed by Pr Sussman Co Being Replaced1994-08-15015 August 1994 Part 21 Rept Re Improper Installation of Thermo-Lag Fire Barrier Matl Furnished & Delivered by Thermal Science,Inc. Eight of Ten Thermo-Lag Fire Barriers Installed by Pr Sussman Co Being Replaced ML20070H1471994-07-15015 July 1994 Part 21 Rept Re Problems W/Thermolag Fire Barriers.Initially Reported on 940715.Replaced Thermolag Fire Barriers ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 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 ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20102B2071992-06-24024 June 1992 Part 21 Rept Re Cracking of Stellite 21 Hardfacing on Guide Nose of Poppets Supplied as Part of MSIV Leakage Improvement Mod.Initially Reported by Clei on 920522. Recommends That Liquid Penetrant Exam Be Performed ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used NRC-89-0267, Deficiency Rept Re Item 143 on as-built Deviations.Qa Audit Conducted on Category C Deviations in Sept 1989.Remaining Category C Deviations Resolved During Refueling Outage1989-11-30030 November 1989 Deficiency Rept Re Item 143 on as-built Deviations.Qa Audit Conducted on Category C Deviations in Sept 1989.Remaining Category C Deviations Resolved During Refueling Outage ML20196B8481988-01-29029 January 1988 Part 21 Deficiency Rept Re HPCI Suction Pipe Overpressure Transient.Initially Reported on 880129.Caused by Installation of Lift/Plug Check Valve.Potential Water Hammer Condition Corrected by Replacing Valve NRC-87-0259, Part 21 Rept Re Unqualified Kalrez Soft Seats Used in Feedwater Check Valves Supplied by Atwood & Morrill Co. Initially Reported on 871203.Soft Seats for Valves Replaced W/Soft Seats Using Parker Compound E692-751987-12-0808 December 1987 Part 21 Rept Re Unqualified Kalrez Soft Seats Used in Feedwater Check Valves Supplied by Atwood & Morrill Co. Initially Reported on 871203.Soft Seats for Valves Replaced W/Soft Seats Using Parker Compound E692-75 NRC-87-0105, Part 21 Rept Re Failures of Hydrogen/Oxygen Sampling Sys Supplied by Exo Sensor,Inc.Initially Reported on 870630. Sensors to Be Replaced at 6-month Intervals & Tested Every 30 Days to Ensure Operability1987-07-0606 July 1987 Part 21 Rept Re Failures of Hydrogen/Oxygen Sampling Sys Supplied by Exo Sensor,Inc.Initially Reported on 870630. 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Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly 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 ML20211D8351986-06-0606 June 1986 Part 21 Rept Re Failure of Four External Closing Springs on MSIVs Supplied to Plant Due to Quench Cracks Developed During Mfg Process.Encl List Details Utils,Plants & Quantity & Size of Valves Supplied ML20195E4881986-05-23023 May 1986 Part 21 Rept Re Potential Failure of Ite/Gould Disconnect Switch,Type 7860 Ds Series.Instructions for Verification of Proper Operation of Switches Included in Notification to Plants.New Switches Available by 860901 ML20141A2501986-02-25025 February 1986 Part 21 Rept Re Two Broken Carrier Assemblies from NEMA Size 5 Contactor A103G12,preventing Proper Closing of Contactor. 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Initially Reported on 841107.Item Not Reportable Per 10CFR50.55(e) ML20101M9621984-12-13013 December 1984 Amend to Final Deficiency Rept,Item 114 Re Possible Overpressurization of North RHR Hx.Initially Reported on 840124.Investigation & Analysis Determined HX Acceptable for Intended Function ML20101M9521984-12-12012 December 1984 Final Deficiency Rept,Item 139 Re Deficient Shop Weld in Fluid Head Structure.Initially Reported on 841015.Review of Stress Calculations Revealed Max Stress on Welds Does Not Exceed Allowable.Item Not Reportable Per 10CFR50.55(e) ML20100N8841984-11-30030 November 1984 Supplemental Final Deficiency Rept,Item 111 Re Design Deficiency on RHR Reservoir Freeze Over.Methods for Adding Heat to RHR Reservoir Clarified ML20100N8651984-11-30030 November 1984 Amended Final Deficiency Rept,Item 116 Re Potential Design Deficiency Allowing Freezing of Buried Piping Sys.Walls Will Be Installed & Temp Monitored.Pipes Will Not Be Rerouted ML20100L2041984-11-30030 November 1984 Interim Deficiency Rept,Item 141 Re Deviations from Specified Clearance Between Cable Trays & Vertical Support Members.Initially Reported on 841107.As-built Tray/Hanger Clearance for Hangers & Cable Trays Acceptable ML20100K7301984-11-27027 November 1984 Final Deficiency Rept,Item 129 Re Lack of Design Calculations for HVAC Duct Supports.Initially Reported on 840614.Supports & Base Plates Modified & Installation Discrepancies Documented on Nonconformance Repts ML20099F5011984-11-0505 November 1984 Final Deficiency Rept,Item 121 Re Water Found in HPCI Lube Oil Reservoir.Initially Reported on 840330.Byron-Jackson Field Mod Request 6337 Revised to Provide Proper Piping Configuration for Main Pump Seal ML20099E3911984-11-0303 November 1984 Final Amended Deficiency Rept,Item 76 Re Limitorque Switch Rotor Failures.Initially Reported on 820731.Repairs Performed Per Maint Instructions MI-M070,M179,M182,M203,M272 & M187 ML20099F5381984-11-0202 November 1984 Final Part 21/deficiency Rept Re Contaminated Hydraulic Fluid in Hydraulic Pipe Snubbers.Initially Reported on 821015.All Affected Hydraulic Pipe Snubbers Returned to Power Piping Co for Refurbishment ML20099F5261984-10-31031 October 1984 Final Deficiency Rept,Item 112 Re Poor Quality of Vendor Connection Workmanship in Emergency Diesel Generator Panels. Initially Reported on 840113.Deficient Wiring Terminations Documented on Nonconformance Repts Reterminated 1997-09-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217N4381999-10-25025 October 1999
[Table view]Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0062, Monthly Operating Rept for May 1999 for Fermi 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fermi 2.With ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety NRC-99-0022, Monthly Operating Rept for Apr 1999 for Fermi 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fermi 2.With ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 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for Nov 1998 for Fermi 2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fermi 2.With NRC-98-0160, Monthly Operating Rept for Oct 1998 for Fermi 2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fermi 2.With ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode NRC-98-0139, Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With ML20154H8161998-09-30030 September 1998 Rev 0 to COLR Cycle 7 for Fermi 2 ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 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Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval NRC-98-0015, Monthly Operating Rept for Dec 1997 for Fermi 21997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Fermi 2 ML20217N3821997-12-31031 December 1997 Annual Operating Rept for 970101-1231 NRC-98-0053, 1997 Annual Financial Rept for Detroit Edison Company1997-12-31031 December 1997 1997 Annual Financial Rept for Detroit Edison Company ML20205Q9601997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Fermi 2 NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent 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August 18, 1982 EF2-59386 Mr. James G. Keppler, Regional Mministrator Region III
_.U.S. Nuclear Regulatory Comission 799.Rooseveit Road Glen Ellyn, Illinois 60137
Subject:
Interim Report of 10CFR50.55(e) Item on Rosemount Trip Units (#75)
Dear.Mr. Keppler:
On July 20, 1982, Detroit Edison's Mr. G.M. Trahey, Assistant Director-Project Quality Assurance, telephoned Mr. J. Konklin of NRC Region III to report on a potential problem with Reactor Pressure Trip Units at the-Fermi 2 site.
During calibration of Rosemount Model 510 DU Trip Units, it was determined that a high percentage could not be calibrated. Without circuit analysis, Engineering is unable to determine whether or not, if uncorrected, the problem would prevent the unit frm performing its function properly.
Based on preliminary evaluation, the cause is balieved to be oxidation of-the trip set point adjusting potentiometer windings due to inadequate storage environment. Investigation is incmplete at this time. Additional informa-tion will be provided upon completion of investigation.
Another report on this item, either interim or final, is scheduled to be sent to you on or before December 16, 1982. If you have questions concerning this matter, please contact Mr. G.M. Trahey, Assistant Director-Project-Quality Assurance.
-Very truly yours, f t l DAW /DF/cp d cc: Mr. Richard DeYoung, Director Office of Inspection and Enforcement Division of Reactor Inspection Programs Washington, D.C. 20555 Mr. Bruce Little, Resident Inspector U.S. Nuclear Regulatory Comission 6450 North Dixie Highway, Newport, Michigan 48166
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