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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 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 ML20132D8091996-12-18018 December 1996 Part 21 Rept Re Defect of Welds on Weld Nut Holding Filter Assembly Panel.Failure of Weld or Weld Nut Could Allow Filter Assembly Panel to Break Loose Under Seismic Stress & Cause Damage to Other Components in Charger ML20082D9011995-01-27027 January 1995 Final Part 21 Rept Re Valves Installed W/Shim Between Yoke & Adapter Plate Involved in Jan 1994 Incident.Caused by Operational Problems Involving Maint Procedures.Ltr Sent to Affected Utils.Item Not Reportable Under 10CFR21 ML20080D5921994-12-28028 December 1994 Submits Followup to 940418 Part 21 Re Investigation W/ Respect to Jan 1994 Incident at Prairie Island Generating Plant Involving Crane Design Gate Valves ML20072S9581994-08-30030 August 1994 Part 21 Rept Re Crane Design Gate Valves Involved in Jan 1994 Incident at Praire Island Nuclear Generating Plant. Historical Records Do Not Contain Info Addressing Total Number of Configuration Mfg by Crane ML20065G4671994-04-0101 April 1994 Part 21 Rept Re Failure of Support Studs on Discharge Piping Bracket to Turbocharger That Provide Support for Air Inlet Housing 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 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 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 ML20028H3531990-12-13013 December 1990 Part 21 Rept Re Cable Assemblies Failing to Meet IEEE-383 Section 3 Flammability Tests.Results of Tests Conducted on 901206 Encl.Corrective Actions Include Applying Flame Retardant Covering to Cable or Cable Replacement NRC-90-3528, Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 9007231990-07-16016 July 1990 Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 900723 ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified 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 ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants 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 NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20132F3521985-09-26026 September 1985 Preliminary Part 21 Rept Re 3.5-inch Crack on Snubber Ball Bearing.Vendor Attempting to Have Bearing Returned for Exam & Evaluation by Skf Industries.Next Rept Will Be Submitted When Significant Info Available ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML20135D4481985-08-15015 August 1985 Part 21 Rept Re Raychem auto-trace 20PTV1 self-regulating Electric Heat Tracers & Associated Derivatives.Licensees Advised of Problem & Procedures to Determine Any Effect on Operation ML20129J7381985-06-24024 June 1985 Part 21 Rept Re Auto-Trace 20PTV1,self-regulating Electric Heat Trace,W/Lower than Specified Power Output.Deficiency Could Result in Lower Maint Temp in Electric Pipe Heating Sys.Affected Licensees Identified ML20094S4971984-08-16016 August 1984 Part 21 Rept Re Separation of Rod Eye Connected to Piston Rod from Threaded Portion of Piston Rod at Approx 750,000 Lb Stress Load.Caused by Insufficient Matl Thickness to Withstand Faulted Load.Matl Certification Encl ML20092L1421984-06-21021 June 1984 Part 21 Rept Re Static Load Rating on Anker-Holth,Baxter Hydraulic Suppressor.Caused by Failure of Torrington self-aligning Ball Bushing.Recommends Replacement W/ Paul-Monroe Hydraulics Part PA-89492 & PA-89493 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data 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 ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30
[Table view] |
Text
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JL'h ( t. L 644 34 CRAN....J> E l NUCLEAR OPERATIONS e 104 NC ;TH CHICAGO Si AEET
- JOU('T. IL 00431 CRANE VALVES _. - - - _ . _ .
January 27,1995 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
FINAL REPORT ON 10 CFR PART 21 EVALUATION OF CRANE VALVES INSTALLED WITH SHIM BEW/EEN YOKE AND ADAPTER PLATE.
' REF: A.) Crano Letter dated August 30,1994 B.) Northern States Power Letter to the NRC Dated April 18,1994 Ladios/Genticmon:
- 1. FINAL REPORT:
As outlined in our August 30,1994 letter, Crano Valves Nucicar Oporations (CVNO) undertook an evaluation of the design of cortain Crano Gr.to Valves. One of these valves was involved in a January 1994 incident at the Prairic Island Nuc! car Generating Plant. Details of that incident are contained in the correspondonce referenced above (B).
- 11. BACKGROUND:
i A Containment Isolation Valvo at the Prairic Island Nucioar Plant was damagod as a result of operational problems involving maintenanco procedures. Dotails of the incident have been reported to the NRC via Prairio Island's Docket Nos. 50 282 and 50 306 and associated NRC Inspection Report Nos. 282/94002 and 306/94002. Tho valve in question was a Crano 10", Figure 63174.
Tho extraordinary conditions experienced by the valvo during the event resulted in a failure of the welds joining the yoke and adapter plate and more catastrophic failure to other valve parts. Valvo drawings reviewort as part of the ovaluation did not explicitly indicato that shims had been installed between the yoko and the adapter plate.
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SUBJECT:
FINAL REPORT ON 10 CFR PART 21 EVALUATION OF CRANE VALVES INSTALLED WITH SHIM BETWEEN YOKE AND ADAPTER 1 PLATE.
Pago 2 CVNO assisted the utility in identifying other valves of the same design ,
for existence of shirns and in evaluating the adequacy of the attachment wolds on valves with shims. It was concluded that a substantial safety ;
hazard docs not exist at the Prairic Island Nuclear GeneratinD Plant based j on the walk down that was performed and additional analytical ovaluations of the as built valve characteristics. .
Ill. RESULTS OF EVALUATION:
As part of the evaluation CVNO retrieved documents located in archivos stored in a Crane facility in Pennsylvania. Tho valves at the Prairic Island i Nuclear Generating Plant were produced by Crano as part of an order for !
Westin0 house Electric in the early 1970's.
CVNO has also contacted Westinghouse Electric's NATD EngineerinD i Technology Dopartment concerning their Decernber,1969, P.O. 546 CAK- ,
116878 DN on which the valves in question were purchased from Crano !
Company. Westinghouse Electric Corporation in turn supplied tho valves to a number of nuclear utilities, some records for which have been -
retrioved from Crano archives. The records reviewed contained no information on the addition of shims. This order was placed prior to 10 CFR 50, Appendix B being issued. t On August 23,1994, CVNO sent a letter to utilitics identified as having been supplied with the valves. Each utility was offered assistance in evaluating the condition of the hardware and in performing any analytical .
cvaluations to determino if potential safety hazards exist. Valves of the l G3174 design were supplied in 10" and 12" sizes.
Historical records contain neither information on the total number of valves of this configuration manufactured by Crane, nor on their application throughout the industry. Attachment 1 identifics the utilitics that woro contacted. Four utilitics responded formally to CVNO therchy facilitatinD technical discussion and additional analytical support. No ;
substantial safety hazards were identified as a result of those technical discussions or analytical support efforts.
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-SUHJECT: FINAL REPORT ON 10 CFR PART 21 EVALUATION OF CRANE VALVES INSTALLED WITH SHIM BETWEEN YOKE AND ADAPTER PLATE.
Pago 3 IV. CONCLUSION:
Crano suppfled 10" and 12" Gate Valves, Figurc 63174 to Westinghouso Electric in the early 1970's for nuclear stations. As a result of an operational problem involving maintenance proceduros at a nuclear generating station that utilized this valvo design, the welds joining the yoko and adapter plato failed followed by additional damage to other valvo operator assembly parts. This incident did not constitute a substantial '
. safety hazard.
An ovaluation of the original valve order retrieved from Crano archivo records identiflod many of the utilities to whom valves, purchased by Wostinghouse Electric, were shipped. This enabled CVNO to send a special letter to those utilitics discussing the incident, providing a technical discussion, and offering analytical engineering support.
Analysis of the as built valvo configurations brought to CVNO's attention indicatos there is adcquato thrust capacity with respect to design basis.
Ba. sed on its evaluation of this matter, and given the relevant facts and circumstances, CVNO concludes that the valve design of Figurc G3174, when installed and operated proporly does not constitute a reportablo Itom under 10 CFR Part 21.
Should you have any questions or request additionalinformation, pleaso contact mo at (815) 740 7571. ;
Sincoroly,
^7 'A 3 b ,Ff-Henry G.L. McCullough, P.E. l Mannuor of EngineeringIQuality l 1
HGMcClcs cc: J. Algozino P. Hundt J. Carlson B. Harry Filo attachments
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Attachntent Nainex / Address of Recipients of August 23,1994 Letter Heaver Valley Power Station Kewaunce Nuclear Power Plant SHH-3 Wisconsin Public Service Corp.
Dugnesne Light Conspany N 490 !!wy 42 JY) Box 4 Kewaunee, WI 54216 Shippingport, PA 15077 A *11N: Air. Neil biorrison A YIN: bir. Larry L Limberg Senior lingineer hiainteno.sce Engineer Diablo Canyon Power Plant AIC N-50 Public Service Electric & Gas Company Pacific Gas & Electric Co.
~ PO Box 56 PO Box 236 Avila Beach, CA 93424 IIancocks Bridge, NJ 08038 ATIN: Air. Don Bauer ATJN: Mr. Robert S. Lewis ~
Senior Staff Engineer Corporate Office HR SA Tennessee Valley Anthority 1101 Afarket St.
Chattanooga,1N 37402-2801 i
A 1* TN: Mr. Michard G. Siminans Prograin hinnager, Valve.s innsbrook Technical Center Virginia Power Cornpany 5000 Dorninion HinL ,
Glen Allen. VA 23060 .
l ATIN: Ms. Parnela E. Detine Project Engineer
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. CRANE. I Cl(ANE VAI,VES NUCI,EAll OPEl(ATIONS TEI,ECOPIElt TRANSMITTAL. <
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NUCLEAR OPERATIONS 104 NOAfH CH!CAGO SMtEET
- JOUE T.it. 00431 CftANE VAi,VE S
- August 23,1994 Kewannee Nuclear Power Plant Wisconsin Public Service Corp.
N 490 liwy 42 Kewanner, WI S4216 9510 Gentlemen:
In January of this year a containtnent isolation valve at the Prairie Island Nuclear Station was dantaged as a result of operationalproblems involving snaintenance procedures.
Details of the event have been reported to the NRC via 14airie Island's Docket Nos. $0-282 and 50-306 and associated NRC Inspection Report Nos. 282M4002 and 306/94002.
The valve in question was a Crane 10' Figure 63174 and during the course of the investigation, it was discovered that, centrary to information shown on the valve assembly drawing, shirns were installed F:iwcen the yoke and the adapter plate. The extraordinary conditions experienced b;: :ne valve during the event resulted in failure of the weldsjoining the yoke and adapter plate and more catastrophicfailure to the other valve parts. \
l Crane assiard the Utility in evaluating additional valves of the same design for evidence of \;
the existence of shhns andfor the adequacy of the attachment welds where shhns did exist.
11 was concluded that a substantial safety hatard did not exist at the Prairie Island plant, based on the walk-down that was performed and additional analytical erahtations of the ns-built valve characteristics.
Since that incident Crane has conducted additional evaluations, including a search of nichives stared in a Granefacility in Pennsylvania. The valves at the 11airie Island plant were part of an order produced by Cranefor Westinghouse Electric in the early 1970's.
Although the records retrieved contained no information to support the addition of shims to the design, the records indicate that valves of the Figure 63174 design were supidied to you on that same Westinghouse order.
Crane requests your cooperation in deterrnining of those valves are in your systent. We will be glad to assist you in crahtuting the condition of the hardware and in perforndng any analytical evaluations to determine if safety ha:ards exist. Valves of the 63174 design were supplied in 10" and 12" sizes.
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You have been contacted based upon your affiliation dith the Afotor Operated Valve ther's Group and its hiernber Roster.
We appreciateyour cooperation in channeling this conununication to the appropriate penannel at yourfacility.
Your questions can he directed to the writer or to our hianager of Developinent Engineering, hit. litace Harry (who perfornted the initial on-site evahtation at Prairie Island) or Afr. David Dnyer, our Analytical Project Engineer, who has paid subsequent visits to the Prairie Island plant. Our general nutnber in Joliet is 815 727 260l).
Very *1>uly Yours, R.E llornyak ofanager QA/ Support Engineering R Fil/lik cc: J. Carlson K. IIutchinson
]!.11arry D. Dayer W
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