ML20080S777

Interim Deficiency Rept,Item 109 Re Broken Valve Stem on 24-inch Globe Valve & Pilot Pin.Initially Reported on 840103.Breakage May Be Due to Fatigue Failure.Evaluation in Progress

ML20080S777
Person / Time
Site:	Fermi
Issue date:	02/17/1984
From:	Wells D DETROIT EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
109, QA-84-0083, QA-84-83, NUDOCS 8402290248
Download: ML20080S777 (2)

Text

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Detroit Edison EMim-February 17, 1984 QA-84-0083 Mr. James G. Keppler, Regional Administrator Region III U.S. Nuclear Regulatory Comtission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Report of 10CFR50.55(e) Itan on Broken Valve Stem on 24" Globe Valve and Pilot Pin (#109)

Dear Mr. Keppler:

On January 3, 1984, Detroit Edison's Mr. J.E. Durkin, Quality Engineer - Construction Quality Assurance telephoned Mr. J.E.

Konklin of NRC Region III to report a broken valve stem on a 24" Globe valve and pilot pin at the Fenni 2 site.

The pilot pin broke off of the lower portion of a disc of the 24" Globe valve. This allowed the disc to vibrate resulting in stress on the valve stem causing the stem to break. The breakage appears to be due to fatigue failure, and is currently being evaluated by Detroit Edison's Engineering Research.

As indicated in the proposed disposition for NCR 83-1289, the damaged canponents of this valve will be replaced.

The identical valve (V15-2019) in Division II of the RHR service water systen has been examined and no similar damage has been found.

During the RHR service water system preoperational testing, this valve was throttled. The throttling induced flow turbulence which resulted in valve assembly vibration. The excessive vibration eventually led to an apparent fatigue failure of the stem and possibly the guide pin. A restricting orifice has been installed in the pipe line and has successfully reduced the amplitude of the vibration. The valve in nonnal operation will be either open or closed. There is still sane short duration throttling service to be performed, the valve will be restored when the service is carplete.

After preoperational testing, the valve shall be inspected for damage. If required, the valve will be refurbished to "like new" condition prior to turnover to Nuclear Production. This applies to both valve V15-2018 (Division I) and V15-2019 (Division II) . i 8402290248 G40217 PDR ADOCK 05000341 S PDR FEB M # d

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r. James G. Keppler, . Regional /dninistrator February 17, 1984 OA-84-008?

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Another report on this item, either interim or final, will be sent when further information is available. If you have questions con-

.cerning this matter, please contact Mr. G.M.;Trahey, Assistant Director - Project Quality Assu arsce.

Very truly yours, i

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DAW / DIN /pn s

cc: Mr. Richard DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Ccanission Washington, D.C. 20555 Mr. Paul ~ Byron, Senior Resident Inspector U.S. Nuclear Regulatory Ccmnission 6450 North Dixie Ilighway ,' '

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