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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
gg General Offices
- Seldon Street, Berlin, Connecticut ErY e,s$a w.", P.O. BOX 270
.a me. ...o.enco , HARTFORD. CONNECTICUT 06141-0270 g ioa'.aw wruen mam cow- (203) 666-6911
.o . . co -
September 8,1983 Docket No. 50-423 B10885 Dr. Thomas E. Murley, Regional Administrator Region i U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Reference:
(1) W. G. Counsil letter to J. M. Allar, Millstone Nuclear Power Station, Unit No. 3, Reporting of Potential Significant Deficiencies in Design and Construction: Main Control Board Welds (SD-36), dated May 13,1983.
Dear Dr. Murley:
Millstone Nuclear Power Station, Unit No. 3, Reporting of Potential Significant Deficiencies in Design and Construction: Main Control Board Welds (SD-36)
In Reference (1), Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency as required by 10CFR50.55(e) involving inadequate welds on main control board panels supplied by Reliance Electric Company.
On May 17,1983, Reliancu Electric Company with the assistance of Stone &
Webster implemented an inspection and repair program for all boards supplied by Reliance. Unacceptable welds as identified by Reliance were listed in two categories. The first category included welds requiring rework and the second was for welds requiring analysis to determine if they possess sufficient structural integrity to survive a design basis earthquake. The following is a listing of the two groups.
Main Control Board Repair - 200 Analysis - 234 Primary Relay Board Repair - 2 Analysis - 24 Termination Cabinets Repair - 21 Analysis - 114 830919023183090g3 -
DR ADOCK 05000 qe
- An agreement was made between Stone & Webster Engineering Corporation and Reliance Electric Company to ;use Stone & Webster welding procedures to perform field repairs on the centrol board panels. - The Reliance Q.A.' Manual was revised to include the nece sary field repair work. This revised Q. A. document
. became a controlled document on file at Stone & Webster in Boston.
Attachment I contains -' the justification for inspection of painted welds.
Reliance stated .that throughout their inspections of suspect welding, the deficiency discovered with welding involved dimensional problems, i.e., welds which were undersize, concave, or not filled out. Attachments 2 & 3 address inspection of inaccessible weld areas.
- All welds requiring repair have been completed by' Stone & Webster and accepted by Reliance and Stone & Webster Q. A. All welds requiring analysis have been analyzed by Reliance and approved by Stone & Webster and Northeast Utilities Service Company (NUSCO) as having sufficient structural integrity to withstand a design basis earthquake.
i NNECO considers these corrective actions sufficient to resolve this deficiency.
As such, this letter constitutes our final report closing out all items related to SD-36. We trust the above information satisfactorily addresses your concerns.
Please feel free to contact my staff if you have any further questions.
Very_truly yours, J
NORTHEAST NUCLEAR ENERGY COMPANY Wo ff W. G. CounsF Senior Vice President
- R s e RCMtA Et0T i RELIANCE ELECTRIC S 4900 Lewis Rd.
Stone Mountain. GA 30083 (404) 938-4888 INSPECTION OF PAINTED WELDS When the weld problem was first discovered, we had several control boards in our shop which were already painted. We performed an inspection of 100% of the welds (4500 welds) with the paint on. One of the panels was chosen to be subjected to an additional sample inspection. The number of welds in the lot size were 4000. Five hundred painted welds had already been identified as needing repair. We chose a random sample of 315 welds. This corresponds to an Inspection Level III of MIL-STD-105D which is single sampling for tightened inspection. The 315 welds were wire brushed to remove all paint.
Of the 315 welds, three butt welds were found to have a slight concavity. All of the filltets were good. MIL-STD-105D shows that the panel would be accepted based on the sample inspection. For the Millstone III boards, this translates U into an 0.065 AQL, which means that 195 defective welds (6.5 per 1000) could remain undetected (based on an estimated 30,000 welds in the Main Control Board, panels 1-8). These findings adequately support our proposal for inspecting the welds in the other sections with the paint on. We have used this approach with GA Power FL Power & Light, LA Power & Light, LILCO and Texas Utilir.tes; all of which were built in the same time period as the' Millstone boards. The inspector qualifications for the sample inspection are the same as those being used in the control boards for Millstone 111.
t2*r Richard Morrow, Q.A. Manager Custom Panels Division
${NC-d.h 's Mortheast Utiliti W111 stone Unit 3 O -._
V H e Mark No.3CES 9 MCQ Mfg. Reliance Electric Co.
4900 Lewis Rd. St. Mtn. Ga TD /*bt99
DACM MEN 7 1 RELIANCE ELECTRIC S U
INACCESSIBLE AREAS FOR WELDING INSPECTION The areas in the Main Control Boards which are not accessible for weld inspection are those vertical surfaces covered by subpanels and wireways. The accessible vertical areas were surveyed in order to establish the relationship between the '
vertical areas and the good / bad welds. The type of weld hidden behind the sub- '
panels and wireways is the fillet described by our drawing WS-1-NU-C (SWEC I welding tech sheet W70G). '
A sunanary of the survey follows:
! Total Accessible Total No. Total Defective Total Area l MCB'No. Vert. Area (Sq Ft) of Welds Welds Inaccessible (Sq Ft)
MB1, 2 224 428 4 49 )
MB3 122 238 11 32 MB4 110 279 5 95 O
V MB5.6,7 219 447 2 79 MB8 147 378 4 28 TOTALS 822 1770 26 283 The projection for the inaccessible areas follows:
Defects per Total Area Expected No.
[ MCB No. Square Foot --
Inaccessible Of Defects MB1,2 .018 49 1 MB3 .090 32 3 MB4 .046 95 5 MBS,6,7 .009 79 1 MB8 .027 28 1 SWEc> aA a Northeast Utiliti e Millstone Unit 3 K..ehf /h)
Mark No'4CES#flIQ3 SL 7 Mfg. Reliance Electrio Co.
O V 4900 Lewis Rd. St. Mtn. Ga.
JO 11/79
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( sI IJO tid l 4 30 0 $$ $ 'e i IIl w 1 ( # DIJO I,4 8l $0' I
O MB 1 & 2 INACCESSIBLE AREAS FOR WELD INSPECTION There is a total Of 273 square feet of vertical surface in this section, of which 49 square feet is not accessible for weld inspection.
Of the 428 welds inspected on these vortical surfaces, the following were found to be defective:
l
! Weld No. Defect Description l .
145-A WS-1-NU-C W70G. Wald is 1 3/4" long. It has 1/8" of overlap at each end. The required length is 1".
t 130-A WS-1-NU-C, W700. Tack weld (1/4" long) is between j two fillet welds of proper size, length & spacing.
I 125-A WS-1-NU-C W70G. The 2" fillet has a small hole in one end (1/32" Us). AWS D1.1 allows more porosity than is present.
l 123-R WS-1-NU-C, W70G. Excessive porosity was removed by l grinding. Rewelding was not necessary.
l l
There is a total of 154 square feet of vertical surface in this section, I
of which 32 square feet is not accessible for weld inspection. .
Of the 238 welds inspected on the vertical surfaces, the following were
, found to be defective:
l :
l Weld No. Defect Description l
100-R WS-1-NU-C, W70G. Incomplete fusion.
l 102-R WS-1-NU-C W70G. Incomplete fusion.
l 104-R WS-1-NU-C, W70G. Incomplete fusion.
- 110-R WS-1-NU-C W70G. Incomplete fusion.
103-R WS-1-NU-C, W70D. Incomplete fusion.
The repair did not include welding.
105-R WS-1-NU-C, W70G. Incomplete fusion.
115-R WS-1-NU-C, W70G. Incomplete fusion. g gM 1, The repair did not include welding. Millstone Unit 3 118-R WS-1-NU-C, W70G. Incomplete fusion. P.O. 2424 10 - 45 A 117-R WS-1-NU-C, W70G. Incomplete fusion. ,,,, y} E ,, 6s Bea:Er j q 116-R WS-1-NU-C, W70G. Incomplete fusion.
WS-1-NU-C, W70G. Incomplete fusion.
Mark No.MSNM L 7
' tg 132-R Mf8. Reliance Electric Ce The repair did not include welding. 4900 Lewis Rd. St. Mtn. c4 70 #2i?9 l
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N rth3 cst Utilttico M1110 tono Unit 3 1 2-y e 1 Maric No.3CES+ MM E @ 7 Mrg. Reliance Electrio Co.
MB4 4900 Lewis Rd. St. Mtn Ca.
~TI) 17/74 There is a total of 205 square feet of vertical surface in this section, of which 95 square feet is not accessible for weld inspection.
Of the 279 welds inspected on the vertical surfaces, the following were found to be defective:
Weld No. Defect Description 060-A WS-1-NU-C W70G. Incomplete fusiod on the last 1/4" of the 2 1/2" long weld. The weld length minimum length is 1 inch.
055-R WS-1-NU-C W70G. Incomplete fusion. The repair did not include welding.
061-R WS-1-NU-C. W70G. Incomplete fusion. The repair did not include welding.
063-R WS-1-NU-C, W70G. Incomplete fusion.
064-A WS-1-NU-C, W70G. A tack weld was left between two welds of adequate size, length & spacing.
() MB5, 6 & 7 There is a total of 298 square feet of vertical surface in this section, of which 79 square feet is not accessible for weld inspection.
Of the 447 welds inspected on these vertical surfaces, the following were found to be defective:
Defect Description Weld No.
6-204A WS-1-NU-C W70G. Incomplete fusion.
5-214R WS-1-NU-C, W70G. Two fillets 3/16" x 1" are missing.
MB8 There is a total of 175 square feet of vertical surface in this section, of which 28 square feet is not accessible for weld inspection.
Of the 378 welds inspected on these vertical surfaces, the following were found to be defective:
Weld No. Defect Description
. C, 265-R WS-1-NU-C, W70G. Incomplete fusion.
264-R WS-1-NU-C, W70G. 3/16" x 1" fillet missing.
202-A WS-1-NU-C W70G. Fillet size 1/8" rather than 3/16" 203-A WS-1-NU-C, W70G. Fillet size 1/8" rather than 3/16"
O When we complete the inspection of the other sections of the Main control Boards, we will determine a percentage of defects which will be applied to the inaccessible areas. This percentage will include an appropriate safety factor. Analysis will then be used to determine acceptability of the inaccessible areas.
Richard Morrow Q.A. Manager Custom Panels Division 6LdE C,t b Ugliti[s Northeas Millstone Unit 3 Os y a b c _
Mark No.3M6# /#O3 I l 7 Mfg. Reliance Electric Co.
4900 Lewis Rd. St. Mtn. Ga.
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Attentiost Mr. Georga a=r1=r .
Subject:
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, ~ During our' inspection of the Maia control Boards, it was deter =f aad l that the weld areas that were inacessaible were prada=hatly in the rear of l ,
the boards frequent.ly covered by the sub-panels and the wireways. The type l i
of weld hiidea behind these ebetructions is the fillet weld joining the stiff-ener(e) to the penal skia and fully described la our drawing No. WS-150-4.
N inspectiam of these typical joista revealed that the walds are oversised (1/4" rather than 1/8") and longar la lamath (11/2" to 2" rather thes 1")
than the =1=f- Armspectise rguirement:a.
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h analyttral evaluarica of these welds was done using both the ;
l 1/4" and the 1/8" fillet sige. aed in all but one fastanca, the 1/8" sise wslda analysed. possessed sufficient margins of safety under the desig.
basis loading condition. N 1/8" sise weld judged to be M pts was sely .975" long campared to the =f nt===g requirsummt of oma tech langth (weld ar.omaly ammbec 007A MD-1). .
t As sock. if fifty percent of the weld area of a 1/4" aise fillet weld is missing, or every othat weld is bad. the remaining us1dm would still preseos sufficient structars1 istogrity weder the worst case ==f ==fr loading ecaditinm. .
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- Our Kaspectica of the main boards also revealed that most of these defects were readamly spread out throughout the control board and addittomally j mo two. ces bundred percest rejectable welds were found side by side. Saeed a
on our previously submitted statistical evaluation as the sapected aunbar of
), defects, and the store described evaluattaa Saliance feels that there are act F any significan: number of taurassible weld defects that woeld comerce.ine tha j aafsty and perforasace of the boards.
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