|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARB17414, Part 21 Rept Re 980116 Failure of Tachometer Transducer,Id Number TG-25-5,during Surveillance Test.Caused by Bearing Failure Which Could Cause Shaft to Seize & Break.Removed from Svc & Replaced Failed Tachometer Transducer1998-09-0303 September 1998 Part 21 Rept Re 980116 Failure of Tachometer Transducer,Id Number TG-25-5,during Surveillance Test.Caused by Bearing Failure Which Could Cause Shaft to Seize & Break.Removed from Svc & Replaced Failed Tachometer Transducer ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236Y1231998-08-0707 August 1998 Part 21 Rept Re Gas & Turbine Generator for Dedicated Emergency Power to Vital AC Buses ML20247B6751998-05-0101 May 1998 Part 21 Rept Re Evaluation & Notification for RELAP4 Excessive Variability at Millstone Unit 2.Caused by Small Changes in Input to RELAP4 That Can Result in Large Changes in Calculated Peak Cladding Temp.Informed NRC of Deviation ML20198E0631998-01-0707 January 1998 Part 21 Rept Re Shipment by Dubose National Energy Svcs,Inc, of 40 Pieces of 4 inch,90 Degree Elbows Which Did Not Meet ASME Section II SA-234 Requirements 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 B16531, Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair1997-07-0303 July 1997 Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair ML20140D6581997-06-0606 June 1997 Part 21 Rept Re GE Model Ifcs Relays Procured from GE Delivered W/Loose Hardware & Unsuitable for Use at Unit 1 ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A B16149, Part 21 Rept Re Cracked Fuse Ferrule Defects Due to Administrative Error in Ltr Detailing Commitments Re Issue. Corrected Copy of Commitments Associated W/Ltr Provided1997-01-14014 January 1997 Part 21 Rept Re Cracked Fuse Ferrule Defects Due to Administrative Error in Ltr Detailing Commitments Re Issue. Corrected Copy of Commitments Associated W/Ltr Provided B16030, Part 21 Rept Re Stocked safety-related Fuses Issued from Storeroom for Installation Which Had Cracked Ferrules in Longitudinal Direction on 960911.Procurement & Warehouse Groups Completed Inspecting Fuses in Warehouse1996-12-13013 December 1996 Part 21 Rept Re Stocked safety-related Fuses Issued from Storeroom for Installation Which Had Cracked Ferrules in Longitudinal Direction on 960911.Procurement & Warehouse Groups Completed Inspecting Fuses in Warehouse ML20134N4061996-11-22022 November 1996 Part 21 Rept Re Fifteen Different Fuse Types from Three Different Mfgs Found to Have Axial Cracks Due to Brass Being Susceptible to Defect.Functional Testing Should Be Performed on Sample of Fuses ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology LD-96-014, Part 21 Rept Re Response to NRC Notice on Nonconformance. Licensee Will Direct Cognizant Personnel Reviewing Deviation or Failure to Comply for Basic Components Delivered to Customers,To Document Whether/Not Facts Indicate Evaluation1996-04-26026 April 1996 Part 21 Rept Re Response to NRC Notice on Nonconformance. Licensee Will Direct Cognizant Personnel Reviewing Deviation or Failure to Comply for Basic Components Delivered to Customers,To Document Whether/Not Facts Indicate Evaluation 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 B14680, Part 21 Rept Re Substantial Safety Hazard Evaluation of RCP Turning Vane Cap Screws.Util Increased head-to Shank Fillet Radius to Reduce Stress Concentration & Reduced Thread Engagement to Reduce Axial & Bending Stiffness1993-11-22022 November 1993 Part 21 Rept Re Substantial Safety Hazard Evaluation of RCP Turning Vane Cap Screws.Util Increased head-to Shank Fillet Radius to Reduce Stress Concentration & Reduced Thread Engagement to Reduce Axial & Bending Stiffness 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 B14544, Update to 900827 Rept of Substantial Safety Hazard Re GE Custom 8000 Horizontal Induction Motors,Reported Per 10CFR21 for Unit 3.Util Has Determined,As Part of Review of in 91-007 That Subj GE Motors Also Used at Units 1 & 21993-08-11011 August 1993 Update to 900827 Rept of Substantial Safety Hazard Re GE Custom 8000 Horizontal Induction Motors,Reported Per 10CFR21 for Unit 3.Util Has Determined,As Part of Review of in 91-007 That Subj GE Motors Also Used at Units 1 & 2 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 ML20085N3251991-11-0101 November 1991 Part 21 Rept Re Hardness Levels,In 8 of 20 Bolts in Steam Generator,W/Approx Half of Expected Value for Matl Spec. Bolts Supplied by Process Products,Ltd & Cardinal Fastener & Specialty Co.All Bolts Will Be Replaced L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl B13620, Part 21 Rept Re Substantial Safety Hazard Involving GE Custom 8000 Horizontal Induction Motor.Pump Motor Failure Identified Due to Loud Noise During Operation.Caused by Loosening of Clamps of Air Deflector.Damaged Motor Removed1990-08-27027 August 1990 Part 21 Rept Re Substantial Safety Hazard Involving GE Custom 8000 Horizontal Induction Motor.Pump Motor Failure Identified Due to Loud Noise During Operation.Caused by Loosening of Clamps of Air Deflector.Damaged Motor Removed B13621, Part 21 Rept Re Substantial Safety Hazard Involving Westinghouse Veritrek Transmitters.Large Shift in Output Observed While Attempting to Calibr Two Transmitters. Internal Review Performed & Defective Transmitters Replaced1990-08-27027 August 1990 Part 21 Rept Re Substantial Safety Hazard Involving Westinghouse Veritrek Transmitters.Large Shift in Output Observed While Attempting to Calibr Two Transmitters. Internal Review Performed & Defective Transmitters Replaced ML20043A2491990-05-11011 May 1990 Part 21 Rept Re Tufline Plug Valves.Metallographic Exam of Cracked Bolting Revealed That Failures Due to Igscc.Cause Not Determined.Lubricant Used Not Tested or Certified for Low Halogen Content.Addl Metallographic Exam Underway ML17223A5941990-03-0909 March 1990 Errata to 900126 Part 21 Rept Re Anchor/Darling Actuators Incorporating Use of Teldyne-Republic four-way Valves.Lists Plants Inadvertently Left Out in Original Rept B13253, Part 21 Rept Re Failure of Several Motor Control Starters Mfg by Telemecanique Due to Mechanical Binding in Motor Starter.Initially Reported on 890512.Failed Starters W/Units Replaced & Two Failed Starters Returned for Vendor Tests1989-05-15015 May 1989 Part 21 Rept Re Failure of Several Motor Control Starters Mfg by Telemecanique Due to Mechanical Binding in Motor Starter.Initially Reported on 890512.Failed Starters W/Units Replaced & Two Failed Starters Returned for Vendor Tests ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H B12449, Part 21 Rept Re Noryl Plastic Insulation Deterioration on Bus Bars in Certain Metaclad Switchgear at Facility. Switchgears Used in safety-related Circuits Will Be Inspected & Repaired During Refueling Outage in Nov 19871987-03-0404 March 1987 Part 21 Rept Re Noryl Plastic Insulation Deterioration on Bus Bars in Certain Metaclad Switchgear at Facility. Switchgears Used in safety-related Circuits Will Be Inspected & Repaired During Refueling Outage in Nov 1987 ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20211C8371987-02-13013 February 1987 Part 21 Rept Re Insufficient Length of Upper Adjusting Ring Retaining Pins on Dresser Main Steam Safety Valves. Initially Reported on 870211.Defective Pins Replaced 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 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 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 B12082, Part 21 Rept Re Substantial Safety Hazard Due to Generic Defect in Ite/Brown Boveri Type K600S Circuit Breakers. Initially Reported on 860501.Mod & Repair of Breakers Continuing1986-05-0909 May 1986 Part 21 Rept Re Substantial Safety Hazard Due to Generic Defect in Ite/Brown Boveri Type K600S Circuit Breakers. Initially Reported on 860501.Mod & Repair of Breakers Continuing ML20141D8051986-04-0101 April 1986 Part 21 Rept Re Model 402 Series Level Control Used for safety-related Application Shipped W/O Torque Check. Customers Will Be Notified by 860428 & Requested to Perform Torque Check.List of Plants Using Component Encl ML20137X3891986-02-27027 February 1986 Part 21 Rept Re Possible Defect in Model KMG-HRH Noble Gas Radiation Monitor W/Enhanced Detector Model KDGM-HR. Initially Reported on 860222.Vendor Will Request Utils for Listed Plants to Determine If Monitors Defective ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder ML20137N4831986-01-17017 January 1986 Final Potential Significant Deficiency Rept SD-57 Re High Energy Steam Line Breaks Outside Containment.Initially Reported on 840605.Info on Impact of Break on Environ Qualification of Equipment Outside Containment Submitted ML20138K8401985-12-0303 December 1985 Final Part 21 & Deficiency Rept SD-41 Re Gould Type He 4 100-amp Frame Size Breaker in 480-volt Motor Control Ctr Which Failed When Pole C Did Not Close When Breaker Operated.Initially Reported on 830608.Breakers Replaced ML20137N5611985-11-13013 November 1985 Final Part 21 & Significant Deficiency Rept SD-82 Re Errors in Westinghouse Core Exit Thermocouple Sys.Initially Reported on 850509.New Emergency Operating Procedure Setpoints Calculated.Item Not Reportable Per 10CFR50.55(e) ML20137R0291985-11-13013 November 1985 Final Potential Significant Deficiency Rept SD-56 Re Undocumented Linear Indications & Excessive Geometric Unsharpness of Tubeco Weld Radiographs.Initially Identified in Insp Rept 50-423/85-14 on 831122.Weldments Repaired ML20137S0981985-11-12012 November 1985 Final Potential Significant Deficiency Rept SD-89 Re Binding of Telemecanique (Formerly Gould) Starter Contact Carrier Assemblies.Initially Reported on 851014.Size 1 & 2 Starters Being Inspected.Vendor Has Supplied Retrofit Kits ML20137N5101985-11-12012 November 1985 Final Potential Significant Deficiency Rept SD-75 Re Nonconforming Terminations in CVI Corp Equipment.Initially Reported on 850213.Insp of Lugs Completed.Deficient Terminations Repaired or Replaced ML20198F7421985-11-0101 November 1985 Final Part 21 & Deficiency Rept SD-25 Re Failure of Pinion Gear Shear Keys in Limitorque Model SBO Motor Operated Valves.Initially Reported on 820903.Westinghouse Determined Item Not Reportable Per 10CFR50.55(e) ML20198F7041985-11-0101 November 1985 Deficiency Rept SD-56 Re Tubeco Weld Radiographs.Initially Reported on 840618.Review of Tubeco Radiographs for QA Category I,Asme III Code Class 1,2 & 3 Welds Complete.Final Rept Will Be Provided by 851113 1998-09-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
[Table view] |
Text
g General Offices
[ ""['j'
, ,,',*, "" HARTFORD. CONNECTICUT 06141-0270
.,,,, o,,,,o ,. ,u w. (203) 666-6911 J . . - , -
July 1,1983 Decket No. 50-423 B10832 Dr. Thomas E. Murley, Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction: Westinghouse 7300 Process Protection System Potential Problems with NLP Card Heat Sinks (SD-40)
As required by Title 10, Code of Federal Regulations Part 50, Paragraph 5)(e),
Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the design of Millstone Unit No. 3 in a June 2,1983 telephone conversation between your Mr. Johnson and our Mr. R. E. Lefebvre.
Our notification to you was made under the advice of Westinghouse, who on June 1,1983 notified affected customers and provided an initial notification of a potential problem to the NRC.
Attached is a copy of Westinghouse letter NS-EPR-2774 from E. P. Rahe to R. C. DeYouag, dated June 8,1983. We have reviewed the subject problem concerning the failure of adhesive bonds for thermal heat sinks on the inverter transistors associated with loop power supply (NLP) cards. We agree with the Westinghouse assessment of the failure mode and concur with the corrective action of hardware changes which eliminates the adhesive. As such, it is our position that this letter, including the attached Westinghouse report / correspondence, constitutes our final report on this significant deficiency.
We trust the above information satisfactorily responds to your concerns.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
//7VP W. d. 'Counsil " 8 Senior Vice President 8307110390 830701 PDR ADOCK 05000423 S PDR $6d
- m. CE .
0220 '00/06/15 08228 NEU-4705 Westinghouse WaterHeactor wucpaimucom Electric Corporation DMstans em PiniW:ghPesyMNa 15130 June 14, 1983 S.0. No: NEU-320 kr. $. Orefice
- Project Engineer NORTHEAST UTILITIES SERVICE COMPANY P.O. Box 270 Hartford, Connecticut 06141 '
NORTHEAST UTILITIES SERVICE COMPANY MILLSTONE NUCLEAR POWER STATION UNIT NO. 3 7300 Process Protection System Potential ProbTems With NLP Card Heat Sinks and NTC Card Relays
Dear Mr. Orefice:
~
With reference to the subject sotential problems, attached is a copy of
= Westinghouse sent on June 8,1983. letter NS-EPR-2774 from E. P. Rahe to R. C. DeYoung which was TheYe"pWt#iit'f ar ~ problems were verbally discussed with a member of your projects organization on June 1, 1983.
Please foregoing. feel free to contact us if there are further questions regarding the J.b.;,,x- _..
Very truly yours, ,
J WESTINGHOUSE ELECTRIC CORPORATION 1r.ht= 1 - A A R. L. Hofe'r , fnager NUSCO Projects Gregg/nnc/12510: 1 Attachment ec: S. Orefice 4L 4A R. W. Ackley 6L, 3A enum
+
u **
,- d *
- - *N +-.
_ _ -__ - __.___ - _-_ - - A
~
{
- ~
'00.<'06/15 08331 02 {4 NEU-4705
( .
bec: R. L. Hofer IL R. Cepko 1L. TA D. R. Gregg TL W. E. Cheshire (MNO 578) 1L J. Cartson (Hartford Sales) IL R. M. Pantuck (Boston Sates) TL ~
H5ID tentral Fife R&D Bidg. 707, 4th Fiocr IL. TA J. Dolan (W Site Manager) 2L, 2A E. R. Duhn 1L
,, g - .
I s
f e'
O O
e b
-e l
. .o
' *[ ** ,
. ,Q,
.'y__. . S ^;akl& <.--
-$ *k Nhiksk
' c. n 02Pd '00/06/15 08334
.U ,
(- \ W -
I Westinghausa
~
Water Reactor seus .'
E:ectric Corporation DMsions 8*W"A 2
. . NS-EPR-2774 June 1,1983 Mr. k. C. DeYoung. Director -
Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Phillips Building
Bethesda, MD 20014
Dear Mr. DeYoung:
This is to confirm the, telephone conversation of June 1, 1983, between ,
Messrs. D. H. Rawlins and C. G. Draughon of Westinghouse and Mr. N.
V111alva of the NRC. In that conversation, Westinghouse notified the f NRC of two potential problems within the Westinghouse 7300 Process Protection System. This was re plants and under 10CFR 50.55(e)for ported plantsunder under10CFR 21 for operating construction.
Westinghouse has advised its NSSS utility custor.ers of this determination. The two concerns are described below.
- 1. Heat $1nks on NLP Card Description of Problem .
Heat sink adhesive failures have been identified at several utilities and were reported to Westinghouse as field deficiencies.
All reported field failures have occurred only on the loop power supply (NLP) cards. Westinghouse has determined that NLP printed circuit cards shipped from Westinghouse Industry Electronics Division (WIED) between August 1,1980, and September 1,1982, were equipped with a thermal heat sink assembly on the inverter transistors that are subject to potential failures in the adhesive bond in the thermal link assembly. The adhesive bond is between an insulating washer and the thernal link (see Attachment 1). Failure of the band can cause the heat sink plate to separata from the thernal ifnks and fall off of the printed circuit board. The plate is conductive metal and under certain circumstances could cause shorting of low level signals if it became wedged between cards in the card frame. The affected printed circuit boards are:
1
-(
b gg M o Miro % 3
%= ~aw%
Pbitlll[
[' ' g : ([ O ( '00/06/15 08 38
./ '-
5NLP Sub-Tevel 18 and above "
6NLP Sub-levei 18 and above
( Note: Previous Sub-Teveis did not contain heat sinks.' Th's assembly sub-TeveT jdentification sticker is attached to the solder side of the card near the front edge. It is not the revision identified on the front edge.
The adhesive failure mechanism or expected number of hours of system operation before failure is not defined. All reported problems have occurred under normal system usage or storage. To date, these heat sink adhesive failures have not resulted in any damage to the Westinghouse 7300 Process Protection System nor have these failures resultedinanyJossofsystemsafetyfunctions.
CorrahtiveAction Weskinghouse has committed to provide replacements for the heat sinks that are subject to this potential adhesive fa1Ture meenanism. These heat sinks can be identified by inspection of the printed circuit card for hex nuts visible on the top side of the assembly. See attached drawing 404A605 (superceded) (Attschment li) . The new style heat sink has screw heads visibTe from the top side of the assembly (see Drawing 403A947 Attachment 2).
NTo justify continued piant operat. ion until these heat sinks can be -
p replaced with the new design, Westinghouse reconnends that utilities inspect their 7300 Process Protection System for separated heat t
sinks and remove any heat sinks that are separated. This inspection should be conducted during each periodic system test until the heat
. sinks are replaced. In addition, Westinghouse has determined that:
- a. Tne NLP card can operate satisfactorily without the heat sink.
- b. If a heat sink disiocates during operation and causes a failure,
, the probability of the failure being detectable is high. .
Attachment 3 to this letter is a Tisting of piants which have been i shipped the potentia 1Ty defective NLP cards. In addition to t
WIED supplies this type of equipnent Westinghouse direct y to Architect NSSS Engi plants, iieers for utility balance of plant (BOP) use and also to other N555 vendors.
~
- 2. NTC Card Relay Description of Problem During seismic testing of the Temperature Channel Test (NTC) card, contact bounce was experienced in the mercury relay utilized on this card. This intermittent contact bounce will result in signal l saturation of the downstream RTD Amplifier (NRA) card in the That and Tcold circuits of the Westinghouse 7300 Process Protection l ( System. In these systems, filters are adjusted to maintain a total l
time constant of approximately two seconds for the R7D/ filter combination. Since the filter is downstream of the relay, the e ' *
. .u.: w-e
e
~ '
~
characterist.. f of the channei response depb s on the time constant
~ of the filter. For RTD's specified by Westinghouse, the filter has been set at either zero or two seconds depending on the type of RTD i
(fast or slow response) ut1712_ed. For applications utilizing unfiltered signals, saturation of the NRA card could delay initiation of the Overtemperature - Detta T and Overpower - Delta T l
trips. ' For applications utilizing a fi'itered signal, NRA card saturation would not spur 1ous piant trip. prevent plant only trips,occurs but could as a result result ic of a
~
This problem contact bounce induced by a seismic event. A list of piants :
utiliz'ing filtered and non-filtered circuitry are provided in .i Attachments 4A and B. This Tist also provides a reference for all Westinghouse piants utilizing 7300 process protection equipment. '
Corrective Action Attachment 48 Tists the plants utilizing unfiltered signals which may experience trip delays due to intermittant relay contact bounce during a seismic event. A replacement relay is being developed and tested and most of these plants will have the replacement reiays installed prior to operation.
For operating plants with unfiltered signals. Westinghouse recom= ends that the existing filters be set for a one second response. This will eliminate the potential delay and ensure that the plant will trip on demand. If the plant does not have -
sufficient time response margin to accomodate the one second -
response, then the relays must be bypassed with permanently f installed jun,pers until the replacement relay is installed.
If you require additional information on these subjects, please contact C. G. Draughan of my staff at 412-374-5761.
Very truly yours, ..
bb'!
E. P. Rahe, Manap r Nuclear Safety Department
(
/ KEG Attachment (s)
G
( .
l .
_%,,,, e gu ' ._
+g.
+d M S 4.s.e 'how k
,.+- e 0220 700/06/15 08:44 i* ~w h; $$ e
$Yk I k N '4? (.rACHMENT1
~
, w*nA ~
, J m$ ' : p.
r **<<. .
T '
- i! !! ! ! ! dE w@.AG :
' .b ~
Westinghouse' Electric Corpora' ttori . ' * * * *J4T E* T
- 2 l mte HEKT SIMK ASSEuSLY w {
[
Cwa 40 4 AGO3 sus.s A3 -
rm.m cum 3 3 . _ . _ ,. - "
. o m e.= ~ . i,. i,.cx ==
,,,r, m -
= , .,,. , ,, , ,l, ,
l HE.AT SI N A Pl.JTE i J25 35 A 35 H01 1 l l i 2 THEFMAL LINK ! 404AGCGMol 4 (
i l 3 .t38 - 32 14YLON HE.x NUT 7 0 9 0 80 -
4 '
1- I I
- 4. I~
.l'55 9.T TCCTH WOMEE lidos 4 ' '
I 5 LOCT! TE # 271 ,,,_[~ W
' ' '~
l 2 G t 52.'_" . , ,
l 0, . 5 40 A')4760I fg ggw 1)E516N- _
l-To RETROFir To P.xisil% F1C.BD A55EMEL155, MouuT THERMALLINK 1T.2 T: TRAN5($ TORS BEFORF ASSEMEUNG TO HEAT S1MA I: LATE \T.I~ .
k??LV TO THRD:5 * ~~ M A XIM UM 7'CRQUE S IN.-L25.-
l .'O
^ .5
%s '
4 (2 s
o
-)
,h h , ' *
.' Y- i '
i Mg
. T' '
YY '
L50 l RE?.
4P
(.
2.00 REE =- .0 4 -- --- 4 2 ~
su/MstGCD STANCAAQ CRAWING - -
ANY QeM*Cf M BE AlmeCaltt3 sv QE'WELOPu(NY DeQl4ttpi>G OgrP, 4 ,
~ ~~F,
- __ "y g g
e
7(
g, ATTACHMEN.T2(
. { n. .l.
a i ~
( l i!,. !.
. i. 1. , d.
'" '"S*
Westinghause Sectric Corporation . *2?E*JH2E" w
TTT1 w HEAT !!NW ASSEMBLY, 70 ~ S
pg, g, -
7 STYLE No. DESCR//7/CN GROdP
- M i 12iJifISi l 235SA 3EH01 l HEA7' 5/NM PL ATE llI l l t l 2 404A 947H01 l THEWMAl. UNX ,+l l l 3 1 M02l Shout.3ER WASMER -
,4 l l
+ 1 _ M05\35 0 WASHER __
U+ l ! l 1 11 10/0/ l4-40 X .fS SCREW, B/ND. AD . - 1+! l l
/ ~
5
( .
.58 -
2
~l. ,
i e c.----.1
- @ @. y a
m 4
3
+
t .
= -
2.00 REF. -1 .0'~ =m . 42
. ETANDARD CMAWING g A saw o.uce war en mnem _u j-n m. e-. , e w,. .... -
l
[ _ ,, ' ,
_ . . .. .2 .. .
. c- ,
ATTACHMENT 3 (1 a 0220 '00/06/15 08:51
( Plants Having Potentially Defective NLP Cards '
1 1
IED records shcw the following projects have scme NLP Cards with the old style heat sink assemblies which should be replaced. -
I. Supplied with Original of NSSS Process Protaction Systens:
SITE P.S. OF N.H. - SEABROOK KO-RI #2 - KOREA NAPOT PT. - PHILIPPINES VANDELLOS - SPAIN WOLF CREEK CALLAWAY #2 NAP 0T PT. - PHILIPPINES TAIWAN POWER - MAANSHAN #1 TAIWAN POWER - MAANSHAN #2 KO-RI #5 - KOREA CP&L - SHEARON HARRIS #1 DUKE POWER - CATAWBA #1 C DUKE POWER CATAWBA #2 N.E. UTILITIES - MILLSTONE #3 -
S.C. ELECTRIC & GAS - SUMMER LEMONIZ, SPAIN ASCO SPAIN .
, ASCO, SPAIN -
COMM. EDISON - BYRON #1 COMM. EDISON - SYRON #2 COMM. EDISON - BRAIDWOOD #1 c COMM. EDISON - BRAIDWOOD #2 TEXAS UTILITIES - COMANCHE PEAK #1 TEXAS UTILITIES - CDMANCHE PEAK #2 CALLAWAY #1 WOLF CREEK #1 CALLAWAY #2 P.S. OF N.H. - SEABROOK II. Supplied in Other Than NSSS Systens:
SITE i
VEPCO - NORTH ANNA i VEPC0 - NORTH ANNA l 50. CAROLINA ELECTRIC & GAS - SUMMER
( COMMONWEALTH EDISON . , _ .
l $0. CAROLINA ELECTRIC & GAS - SUMMER .
l
- 50. CAROLINA ELECTRIC & GAS - SUMMER AMERICAN ELECTRIC POWER IND. & MICH. POWER ,
KANSAS GAS & ELECTRIC ,
- r. . . . .
.:f {
ATTICHMENT 3 (2 of 0,2(00 '00,'06/15 08:54 .
II.SucoliedinOtherThanNS_55Syste_ms(Cont.-): -
i SITE P'ASNY - INDIAN PT.
. VEPCO - NORTH ANNA
. DUKE POWER
. CON ED - INDIAN PT.
VEPC0 - NORTH ANNA
.- e DUKE POWER ALABAMA POWER - FARLEY ALABAMA POWER - FARLEY ANGRA - BRAZIL
' ALMARAZ - SPAIN KOREA ELECTRIC - KO-RI 2 KOREA ELECTRIC - KO-RI 2 PHILIPPINES - NAP 07 PT.
PHILIPPINES - NAPOT PT.
TAIWAN POWER - MAANSHAN ALMARAZ - SPAIN PHILIPPINES - NAP 0T PT.
l III. Repair Orders #
f, SITE CON ED - INDIAN PT. #2 TEXAS ' UTILITIES - COMANCHE PEAK IND. & MICH. POWER (AEP) RVLS
, P.S. OF N.H. - SEABROOK #2 DUKE POWER - CATAWBA KRSK0 .
TVA - SEQUDYAH TVA - SEQUDYAH NOTE: - = WNSD ALSO BEING NOTIFIE0 AS THIS WAS AN NSD ORDER
- = THIS SITE IS ALSO ON THE SYSTEMS LIST
(
- 0 e
. .~ . m .
('
, , l. -
. ATTACHMENT 4A 0{# '00/06/1508558
( .
FlitarefPlants' .
(Utilize a Fast Response RTD)
- Joseph M. Farley Unit 2 North Anna Unit i
, Wm. B. McGpire Unit 1 North Ann.a Unit 2
f .
~l- .
. b e
( .
4475Q
. s.u.. ~.
r, ..;,7..
" J 02 " '00/06/15 09:01 ATTACHMENT 48,
( .
Non-Ffitered Plants
, (Utilize a Slow Response RTD)
Comanche Peak Units 1 and 2
, Seabrook Units 1 and 2 Beaver Valley Unit 2 i
Byron Units 1 and 2 Braidwood Units 1 and 2 Vogtie Units 1 and 2 Shearon Harris Units 1 and 2 Catawba Units 1 and 2 South Texas Units 1 and 2 M1Tistone Unit 3 Marbie Hill Units 1 and 2
Callaway Unit 1 f Wolf Creek Unit 1 4
Overtemperature N-16 channels for these plants utilize Tcold signal. HRA card saturation would not prevent plant trips, but could result in a spurious plant trip.
O 9
e S 9 -
--4 **',A ** m %