|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20112G3871996-06-0404 June 1996 Potential Part 21 Rept Re Capscrews W/Trace Code of K7 Mfg by Cardinal Industries (Now Known as Accutech) & Distributed by Energy & Process Corp for Plant CP S/N 0194012.Pump/motor Would Remain Operational Throughout Worse Case Scenario 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 ML20086G2931991-11-21021 November 1991 Part 21 Rept Re Failure of Model 763 & 763A Static Pressure Transmitters.Caused by Short Circuit in Connector Pin to Adjacent Mounting Screw.Engineering Drawings & Mfg Work Instructions Changed & Stock Purged of Subj Transmitters ML20059N5191990-10-16016 October 1990 Part 21 Rept Re Rod & Bearing Assembly Failures Noted by Wolf Creek Nuclear Operating Corp During Testing.Rept Will Be Issued Outlining Root Cause & Corrective Actions to Prevent Recurrence 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 ML20246J0631989-08-29029 August 1989 Part 21 Rept Re Namco Refusal to Certify Design & Matls for Replacement Namco Limit Switches Supplied by Masoneilan. Initially Reported on 890825.Switches Put on QC Hold Until Final Disposition of Switches Determined ML20244D2901989-06-0101 June 1989 Part 21 Rept Re Buchanan 724 Terminal Blocks Supplied by Limitorque Corp,Rather than Correct Buchanan 524 Terminal Blocks.Caused by Error in Order Processing.Training Held to Ensure That Procedures Followed Correctly ML20235Y4811989-03-0303 March 1989 Part 21 Rept Re Cracked Welds Discovered on Striker Plates of GE Circuit Breakers.Initially Reported on 890130.GE Advised Util That Striker Plates Subj to Impact Loading Only When Breaker in Racked Out & Operated in Test Position ML20195F6191988-11-18018 November 1988 Part 21 Rept Re GE Magne-Blast Circuit Breakers.Initially Reported on 881116.Welds on All safety-related Breakers Will Be Repaired Prior to Entry Into Hot Shutdown ML20151W7841988-08-16016 August 1988 Part 21 Rept Re Cracking of Slides Used in Four Way Valves Furnished on Actuators for MSIVs Due to Brazing/Heat Treating of Slide Matl.All Sites Using Actuators Will Be Formally Notified by 880826.List Encl ML20151B4291988-04-0101 April 1988 Part 21 Rept Re Inconsistencies in Gould,Inc Certificate of Compliance Received W/Class 1E Fuses Procured from Planned Maint Sys Due to Fuses Not Being Qualified for Certain Specs.Initially Reported on 880329.Fuses Remain on Hold ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station 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 ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20117B8141985-05-0101 May 1985 Part 21 Rept Re Ruskin Fire Dampers Installed at Facility. Initially Reported on 850426.Fire Dampers Found in Discrepant Condition Will Be Reworked in Order to Assure Integrity & Proper Functioning ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20116D3201985-04-22022 April 1985 Part 21 Rept Re Ruskin Mfg Co Welds Used to Join Damper to Damper & Damper Section to Mullion Plates.Welds Not in Accordance W/Approved Design Drawings.Drawing 5415 Revised to Indicate Weld Spacing.Drawing of Weld Spacing Encl ML20115J1361985-04-15015 April 1985 Forwards Insp Procedure for Investigating Emergency Diesel Generators for Fractured or Cracked Welds to Determine If Part 21 Problem Exists,Per Jg Borman ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed NRC-85-3024, Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware1985-03-22022 March 1985 Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware ML20102B9531985-02-13013 February 1985 Supplemental Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213. Coated Concrete Surfaces Inside Containment Will Perform Satisfactorily Under DBA Conditions ML20107B6931985-02-0707 February 1985 Final Deficiency Rept (53564-K161) Re Uncertainties in Resistance Temp Detectors Calibr.Westinghouse Evaluation Demonstrated That Revised Resistance Temp Detectors Uncertainty Acceptable ML20101T1211985-01-25025 January 1985 Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213.Destructive Adhesion Tests Performed on Locations Selected by Sampling Plan to Verify Acceptability of Coatings ML20104B1471985-01-18018 January 1985 Final Deficiency Rept Re Insp of Structural Steel Welds. Initially Reported on 840918.Structural Concerns Identified & Corrective Action Repts Issued to Have Shims Less than 1/4 Inch Thick Placed Flush W/Mounting Frame ML20104A8671985-01-13013 January 1985 Final Deficiency Rept Re Standby Diesel Generator B Left Bank Turbocharger.Initially Reported on 840504.Caused by Loose Lock Nut on Left Bank Turbocharger Lubricating Oil Pump Centrifuge.Damaged Turbocharger Repaired & Inspected ML20104A8171985-01-13013 January 1985 Final Deficiency Rept Re Subcooling Core Monitor Alarm & Caution Relays.Initially Reported on 840821.Interposing Relays & Diodes Added to Sys to Minimize Potential for & Suppress Effects of Any Arcs Generated ML20114C9141985-01-13013 January 1985 Final Deficiency Rept (53546-K158) Re ASME Hangers & Component Supports.Initially Reported on 841212.Insulation Contractors Revised Procedures & Retrained Personnel to Preclude Further Tampering of Supports ML20104B9241985-01-13013 January 1985 Final Deficiency Rept Re Water Damaged Limitorque Motor Operators.Initially Reported on 840203.Caused by Leakage During Sys Flushing & Hydrostatic Testing Activities.Seals Added Inside Conduit & T-drains Installed in Operator ML20114D1081985-01-13013 January 1985 Final Deficiency Rept (53564-K118) Re safety-related Field Procurement by Constructor.Initially Reported on 840103. Complete Review of Constructor safety-related Purchase Orders Completed.All Nonconformance Repts Resolved ML20114C8441985-01-13013 January 1985 Final Deficiency Rept Re Microbiologically Induced Corrosion in Hxs.Initially Reported on 840601.All HXs Utilizing Lake Water for Cooling Medium Eddy Current Inspected for Microbiologically Induced Corrosion ML20114C7981985-01-13013 January 1985 Final Deficiency Rept Re Removal & Replacement of ASME Components in Support of Cleaning & Flushing Activities. Initially Reported on 840711.Investigation Into Handling & Storage of ASME Components Removed from Sys Conducted ML20112D8061985-01-0404 January 1985 Final Deficiency Rept Re MSIV Lockwashers.Initially Reported on 841207.Lockwashers Installed Via Startup Field Rept I-SU-122 & Will Be Completed Prior to Fuel Load ML20112F5421985-01-0303 January 1985 Forwards Dec 1984 Status Rept Re 10CFR50.55(e)/Part 21 Open Items RBG-19-803, Final Deficiency Rept DR-234 Re Short Cap Screws,Shallow Bolt Holes,Damaged Dowel Pins & Damaged or Missing Lock Devices for Hanger Block Bolts in Check Valves Supplied by Velan Engineering,Ltd.Initially Reported on 8411281984-12-28028 December 1984 Final Deficiency Rept DR-234 Re Short Cap Screws,Shallow Bolt Holes,Damaged Dowel Pins & Damaged or Missing Lock Devices for Hanger Block Bolts in Check Valves Supplied by Velan Engineering,Ltd.Initially Reported on 841128 ML20101N0481984-12-0707 December 1984 Final Deficiency Rept Re RCS Resistance Temp Detector Calibr Data.Initially Reported on 840801.Manufacturer Calibr Procedures Revised to Allow Recalibr at Facility.All Resistance Temp Detectors Will Be Replaced or Refurbished ML20101K8531984-12-0707 December 1984 Final Deficiency Rept Re Certification of Lead Auditor for Technical Metals,Inc.Initially Reported on 840524.Samples from Production Lots Remaining in Site Warehouse Chemically Analyzed & Found Acceptable ML20101L5631984-12-0707 December 1984 Supplemental Final Deficiency Rept Re Installation of 3-h Rated Hollow Metal Fire Door Frames.Initially Reported on 840525.Existing Caulking Replaced W/Approved Flame Retardant Adhesive Sealant ML20101N1871984-12-0707 December 1984 Final Deficiency Rept Re Heat Numbers W/More than One Pipe Schedule.Initially Reported on 831213.Two Piping Spool Pieces Replaced W/Correct Schedule of Pipe.Exam of All Installations of Subj Heats Revised to Prevent Recurrences ML20101L3591984-12-0707 December 1984 Final Deficiency Rept Re Lubricating Oil Piping Sys for Safety Injection Pumps & Centrifugal Charging Pumps. Initially Reported on 840717.Replacement of safety-related Equipment W/O QA Program Will Be Repeated Per QA Program ML20101M1031984-12-0707 December 1984 Final Deficiency Rept Re ITE-Gould Containment Cooling for Mechanical Interlocks.Initially Reported on 840316. Instruction Manual Revised to Change Installation Instructions of Size 5 Mechanical Interlock Assembly ML20101D3011984-12-0505 December 1984 Forwards Status Rept for Oct & Nov 1984 Re 10CFR50.55(e) & Part 21 Items ML20100R5131984-12-0101 December 1984 Final Deficiency Rept Re Standby Diesel Generator Lube Oil keep-warm Pumps Supplied by Crane-Deming.Pumps Will Be Designed for Reliability.Interim Pumps Reliable for Use Until ASME Rated Pumps Available ML20100C1161984-11-19019 November 1984 Deficiency Rept Re Pressurizer PORVs Preoperational Test Discrepancies.Special Operations Procedure Will Be Performed to Resolve Existing Test Discrepancies ML20099K7801984-11-16016 November 1984 Final Part 21 & Deficiency Rept Re Turbine Driven Auxiliary Feedwater Pump Governor Valve Stem Guide Bushings.Initially Reported 841017.Investigation Revealed That Defictive Parts Described by Terry Corp Installed at Facility ML20099K8291984-11-13013 November 1984 Final Part 21/deficiency Rept Re Pressurizer PORV Failing to Close During Preoperational Test.Initially Reported 841011. Resolution Will Be Provided by 841119 ML20099H1601984-11-0909 November 1984 Final Deficiency Rept Re ex-core Neutron Detector Field Cabling.Initially Reported on 841009.All Damaged Triaxial Cables & Connectors Repaired &/Or Replaced.All Insulation Panels Verified to Be Properly Reinstalled 1996-06-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195D1791998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Wolf Creek Generating Station.With ML20154L4591998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Wolf Creek Generating Station.With ML20153G2771998-09-30030 September 1998 Rev 1 to WCAP-15079, Wolf Creek Heatup & Cooldown Limit Curves for Normal Operation ML20153G2851998-09-30030 September 1998 Rev 1 to WCAP-15080, Evaluation of Pressurized Thermal Shock for Wolf Creek ML20153G2691998-09-30030 September 1998 Rev 1 to WCAP-15078, Analysis of Capsule V from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20153G7301998-09-23023 September 1998 Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated ML20151W1491998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Wcgs.With ML20237B7381998-08-14014 August 1998 Special Rept 98-001:on 980615,oxygen Analyzer on Wgs Was Declared Inoperable.Wgs Oxygen Analyzer OARC-1119A Was Indicating 0 Ppm on 980814 & Fluctuated Between 200 & 900 Ppm on 980615.Completed Work Order & Declared Wgs Operable ML20237B0841998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Wolf Creek Generating Station ML20236P3441998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Wolf Creek Generating Station ML20236P3481998-05-31031 May 1998 Corrected Page of MOR for May 1998 for Wolf Creek Generating Station ML20249A0171998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Wolf Creek Generating Station ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247H0901998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Wolf Creek Generating Station ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20216F6101998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Wolf Creek Generating Station ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20216G1971998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Wolf Creek Nuclear Operating Corp ML20202H0721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Wolf Creek Generating Station ML20217G4311997-12-31031 December 1997 Western Resources 1997 Annual Rept & Financial Statements for Years Ended 971231 & 1996 for Ks Electric Power Cooperative,Inc ML20203H0151997-12-31031 December 1997 Annual Operating Rept 13 for Jan-Dec 1997 ML20217G3711997-12-31031 December 1997 Kansas City Power & Light Co 1997 Annual Rept ML20216D7771997-12-31031 December 1997 Annual SER 12 for Jan-Dec 1997, for Wolf Creek Generating Station 1999-09-30
[Table view] |
Text
. - -
7 ,,--. . n-.
3 -
- f_ b WipLF CREEK NUCLEAR OPERATING CORPORATION .
p C Bart D. Withers pr w.n.no August 29, i989 g WM 89-0218 i.
'U. S. Nuclear Regulatory Commission
' ATTN: Document Control Desk Mail Station F1-137 Washington, D.' C.,20555-
, _R. D. Martin, Regional Administrator i .U.:S. Nuclear Regulatory Commission Region'IV, 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Subject:
Docket No. 50-482: 10 CFR 21 Notification Concerning; Masonellan Certification of Replacement Electrical Parts
~
Gentlemen This letter is b'eing submitted pursuant to 10 CFR 21.21(b)(2) as a follow-up to. a telephone call between K. R. Petersen, Wolf Creek Nuclear Operating
-Corporation (WCNOC) and D. M. Hunnicutt, NRC on August 25, 1989.
s WCNOC has determined that Masoneilan could not provide a basis for-certifying conformance to WCNOC purchase order requirements for certain spare / replacement electrical parts for nuclear service control; valves. As explained in the attached evaluation, this deviation is considered to be reportable as a defect pursuant to 10 CFR 21.
If you have any questions concerning this matter, please contact me or Mr. O. L. Maynard of my staff.
cz Very truly yours, i:
Bart D. Withers President and Chief Executive Officer BDW/jad Attachment cet B. L. Bartlett (NRC), w/a E. J. Holler (NRC), w/a
~D. V. Pickett (NRC), w/a d
I P.O. Box 411/ Burlirgton, KS 66839 / Phone: (316) 364-8831 I
?l?%88U M8FDC % ~ ~ c~ ~~
3
e Attachment to WM 89-0218 Page 1 of 2 10 CFR 21 Notification Concerning Masoneilan certification of Replacement Electrical Parts In 1988, Wolf Creek Nuclear Operating Corporation (WCNOC) attempted to procure spare NAMCO limit switches (model EA170-51100) from Masoneilan. When Masonellan placed the order with NAMCO for the model EA170-51100 switches, NAMCO refused to certify the switches as being similar in design and materials to the switch ordered in the construction of Wolf Creek Generating Station (WCGS). NAMCO informed Masonellan that NAMCO model EA170-51100 was not the correct model designation for the equipment being purchased and that the switch that was qualified was model EA170-51302. NAMCO could not certify the model EA170-51100 switch as a replacement switch because of a lack of traceability for the standard off the shelf switches. NAMCO stated that there is no Appendir B control of drawings and bills of materials for the standard switches. Masonellan conveyed this to WCNOC along with the fact that Masoneilan had previously certified similar spare switches (model EA170-11100) fcr use at WCGS.
Upon discovery of this situation, WCNOC reviewed the procurement history of limit switches supplied by Masoneilan. During the construction phase at WCCS, several control valves were procured from Masoneilan (Dresser Industries, Inc. , Hasonellan North American Operations, 85 Budwell Street, Avon, MA 02322) for use at WCGS. These control valves, which contained NAMCO lbnit switches (model EA170-11100), were environmentally and seismically qualified by Masoneilan in accordance with IEEE 323 and 344. Subsequently, model EA170-11100 NAMCO limit switches were ordered for WCGS as spares and supplied by Masonellan. Five purchase orders with Masonellan to order spare limit switches (model EA170-11100) were found in which a total of 97 switches were procured. Although, during contract negotiations, Masonellan indicated the switches were commercial grade items, Masonellan certified the switches as qualified per IEEE 323 and 344. Furthermore, this certification was to the purchase orders, which also invoked 10 CFR 50 Appendix B and 10 CFR 21. Prior to the 1988 procurement, the Masonellan program appeared to adequately control spare parts procurement. This was based on the Masonellan certification and on a sampling evaluation of Masonellan certifications during onsite audits and surveillance of other material procurement. However, based on the disclosures discussed above, coupled with results of recent WCN00 surveillance, WCNOC has determined that there is a lack of design control and material traceability associated with these switches. Therefore, WCNOC considers Masonellan's past certification of model EA170-11100 switches supplied as spares to be in error.
Further review of Masonellan procurement has determined that five of the 37 switches were issued to the field for use in four control valves. In order to determine acceptability of the switches which are installed at WCGS, an engineering evaluation was conducted to determine the acceptability of using the switches already installed in the four control valves. This evaluation determined that the installed switches were acceptable for interim use until qualified replacement switches are installed. To prevent further switches from being issued to the field, the switches procured from the five purchase orders have been put on QC hold until an evaluation can be conducted to determine the final disposition for these switches.
i
, yAtt,achment to WM 89-0218 !
Page" 2 of 2' l
Subsequent .to the discovery of the improper ' certification of NAMCO limit !
switches .by Masoneilan, WCNOC's Supplier / Materials Quality organization conducted a surveillance program on Masoncilan. WCNOC concluded thst for spare parts procured by Masoneilan and further conditioned through additional manufacturing . processes or assembly, that adequate design controls exist as verified during previous audits and surveillance. However, for. spare parts that do not require further conditioning, such as NAMCO lLait switches and ASCO solenoid valves, the controls evaluated were inadequate. The purpoes of this surveillance program was to evaluate the design and materials control of spare / replacement parts for nuclear service control valves supplied to WCGS by Masoneilan. During the surveillance program, design documents were evaluated, receipt inspection activities were witnessed, and the documentation associated-with certain procurement documents was evaluated.
This surveillance program showed that Masoneilan could not present objective evidence of design control nor provide a basis for certifying conformance to WCNOC purchase order requirements for certain spare / replacement electrical parts for nuclear service control valves. The specific parts in question are NAMCO limit switches (model EA170-11100) and ASCO Solenoid Valves. The surveillance showed that Masoneilan could show evidence of design control and a basis for certifying conformance for all other spare / replacement parts audited. and therefore corrective steps could be limited to the spare / replacement electrical parts. In older to assess the safety significance of procuring these items fran Masonellan, a review was performed by WCNOC to determine if any of the NAMCO switches or ASCO Solenoid Valve replacements were installed at WCGS. This review determined that only the five NAMCO EA170-11100 switches discussed above are installed at WCGS. The remaining NAMCO switches and ASCO Solenoid Valves have been put on hold in the warehouse to prevent them from being used in the future.
Since the electrical spare / replacement parts discussed above were incorrectly certified by NV -eilan, this situation has been determined to be a deviation from the techn. I requirements of the procurement document as defined in 10 CFR 21. As a deviation which could have created a substantial safety hazard.
i I
it is considered to be reportable as a defect pursuant to 10 CFR 21.
l l
1 l
- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _