ML20082D901

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

ML20082D901
Person / Time
Site:	Prairie Island
Issue date:	01/27/1995
From:	Mccullough H CRANE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-95 NUDOCS 9504110027
Download: ML20082D901 (7)

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. <

104 North Chicago Street, Jolict, II, 60431 l

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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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