ML20008F916

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Provides Clarification Re Relief Request 3.1.41 of Inservice Testing Program Re Alternate Testing of Check Valve.Revised Paragraph Will Be Incorporated in Revision 3 of Pump & Valve Testing Program
ML20008F916
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 05/06/1981
From: Clayton F
ALABAMA POWER CO.
To: Varga S
NRC
References
NUDOCS 8105120319
Download: ML20008F916 (1)


Text

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Malling Address Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham. Alabama 35291 Telepnone 205 783-6081 b

F. L Clayton, Jr.

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Alabama Power the southem eleonc system D

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May 6, 1981

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Docket No. 50-348 gg g

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Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission h

p Washington, D. C.

20555 Attention: Mr. S. A. Varga J. M. Farley Nuclear Plant - Unit #1 Inservice Testing Program Gentlemen:

Mr. Joel D. Page of the NRC Staff identified a point of potential confusion in the wording of Relief Request 3.1.41 of the Farley Nuclear Plant - Unit 1 Inservice Testing Program. Paragraph 3.1.41.2, Alternate Testing, implies that either the flow criterion or the differential pressure criterion may be used to verify the full-open position of the check valve.

Since this is not the intent of the Alternate Testing method, the following revised paragraph is submitted in order to provide immediate clarification:

"The valve will be full-stroke tested at each refueling outage. A flow greater than or equal to the manufacturer's minimum full open value (Flow 1 10 GPM) will be verified.

The new paragraph will be fonnally incorporated into the Pump and Valve Testing Program through the forthcoming Revision 3 to the Program.

Should you have any questions, please advise.

Yours very truly,

. Clayton, J.

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cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford Mr. J. D. Page

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