ML20087D529

Final Potential Deficiency Rept 149 Re Sheared Valve Stems in Component Cooling Water Sys.Caused by Excessive Force Used to Close Valves in Order to Prevent Leakage.Item Not Reportable Per 10CFR50.55(e)

ML20087D529
Person / Time
Site:	Waterford
Issue date:	02/29/1984
From:	Gerrets G, Gerrets T LOUISIANA POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
149, W3K84-0429, W3K84-429, NUDOCS 8403130436
Download: ML20087D529 (2)

Text

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e l_OUISIANA 142 DRARONDE STREET P O W E R & L 1 G H T! p O box 6008

• NEW OALEANS. LOUISlANA 70174

. (504) 366 2345

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February 29, 1984 W3K84-0429 Q-3-A35.07 TW@@0MB T Mr. John T. Collins Regional Administrator, Region IV "T U. S. Nuclear Regulatory Commission . @

611 Ryan Plaza Drive, Suite 1000

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Arlington, Texas 76012

REFERENCE:

Telecon C. N. Hooper (LP&L) and W. Crossman (NRC IV) on February 10, 1984

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Potentially Reportable Deficiency No. 149

" Component Cooling Water (CCW) Butterfly Valves" Final Report On February 10, 1984, a problem with sheared valve stems in the Component Cooling Water System was reported as Potentially Reportable Deficiency No.

149. Further evaluation of the previously described condition indicates this condition is net considered reportable pursuant to the requirements of 10CFR50.55(e).

EVALUATION The apparent cause for valve stem failure has been use of excessive force to close the valves in order to prevent valve leakage. This occurred during preoperational testing. After evaluation of the event, it is concluded that the event is not reportable for the following reasons:

(1) The above manually operated butterfly valves must be open during normal unit operation and are allowed to be closed only for maintenance.

Failure of the shafts during maintenance operations does not affect unit safety.

8403130436 840229 PLR ADOCK 05000382 PDR S

L 1 ilo

/

e Mr. John T. Collins February 29, 1984 W3K84-0429

-Page 2 EVALUATION (Continued)

(2) The event occurred during the preoperational testing phase, which is governed by different operating procedures and personnel than during the operational phase.

Based on the above evaluation, this PRD is considered not reportable.

. Very truly yours, ,

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T. F. Gerrets h

Corporate Quality Assurance Manager TFG:CNH:VBR cc: Director Office of Inspection & Enforcement U. S. Nur. lear Regulatory Commission Washington, D.C. 20555 (15 copies)

Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. E. L. Blake Shaw, Pittman, Potts, & Trowbridge 1800 M Street, N.W.

Washington, D.C. 20036 Mr. W. M. Stevenson Monroe & Lemann

1424 Whitney Building New Orleans, Louisiana 70130 I