United States Nuclear Regulatory Commission - Protecting People and the Environment

ACCESSION #:  9504110027

                                                 TELEPHONE (815) 727-2600
                                                     POST OFFICE BOX 3339
                                                         JOLIET, IL 60434
          
CRANE          NUCLEAR OPERATIONS

CRANE VALVES            104 NORTH CHICAGO STREET       JOLIET, IL 60431

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 BETWEEN YOKE AND ADAPTER PLATE.

REF:      A.)  Crane Letter dated August 30, 1994
          B.)  Northern States Power Letter to the NRC Dated April 18,
               1994

Ladies/Gentlemen:

I.   FINAL REPORT:

     As outlined in our August 30, 1994 letter, Crane Valves Nuclear
     Operations (CVNO) undertook an evaluation of the design of certain
     Crane Gate to Valves.  One of these valves was involved in a January
     1994 incident at the Prairie Island Nuclear Generating Plant. 
     Details of that incident are contained in the correspondence
     referenced above (B).

II.  BACKGROUND:

     A Containment Isolation Valve at the Prairie Island Nuclear Plant
     was damaged as a result of operational problems involving
     maintenance procedures.  Details of the incident have been reported
     to the NRC via Prairie Island's Docket Nos. 50-282 and 50-306 and
     associated NRC Inspection Report Nos. 282/94002 and 306/94002.  The
     valve in question was a Crane 10", Figure 63174.

     The extraordinary conditions experienced by the valve during the
     event resulted in a failure of the welds joining the yoke and
     adapter plate and more catastrophic failure to other valve parts. 
     Valve drawings reviewed as part of the evaluation did not explicitly
     indicate that shims had been installed between the yoke and the
     adapter plate.


SUBJECT:  FINAL REPORT ON 10 CFR PART 21 EVALUATION OF CRANE VALVES
          INSTALLED WITH SHIM BETWEEN YOKE AND ADAPTER PLATE.


Page 2

     CVNO assisted the utility in identifying other valves of the same
     design for existence of shims and in evaluating the adequacy of the
     attachment welds on valves with shims.  It was concluded that a
     substantial safety hazard does not exist at the Prairie Island
     Nuclear Generating Plant based on the walk-down that was performed
     and additional analytical evaluations of the as-built valve
     characteristics.

III. RESULTS OF EVALUATION:

     As part of the evaluation CVNO retrieved documents located in
     archives stored in a Crane facility in Pennsylvania.  The valves at
     the Prairie Island Nuclear Generating Plant were produced by Crane
     as part of an order for Westinghouse Electric in the early 1970's.

     CVNO has also contacted Westinghouse Electric's NATD Engineering
     Technology Department concerning their December, 1969, P.O. 546-CAK-
     116878 BN on which the valves in question were purchased from Crane
     Company.  Westinghouse Electric Corporation in turn supplied the
     valves to a number of nuclear utilities, some records for which have
     been retrieved from Crane 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.

     On August 23, 1994, CVNO sent a letter to utilities 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 evaluations to determine if potential
     safety hazards exist.  Valves of the 63174 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 identifies the
     utilities that were contacted.  Four utilities responded formally to
     CVNO thereby facilitating technical discussion and additional
     analytical support.  No substantial safety hazards were identified
     as a result of those technical discussions or analytical support
     efforts.


SUBJECT:  FINAL REPORT ON 10 CFR PART 21 EVALUATION OF CRANE VALVES
          INSTALLED WITH SHIM BETWEEN YOKE AND ADAPTER PLATE.

Page 3

IV.  CONCLUSION:

     Crane supplied 10" and 12" Gate Valves, Figure 63174 to Westinghouse
     Electric in the early 1970's for nuclear stations.  As a result of
     an operational problem involving maintenance procedures at a nuclear
     generating station that utilized this valve design, the welds
     joining the yoke and adapter plate failed followed by additional
     damage to other valve operator assembly parts.  This incident did
     not constitute a substantial safety hazard.

     An evaluation of the original valve order retrieved from Crane
     archive records identified many of the utilities to whom valves,
     purchased by Westinghouse Electric, were shipped.  This enabled CVNO
     to send a special letter to these utilities discussing the incident,
     providing a technical discussion, and offering analytical
     engineering support.  Analysis of the as-built valve configurations
     brought to CVNO's attention indicates there is adequate thrust
     capacity with respect to design basis.  Based on its evaluation of
     this matter, and given the relevant facts and circumstances, CVNO
     concludes that the valve design of Figure 63174, when installed and
     operated properly does not constitute a reportable item under 10 CFR
     Part 21.

Should you have any questions or request additional information, please
contact me at (815) 740-7571.

Sincerely,


Henry G.L. McCullough, P.E.
Manager of Engineering/Quality

HGMcC/cs

cc:  J. Algozino
     P. Hundt
     J. Carlson
     B. Harry
     File

attachments


Attachment

         Names / Address of Recipients of August 23, 1994 Letter

Beaver Valley Power Station             Kewaunee Nuclear Power Plant
SEB-3                                   Wisconsin Public Service Corp.
Duquesne Light Company                  N 490 Hwy 42
PO Box 4                                Kewaunee, WI 54216
Shippingport, PA 15077

ATTN:          Mr. Neil Morrison        ATTN:     Mr. Larry L. Limberg
               Senior Engineer                    Maintenance Engineer

Diablo Canyon Power Plant               MC N-50
Pacific Gas & Electric Co.              Public Service Electric & Gas
                                         Company
PO Box 56                               PO Box 236
Avila Beach, CA 93424                   Hancocks Bridge, NJ 08038

ATTN:          Mr. Don Bauer            ATTN:     Mr. Robert S. Lewis
                                                  Senior Staff Engineer

Corporate Office
BR 5A
Tennessee Valley Authority
1101 Market St.
Chattanooga, TN 37402-2801

ATTN:          Mr. Richard Simmons
               Program Manager, Valves

Innsbrook Technical Center
Virginia Power Company
5000 Dominion Blvd.
Glen Allen, VA 23060

ATTN:     Ms. Pamela E. Deline
          Project Engineer


                     CRANE VALVES NUCLEAR OPERATIONS
                         TELECOPIER TRANSMITTAL
               104 North Chicago Street, Joliet  IL 60431

DATE:

TO:                                     FROM:

TITLE:                                  TITLE:

COMPANY:

PHONE:                                  PHONE:

FAX:                                    FAX: (815) 727-4246

TOTAL PAGES:


                                                 TELEPHONE (815) 727-2600
                                                     POST OFFICE BOX 3339
                                                         JOLIET, IL 60434
          
CRANE          NUCLEAR OPERATIONS

CRANE VALVES            104 NORTH CHICAGO STREET       JOLIET, IL 60431

August 23, 1994

Kewaunee Nuclear Power Plant
Wisconsin Public Service Corp.
N 490 Hwy 42
Kewaunee, WI 54216-9510

Gentlemen:

In January of this year a containment isolation valve at the Prairie
Island Nuclear Station was damaged as a result of operational problems
involving maintenance procedures.  Details of the event have been
reported to the NRC via Prairie Island Docket Nos. 50-282 and 50-306 and
associated NRC Inspection Report Nos. 282/94002 and 306/94002.

The valves in question was a Crane 10" Figure 63174 and during the course
of the investigation, it was discovered that, contrary to inform shown on
the valve assembly drawing, shims were installed between the yoke and the
adapter plate.  The extraordinary conditions experienced by the valve
during the event resulted in failure of the welds joining the yoke and
adapter plate and more catastrophic failure to the other valves parts.

Crane assisted the Utility in evaluating additional valves of the same
design for evidence of the existence of shims and for the adequacy of the
attachment welds where shims did exist.  It was concluded that a
substantial safety hazard did not exist at the Prairie Island plant,
based on the walk-down that was performed and additional analytical
evaluations of the as-built valve characteristics.

Since that incident, Crane has conducted additional evaluations,
including a search of archives stored in a Crane facility in
Pennsylvania.  The valves at the Prairie Island plant were part of a
order produced by Crane for Westinghouse Electric in the early 1970's. 
Although the records indicate that valves of the Figure 63174 design were
supplied to you on the same Westinghouse order.

Crane requests your cooperation in determining if those valves are in
your system.  We will be glad to assist you in evaluating the condition
of the hardware and in performing any analytical evaluations to determine
if safety hazards exist.  Valves of the 63174 design were supplied in 10"
and 12" sizes.


You have been contacted based upon your affiliation with the Motor
Operated Valves User's Group and its Member Roster.  We appreciate your
cooperation in channeling this communication to the appropriate personnel
at your facility.

Your questions can be directed to the writer or to our Manager of
Development Engineering, Mr. Bruce Harry (who performed the initial on-
site evaluation at Prairie Island) or Mr. David Dwyer, our Analytical
Project Engineer, who has paid subsequent visits to the Prairie Island
plant.  Our general number in Joliet is 815-727-2600.

Very Truly Yours,


R. F. Hornyak

Manager QA/Support Engineering

RFH/llk

cc:  J. Carlson
     K. Hutchinson
     B. Harry
     D. Dwyer

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