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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 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days L-98-041, Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods1998-03-0909 March 1998 Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods L-97-059, Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 9802151997-11-14014 November 1997 Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 980215 ML20198J0431997-07-28028 July 1997 Update to Amended Interim Part 21 Rept Re Harness/Positive Plate Lug Disconnect on List Ish Round Cell Battery.Requests 7-10 Day Extension to Complete Review 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 ML20141K7741997-04-24024 April 1997 Part 21 Rept Re Auxiliary Feedwater Check Valve Failure. Concluded Thermal Gradient Conditions Created by Flowing Cold Water Through Hot Valve Created Rapid Cooldown of Seat Ring,Allowing Ring to Displace 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 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 ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20134L1081996-10-10010 October 1996 Part 21 Rept Re Defect in Component of Nordberg Model FS1316HSC Sdg.Nak Engineering,Inc Has Established & Adopted Procedures to Assemble Fuel Oil Lines & Climinate Possible Defective Condition ML20116H2031996-08-0505 August 1996 Part 21 Rept Re Potential Defect on Condition in Component of Nordberg Model FS1316HSC Sdg W/Fuel Injection Line Assembly Which Connects Fuel Pump to Injector.Caused by Loose Fuel Line Sleeve ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20112D0101996-05-30030 May 1996 Part 21 Rept Re Possible Matl Defect in Certain Stainless Steel Swagelok Tube Fittings.List of Three Addl Shipments to Nuclear Facility of Parts Included in Investigation Encl 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 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20092H3811995-09-12012 September 1995 Part 21 Rept Re Addl Defective Lot of 3/8-16x11/2 Hex Capscrews ASTM-A-193 Grade B7 from Which Orders Had Been Processed & Sold to Customers by Licensee ML20092H3761995-09-11011 September 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on Lot 3/8-24 X 2 A-193 B7 Hex Capscrews Identified by Head Markings ML20092A0361995-08-29029 August 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on 3/8-24 x2 A-193 B7 Hex Capscrews Identified by Head Markings ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51's & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20086D9901995-07-0303 July 1995 Part 21 Rept Re Two Failures of Model Vtr 500 Turbochargers Supplied by Abb Turbo Systems Ltd.Failure of Turbocharger Renders Associated EDG Incapable of Providing Rated Output. Seventeen Hole Jet Assist Wall Plates Replaced ML20082Q9491995-04-21021 April 1995 Part 21 Rept Re Notifying Commission of Potential Design Defect of Ksv EDG Sys 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 ML20072S4611994-09-0505 September 1994 Part 21 Rept Re Ssps semi-automatic Tester at Plant 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 ML20059E9081993-12-29029 December 1993 Part 21 Rept Re Decreases in Valve Actuator Motor Starting Torques Resulting from Increasing 3-Phase Actuator Motor Temp.Concludes Valves Capable of Performing Intended safety- Related Function ML20058K6431993-12-10010 December 1993 Part 21 Rept Re Potential for Unacceptable Recirculation Spray Sys Operation for Supporting Long Term Core Cooling Capability.Caused by Disc of motor-operated Valve on Suction of Pump Not Engaged to Motor Operator ML20058H0791993-12-0303 December 1993 Part 21 Rept Re BVPS Unit 2 Suction Valves for Rs Pumps Supplied by Henry Pratt Co,W/Regard to Inadequate Discharge Pressure.Temporary Mod Made to Four Affected Suction Valves Which Will Properly Position & Retain Spline Adapter 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 ML20046B1321993-07-23023 July 1993 Interim Part 21 Rept Re Decreases in MOV Motor Starting Torques Resulting from Increasing Motor Temp.Valves Mfg by Limitorque Corp.Mfg in Process of Revising Recommended Torque Degradation Calculation at Degraded Voltage ML20128H4561993-01-25025 January 1993 Followup Part 21 Rept Re Disintegration of Balston 21554-1 Automatic Drain Float & Air Piping Filter Assemblies Mfg Prior to Nov 1989.Caused by Contaminants in Air Start Sys. Customers Should Order Air Filters Mfg After Nov 1989 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 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl 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 ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20116D1241992-10-29029 October 1992 Supplemental Part 21 Rept Re Byron Jackson River Water Pump Couplings.Initially Reported on 921101.Caused by Lack of Matl Toughness.Replacement Couplings Were Screened to Insure Adequate Toughness & Purchase Spec Amended ML20101R3691992-07-0707 July 1992 Final Part 21 Rept Re Failure of Byron Jackson River Water Pump Couplings.Initially Reported on 911121.Couplings Failed in Svc Due to Lack of Toughness.Couplings Examined & Suspect Matl Removed from Svc ET-NRC-92-3707, Part 21 Rept Re Degraded Performance Condition of Westinghouse Protection Sys Overtemp Delta Temp Reactor Trip Function.Issue Not Reportable,Per 10CFR21,based on Diversity of Westinghouse Protection Sys,Per WCAP-73061992-06-15015 June 1992 Part 21 Rept Re Degraded Performance Condition of Westinghouse Protection Sys Overtemp Delta Temp Reactor Trip Function.Issue Not Reportable,Per 10CFR21,based on Diversity of Westinghouse Protection Sys,Per WCAP-7306 ML20079L8031991-11-0101 November 1991 Part 21 Rept Re 910620 Failure of Coupling in River Water Pump 1A Supplied by Byron Jackson.Caused by Mechanical Failure of Shaft Coupling.Metallurgical Analysis of Suspect Coupling Will Be Performed & Couplings Replaced 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 & ML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With L-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with 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 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr 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 ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With 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 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 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 ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 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 ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 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 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With 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 L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 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 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With 1999-09-30
[Table view] |
Text
_
E; BW!!P International, Inc.
BytOn
Jackson, 2017 canf ma _ 213 597 f171 Pumps GF/F 90051 T ew .
United ,
centrifugat- 2,3 wm Pumps Pump Dmson 22 June,1994 i
U.S. Nuclear Regidatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
This letter transmits a Nonfication ofDefects and Nonconformance in accordance with the requirements of10 CFR, Part 21. The attached Nonfication, CFRN 9402, reports a condition which affects hydraulic valve operators supplied by BWIIP.
7his transmittal completes the nonfication requirements on this issue.
Very truly yours, l
_! 2 D.A. Gibson Afanager, Nuclear Products Operations I
Attach.
l \
l cc: Air. F.J. Costanzo, bianager of Engineering 1,fr. R.D. Ilam, Afanager of Quality i Afr. K.A. Huber, Chainnan, Part 21 Evaluation Board Afr. W.A. Klenner, Product Afanager Afr. K.B. Lemmon, Afanager, Field Service Operations
pV l L/ I 9406280210 940622 PDR ADOCK 05000334 a S
l PDR f L J
~ ,
NOTIFICATION NO. CFRN-94-02 .
I NOTIFICATION OF A REPORTABLE DATE: 21 June 1994 ISSUE PURSUANT TO 10 CFR 21 TO: U. S. Nuclear Regulatory Commission j Attn: Document Control Desk Washington, D.C. 20555 NAME AND ADDRESS OF INDIVIDUALINFORMING THE COMMISSION:
Mr. David Gibson BW/IP International, Inc.
Pump Division 2300 East Vernon Avenue Vernon, CA 90058 .
(213) 587-6171 For Technical Information
Contact:
Dr. Kent Huber j BW/IP Evaluation No. CFR 94-003 IDENTIFICATION OF THE FACILITY, THE ACTIVITY, OR THE BASIC COMPONENT SUPPLIED FOR SUCH FACILITY OR ACTIVITY WITHIN THE UNITED STATES WHICH FAILS TO COMPLY OR l CONTAINS A DEFECT:
Basic Component: Replacement seals for valve hydraulie operator accumulators and cylinders. Part numbers 90433-011, 90433-015, 90433-017, 90433-025, 90433-027, 90433-041 IDENTIFICATION OF THE FIRM SUPPLYING THE BASIC COMPONENT WHICH FAILS TO COMPLY OR CONTAINS A DEFECT:
BW/IP International, Inc.
Pump Division Successor to:
BW/IP International, Inc. l Fluid Controls Division Successor to:
Borg. Warner Nuclear Valve Division 7500 Tyrone Avenue Van Nuys, CA 91409 i
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.- l NOTIFICATION NO. CFRN-94-02 NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY HAZARD WHICII IS CREATED !
OR COULD BE CREATED BY SUCH DEFECT OR FAILURE TO COMPLY:
Seals supplied were Lubrithane (Polyurethane) with a Nitrile spring. Correct material is a ,
fluorocarbon (Viton) seal with a fluorocarbon (Viton) spring. ;
The polyurethane and Nitrile materials have not been qualified for use with Fyrquel 220 MLT or Brayco 853 hydraulic fluids. Both materials are known to degrade when in contact with Fyrquel .
220 MLT hydraulic fluid. Acceptability of the Brayco 853 fluid is unknown.
The polyurethane and Nitrile materials have not been qualified for use in harsh temperature or radiation environments and may degrade and jeopardize operator function.
THE DATE ON WHICH THE INFORMATION OF SUCH DEFECT OR FAILURE TO COMPLY WAS OBTAINED:
Fluid Controls informed Pump Division on 6 June 1994 that incorrect material supply had been discovered on an unshipped order. Subsequent investigation located three earlier incidents in which incorrect material had been supplied and delivered to customer (Enertech). Details were provided to Pump Division by FAX on 14 June 1994.
i h
t IN THE CASE OF A BASIC COMPONENT WHICH CONTAINS A DEFECT OR FAILS TO COMPLY, THE ,
NUMBER AND LOCATION OF ALL SUCH COMPONENTS IN USE AT, SUPPLIED FGR, OR BEING SUPPLIED FOR ONE OR MORE FACILITIES OR ACTIVITIES SUBJECT TO THE REGULATIONS:
All components effected by this Notification were supplied to Enertech Company 2950 E. Birch St.
Brea, CA 92621 -
Sixty-eight (68) of :he items have subsuquently been delivered to the following utilities; Duke Power - Mcguire 18 pieces Commmonwealth Edison - Braidwood 7 pieces {
- Byron (pooled storage) ,
Duquesne Power & Light - Beaver Valley 43 pieces j I
i I
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NOTIFICATION NO. CFRN-94-02 THE CORRECTIVE ACTION WHICH HAS, IS BEING, OR WILL BE TAKEN: Tile NAME OF THE INDIVIDUAL OR ORGANIZATION RESPONSIBLE FOR THE ACTION: AND THE LENGTH OF TIME THAT HAS BEEN OR WILL BE TAKEN TO COMPLETE THE ACTION: ,
l Fluids Controls Division notified Enertech of the deviation on 8 June 1994.
The Pump Division will notify Enertech with the recommendation that all items supplied with incorrect material be removed and destroyed.
ANY ADVICE RELATED TO THE DEFECT OF FAILURE TO COMPLY ABOUT TliE FACILITY, ACTIVITY, OR BASIC COMPONENT THAT HAS BEEN, IS BEING, OR WILL BE GIVEN TO PURCllASERS:
Discrepant parts should be removed and destroyed.
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