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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum NSD-NRC-97-5093, Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established1997-05-14014 May 1997 Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20135E3811997-03-0303 March 1997 Part 21 Rept Re Output Drift W/Increasing Temperature on Several RTD Amplifiers Noted During Installation of RTD by-pass Mod at Station.Action to Identify All Circuit Cards W/Affected Date Codes,Identified ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML20097J6351996-01-30030 January 1996 Part 21 Rept Re Intermittent Failure of DG Relay Mfg by Amerace Electronic Components.Suspect Relays at Plants Identified & Replaced.Amerace Indicated That Operators & QC Personnel Made Aware of Need for Proper Soldering ML20096E6511996-01-18018 January 1996 Part 21 Rept Re Failure of MOV Motor Pinion Gear Mfg by Limitorque at Byron Station.Replacement & Insp Activities Initiated for Potentially Impacted Populations of MOVs at Byron & Braidwood Stations ML20094R7391995-11-28028 November 1995 Potential Part 21 Rept Re Ksv EDG Sys Mfg by Cooper-Bessemer Reciprocating Products Div,Div of Cooper Cameron Corp. Recommends That All Utils Verify Open Oil Passage in Assembly ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept ML20071J1891994-07-22022 July 1994 Final Part 21 Rept Re Cracks Found in Body to Bonnet Nuts on Copes-Vulcan Airoperated Valves.Operability Evaluation for Byron Units 1 & 2,of Affected Valves W/Nuts of Heat Numbers H & I Completed on 940622 ML20073S9541994-06-27027 June 1994 Part 21 Rept Re Incorrect Matl Supply Discovered on Unshipped Order.Pump Div Will Notify Enertech W/ Recommendation That Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20070A1441994-06-22022 June 1994 Part 21 Rept Re Conditions Which Affect Hydraulic Valve Operators Supplied by Bw/Ip to Enertech Co & Listed Utils. Vendor Will Notify Enertech W/Recommendations That All Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20127M5201992-11-24024 November 1992 Final Part 21 Rept Re Reject Lot Serial Numbers of Defective Fuel Nozzle Tips,Consisting of Corrected Page 6 of 921102 Rept Re Reject Lots for Fuel Injector Assembly ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20149H8211988-02-11011 February 1988 Final Deficiency Rept 457/87-01 Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Util Took Steps to Determine Strength of Rocker Arms.Low Strength Rocker Arms Replaced W/New Rocker Arms ML20214H8221987-05-15015 May 1987 Interim Deficiency Rept Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Test/replacement Program Started,Contingent on Receipt of Replacement Exhaust Rocker Arms from Cooper-Bessemer ML20206Q8821987-04-0202 April 1987 Interim Deficiency Rept Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Investigation Emcompasses Both Metallurgical Analysis & Mechanical Interactions.Next Rept Will Be Submitted by 870501 ML20205B6691987-03-17017 March 1987 Deficiency Rept Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Diesel Generator Repaired by Honing Out Crosshead to Crosshead Guide Clearance to 0.006 Inches.Next Rept Submitted by 870430 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 ML20207P1801986-12-29029 December 1986 Final Deficiency Rept 86-02 Re Rejectable Indications During Preservice Insp on Loop 1 Steam Generator.Actions Necessary to Resolve Items Completed,Per Suppls 1 & 2 to NUREG-1002 ML20212D9721986-12-23023 December 1986 Interim Deficiency Rept 84-14 Re Weld & Grindout Identified During Preservice Insp.Initially Reported on 841121.New Data Demonstrates That Indication Size Meets ASME Section XI 1WB-3512,1977 Edition.Indication Grindout No Longer Needed ML20215F9531986-12-19019 December 1986 Part 21 Rept Re Design Error Uncovered in Certain Safety Shutdown Circuits for Standby Diesel Generator.Switches 12E0-1,12E0-2,33E0-1 & 33E0-2 Not Intended to Initiate Emergency Mode Trip as Drawings Indicate ML20210N6561986-09-26026 September 1986 Final Deficiency Rept 85-06 Re Failure of Diesel Generators 1A & 1B to Sustain Adequate Prime During Testing.Initially Reported on 850822.Fuel Oil Sys Modified & Tested ML20210F4781986-09-17017 September 1986 Final Part 21 & Deficiency Rept 86-06 Re Fastener Matl Supplied by Cardinal Industrial Products.Initially Reported on 860617.Fastener Matl Met ASME Code Requirements. Documentation of Corrective Actions Available Onsite ML20203N1931986-09-16016 September 1986 Final Deficiency Repts 84-05 & 84-15 Re Inconsistencies in Documentation of Gk Newberg Structural Steel Installations & Welding Program,Respectively.Initially Reported on 840417. Installation Travelers Reviewed.Deficiencies Resolved ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms ML20214P5121986-09-0202 September 1986 Final Deficiency Rept 83-08 Re Fabrication of Pullman Sheet Metal Duct Fittings W/O Approved Design Documentation. Initially Reported on 830630.Unit 1 Fitting Mods Completed on 860501.Reworking of 12 Fittings Remain for Unit 2 ML20212K2741986-08-12012 August 1986 Final Deficiency Repts 84-05 & 84-11 Re Boeing Steam Generator Snubber Failure.Initially Reported on 840628. Snubber Functional Test Results Reviewed & Acceptable. Snubbers Refurbished for Listed Units ML20205F7211986-08-12012 August 1986 Revised Final Deficiency Rept 84-12 Re Removal of Name Plates from ASME Large Bore Spool Pieces.Initially Reported on 840824.Replacement Identification Plate Not Attached to Installed Spool Pieces.Procedure Revised to Reflect Change ML20212B3791986-07-29029 July 1986 Interim Deficiency Rept 86-06 Re Fastener Matl Supplied by Cardinal Industrial Products.Initially Reported on 860617. Matls Over 1 Inch in Diameter Shipped During 840109-850815 & Not Included in Notification Ltrs Acceptable ML20206B1371986-06-11011 June 1986 Final Deficiency Rept 84-04 Re out-of-tolerance Radiographic Film Densities.Initially Reported on 840406. Unit 1 Production Welds Repaired &/Or Reradiographed & Welder Qualifications Evaluated & Confirmed ML20211F1971986-06-0505 June 1986 Final Deficiency Repts 86-03 by & 86-05 Bw Re Cold Leg Safety Injection Pipe Vibration & Cracks.Initially Reported on 860430.D Loops Changed to 5-D Bends & Support Added for Addl Stiffness ML20211E3471986-06-0404 June 1986 Final Deficiency Repts 84-06(BY) & 84-14(BW) Re Large Laminar Indication in Steam Generator Snubber Piston Rod End Blade.Initially Reported on 840731.Rod End & Six End Caps Replaced ML20198E8981986-05-20020 May 1986 Final Deficiency Repts 86-01 & 86-03 Re Defective Spot Welds on Cable Tray Hanger Strut Matl.Initially Reported on 860306.Engineering Evaluation Performed for Hangers Remaining W/Suspect Control Numbers ML20210L0441986-04-22022 April 1986 Final Deficiency Repts 86-02 for Byron & 86-04 for Braidwood Re Failures of Diesel engine-generator Rocker Arm.Initially Reported on 860327 by Util & 860311 by Cooper Industries Under Part 21 ML20210E0801986-03-18018 March 1986 Final Deficiency Rept 84-17 Re Concrete Expansion Anchor Installations.Sargent & Lundy Evaluation Complete.No Significant Design Discrepancies Noted.Util Nonconformance Repts 658 & 659 Closed ML20137Z5001986-03-0606 March 1986 Interim Deficiency Rept 86-03 Re Defective Spot Welds on Cable Tray Hanger Strut Matl.Initially Reported on 860121. Unit 2 Containment Hangers Will Be Replaced & Unit 1 Hangers Will Be Repaired or Replaced ML20153F3691986-02-11011 February 1986 Interim Deficiency Rept 86-02 Re Rejectable Indications in Weld Seams of Loop 1 Steam Generator & Pressurizer.Initially Reported on 860115.Fracture Mechanics Analysis Performed. Final Rept Will Be Submitted Upon Resolution of Issue ML20153F5811986-02-11011 February 1986 Final Deficiency Rept 86-01 Re Misorientation of Burnable Poison Rods A6P2D in Westinghouse Fuel Assembly C54S. Initially Reported on 860114.Assembly A6P2D Returned to Mfg for Repair.Vendor Will Change Mfg & Insp Practices TXX-4692, Final Deficiency Rept CP-86-03 Re Sealing Techniques Used in Installation of Class 1E Instruments.Initially Reported on 860110.Seal Assemblies Provided for Class 1E Devices W/ Exception of Svc Water Intake Areas1986-02-0707 February 1986 Final Deficiency Rept CP-86-03 Re Sealing Techniques Used in Installation of Class 1E Instruments.Initially Reported on 860110.Seal Assemblies Provided for Class 1E Devices W/ Exception of Svc Water Intake Areas ML20137R7721986-01-29029 January 1986 Final Deficiency Rept 84-16 Re Adequacy of ASME Matl Procurement Documentation.Initially Reported on 841002. Review of Documentation for Approx 4,300 Heat/Lot Numbers Re Site Procured ASME Matls Complete ML20151Y3921986-01-29029 January 1986 Final Deficiency Rept 85-02 Re Tank & HX Welding.Initially Reported on 850221.Util Evaluating Westinghouse Response to Insp Results.Other vendor-supplied Items Submitted to Sargent & Lundy for Evaluation ML20137N5291986-01-21021 January 1986 Final Deficiency Rept 85-03 Re Defects Identified During Instrumentation Installation Reverification Program. Safety-related ASME Section III & Class H Instrument Installations Made Prior to Feb 1984 Reinspected ML20137G7421986-01-13013 January 1986 Final Deficiency Rept 82-07 Re Adequacy of safety-related Mechanical Equipment Installed Prior to Sept 1982.Encl Rept Documents Results of Completed Retrofit Program.Issue Closed ML20137H7241986-01-0707 January 1986 Final Part 21 & Deficiency Rept 84-10 Re Wall Thickness Inadequacies for Small Bore ASME Class Ii,Iii & Class H Piping.Initially Reported on 840720.Util & Sargent & Lundy Program Verified Acceptability of safety-related Piping Sys ML20136G5151985-11-12012 November 1985 Final Deficiency Rept 83-07 Re Matl Traceability Verification Program. Matl Traceability Verification at Braidwood, Encl ML20210A1091985-11-0404 November 1985 Interim Deficiency Rept 84-16 Re Adequacy of ASME Matl Procurement Documentation.Approx 337 Heat/Lot Numbers Needing Addl Documentation or Corrective Action to Conform W/Asme Code Resolved.Final Rept Expected in Jan 1986 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
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[ ) one First National PtapJic;go. tilinois
( O 7 AddrIss R; ply tr Post Offics Box 767 N ,/ Chicago, lihnois 60690 October 8, 1982 Mr. James G. Keppler, Regional Administrator Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Braidwood Station Units 1 and 2 Control of Mechanical Equipment Erection NRC Docket No s. 456 and 50-457 Re ferences (a): September 1,1982, letter from W. L. Stiede to J. G. Keppler.
(b): September 8, 1982, letter from R. L. Spessard to W. L. Stiede.
Dear Mr. Keppler:
On September 2, 1982, Commonwealth Edison Company notified your office of a deficiency reportable pursuant to 10 CFR 50.55(e) regarding control o f the erection of mechanical equipment at Braidwood Station. This letter fulfills the 30-day reporting requirement. For your tracking purposes this deficiency is numbered 82-07.
Description o f De ficiency A substantial number o f pieces o f safety-related mechanical equipment were erected by the mechanical installation contractor without adherence to its quality assurance procedure pertaining to this activity. The chain of events leading to this determination are described in the attachment to this letter.
Analysis of Safety Implication s Erection of mechanical equipment without adherence to the contractor's procedure could result in damage to the equipment or incorrect positioning o f the equipment. Any significant damage not detected during erection would be discovered during subsequent -
inspections and preoperational testing of this equipment. In correct positioning i
4" 8210190299 821000
[:"PDRADOCK 05000456 i g@ @ h
_s PDR !
Q$A7
J. G. Keppler October 8, 1982 of the equipment would become apparent when mechanical and electrical hookups were made. This deficiency is therefore expected to have no safety implications. To date, the reviews described below have rev.?aled no problems which would compromise the effectiveness of the mechanical equipment involved.
Corrective Action - Taken As discussed with Region III personnel on August 31 and as described in reference (a), all equipment which should have been erteted using Phillips,- Getschow Procedure QCP-8 will be rechecked ut.ing the current procedure, QCP-822. Available records will be utilized in completing " Equipment Installation Record" forms.
Other associated corrective actions taken are described in references (a) and (b) and in the attachment to this letter.
Please address further questions regarding this matter to this office.
Very truly yours, fi k e fM"~
T. R . Tramm Nuclear Licensing Administrator cc: Director of Inspection and Enforcement Attachment 5155N
x l
Atta chmen t Additional Information Regarding Braidwood Mechanical Equipment Erection Deficiency History The basic deficiency involving the lack of adequate equipment installaton/ inspection procedures was first identifed during an _ NRC inspection of the Braidwood site on February 7-9, 19 79 b y C. E. Jones and K . R. Naidu (IE Inspection Report Nos. 50-456/79-02 and 50-457/79-02). The inspector observed the installation o f the regenerative heat exchanger and the excess letdown heat exchanger in the Unit #1 Containment Building. It was observed that the typical anchor bolt projection, per design, had not been maintained when set as part of the embedment in the concrete wall. The installation of the heat exchangers was performed by by Phillips, Getscho w Co . It was noted by the inspector that one bolt on the regenerative heat exchanger was cross threaded. Discussions with the licensee and contractor personnel indicated that the installation of the heat exchangers was not complete, and the checklist to document the status of completion of safety-related equipment installed was being finalized.
The follow-up and closure of this item was documented during an NRC inspection on April 16 and 17,1980 by K. R. Naidu (50-456/80-03 and 50-457/80-3). The report states: "Phillips , Getschow Company developed Procedure PGCP-8 dated June 16, 1979 titled ' Equipment Erection Record '
with a checklist to denote the status of erection o f a given equipment".
The Phillips, Cetschow Co. Procedure PGCP-8 dated June 16, 1979 was not formally submitted to Commonwealth Edison Company until after the shutdown period (September ,1979 - March 1980) . During the shutdown period, numerous pieces of equipment were received and stored in place to help prevent degradation durig the potentially long-term storage period.
When the shutdown ended (March, 1980) and the site began to re-staff, it was obvious that a comprehensive procedure to control the installation, inspection, and status of equipment was necessary at Braidwood. The original procedure submittal of PGCP-8 dated May 27, 1980 was the first Phillips, Getschow Co. " Equipment Erection Record" procedure submitted to Commonwealth Edison and Sargent & Lundy for approval.
Commonwealth Edison Site Quality Assurance performed an audit (QA-20-80-21) o f Phillips, Getschow Company activities from June 30, 1980 to July 9, 1980. Two findings were identified concerning mechanical equipment installation:
Finding No .1: Phillips, Getschow Company has not established and implemented adequate procedures for the installation and inspection of bolted connections.
Finding No . 2 : Phillips, Getschow Company has not implemented adequate procedures for equipment installaton and installation inspection.
In regard to Finding No.1, Phillips,1Ge tschow Co'. prepared Pro-cedure PGCP-15 and formal approval' was given on October 9, 1980.- Finding -
No. I was closed.
n
'.. 4 In response to Finding No. 2,.Phillips, Getschow Co. commited to establish a "back-fit" inspection program on previously installed submitted procedure PGCP-8. On July 16, equipment.
1980, Sargentbased on the
& Lundy. recently' approval with comments" (Status 2) granted acceptance of the procedure, and on October 20,1980, final approval by Sargent & Lundy was given. A follow-up surveillance by Commonwealth
. Edison Quality Assurance on January 9,1981 concluded that the inspection program was in place and being implemented. Finding No. 2 was closed.
Another audit-(QA-20-81-22) conducted by Commonwealth Edison i Quality Assurance from June 23 to June 25, 1982 revealed one finding and one observation concerning mechanical equipment installation:
Finding No. 2: Contrary to Phillips Getschow Co. Procedure f
QCP-B4, Sections 6.1 and 6.11, eight pieces of equipment, which :
weighed in excess of 20,000 pounds, had no special lift !
procedure preseating the weight of the item, methods of i attachment, sling locations, balance points, and maximum hoist ,
line speed, i
Observation No.1: Contrary to Phillips, Getschow Co. Procedure !
PGCP-8, Section 4.3, 13 of 69 production completed Equipment !
- Erection Forms (PGCP-8-1A) sampled had not been reviewed by
Quality Control. Also, of 308 grout release forms completed, it !
is not clear that EEF's have been initiated for each case. i t
t In order to reach a mutual resolution with regard to Observation No. 1, much correspondence between Phillips, Getschow and Commonwealth Edison Quality Assurance transpired. Phillips, Getschow committed to l prepare an EER form when discrepancies are found, perform a back-fit inspection on all previously installed equipment, and provide a status log.of installed equipment. These commitments were presented on November !
'10, 1981.. Observation No. I was closed. -
On December 22 - 30, 1981, Site Quality Assurance performed a l
, surveillance (No. 2056) of equipment erection and found that the '
- requirements of Procedure PGCP-8 were met.
l On February 19, 1982, Phillips, Getschow Co. Quality Control ;
performed a surveillance of equipment erection activities, and as a ;
result of numerous deficiencias, prepared Phillips, Getschow Co. NCR No.
- 649, which states: i "1. Numerous equipment has been installed prior to im-. {
plementation of any equipment erection procedure- ;
(5/27/ 80) .
- 2. Equipment' erection records procedure has'not.been ,
properly implemented. (Production was not-routing !
EER forms to; Quality Controllfor the establish- ' i ment _of hold points.)- l
,. .i s : .- . ., ..- , . . , - - , . - - , . . . . . . , , , , . . . , - . - . . . . . , ,
7 -
?. .
- 3. We are unable to determine status of all safety-related and seismic equipment at this time.
- 4. The present PGCP-8 does not meet the requirements of ANSI N45.2.8 as required by the customer Q. A. manual."
As a result of NCR No. 649, a stop-work was placed on equipment erection by Phillips, Getschow Co. Quality Control Department. Th e corrective action defined for NCR No. 649 and approved by Commonwealth Edison Project Construction Department and Quality Assurance on Merch 26, 1982 is as follows:
"1. Revise PGCP-8 to address applicable customer requirements.
(ANSI N45.2.8) 2.- Field engineer to list all equipment we are responsible for and generate equipment erection records for all items
- 3. A complete retrofit inspection for all equipment in place to indicate status.
- 4. Implement revised procedures on equipment which remain to be erected."
Two new forms to better document equipment erection were prepared by Phillips, Getschow in conjunction with Commonwealth Edison Quality Assurance and given interim site approval on April 2, 1982. On May 13, 1982, Project Construction, with concurrence from Site Quality Assurance, forwarded guidelines to be used for the inspection and documentation of equipment installed prior to April,1982. After receipt o f the guidelines on May 13, 1982, work was allowed to proceed on a case-by-case basis.
On May 19, 1982, Quality Assurance requested Project Construction to instruct Phillips, Getschow to revise Procedure QCP-22 to include the retrofit requirements and also a schedule defining priorities of equipment that will be retrofitted. On Ma y 2 7, 1982, Project '
Construction notified Phillips, Getschow of the above mentioned requests.
A draf t copy of QCP-822 'was reviewed by Quality Assurance, and comments were forwarded to Project Construction on June 23, 1982. On August 3, 1982 Commonwealth Edison Site Quality Assurance performed a-
. surveillance (No. 2398) on equipment installation and observed the Phillip s , Getschow millwrights performing work-on equipment in violation o f. the May 13, 1982 guidelines.
On August 5, 1982, Commonwealth Edison Quality Assurance, Project Construction, and Phillips, Getschow discussed the aforementioned surveillance and finalized comments on Procedure QCP-822. Interim approval of QCP-B22 was given on August 10, 1982 and was sent to Sargent
& Lundy for. final approval on August 12, 1982.
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As documented by.the preceding chronology, it becomes apparent 7 that Commonwealth Edison Company and Phillips, Getschow Company were _ !
-involved in the. identification of the equipment installation concerns and
<took positive steps to correct the situation. We, the licensee, failed l
- to effect a timely resolution of the apparent deficiencies, but this. lack '
of timeliness did not in itself compound the problem because all work had ;
been placed under strict controls.
Subsequent Actions 4
Since the NRC Enforcement Conference at the Region III offices [
on-August 31, 1982, the following actions were taken to resolve the issue. :
On September 2, 1982, the mechanical equipment erection *
. deficiency _was reported to the NRC as a 50.55(e) report. Also, a "Secp ;
Work" order was issued to Phillips, Getschow in the area of equipment erection. Commwealth Edison Quality Assurance advised Phillips, Getschow ,
Quality Control of hold points which must be established on equipment i erection. I Phillips, Getschow Co. Procedure QCP-B22 was granted final appproval by Sargent & Lundy on September 2, 1982.
The complete list of safety-related equipment requiring l
' Equipment Installation Records (EIR) was' completed on September 2,1982. l There'are 210 pieces of equipment involved in the EIR backfit program. !
To date, 121 EIR's have been completed indicating the current status of- i installed equipment. The "back-fit" is complete on 38 items and ;
partially complete on 24 others. The remainder of the "back-fit" will be '
completed by December 31, 1982.
t l On September 3,1982 Commonwealth Edison Quality Assurance {
- notified the Phillips, Getschow Quality Control supervisor that a {
mandatory " hold point" by Commonwealth Edison Quality Assurance has been ,
I placed on all safety-related equipment installation and will remain in ;
effect until an acceptable level of confidence is achieved. j Mike Wallace was assigned as Project Manager for Braidwood l Station on September 3,1982- and reported to the site office on September !
7, 1982. Mr. Wallace's addition to the site enhanced the ability of '
Commonwealth Edison personnel 1to resolve.these issues in an acceptable and timely fashion. 'On September 18, 1982, the. Manager of Projects and
- _the ProjectLManager met with Phillips, Getschow Company Corporate i President,'Vice President,-and Quality Assurance Manager to-discuss the
, . deficiency-and. plan: appropriate actions. "
p , -On September'13, 1982i the Braidwood Pro' ject Manager formed-the l
~ Technical Support Group consisting of~three engineers to evaluate _the ;
site'with respect to the recent Enforcement Conf'rence. e At the request t
.of the Project Manager, the' scheduled fall General Office Quality' ;
Assurance audit of the Braidwood site was moved _up one month to September '
113, 1982. 'The o 'was1 lengthened.to~seven scope ofdays the audit 1was: greatly broadened and the duration l
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., 7 The Technical Support ~ Group._ started their, evaluation o f site contractors on September - 14, = - 19 82. The ' Technical Support Group increased its team to five on September 17, 1982 and added one additional member on September. 20, 1982, bringing the' group total to six engineers.
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