ML19257D586

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Forwards Response to IE Bulletin 79-13,Revision 2, Cracking in Feedwater Sys Piping. Indications of Cracking Were Found in Main Feedwater Nozzle of Steam Generator C & in Auxiliary Feedwater Nozzle of Steam Generator a During Radiography
ML19257D586
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 01/03/1980
From: Parker W
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-13, NUDOCS 8002050080
Download: ML19257D586 (2)


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373-4063 January 3, 1980 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: McGuire Nuclear Station IE Bulletin 79-13, Revision 2 RII:JP0 50-369

Dear Mr. O'Reilly:

My letter of October 19, 1979 provided Duke Power Company's response to IE Bulletin 79-13.

As stated in that response, Duke Power Company has performed rai ographic examinations of the auxiliary feedwater and main feedwater nozzle to piping welds on the four Unit 1 steam generators. The results of this examination are attached.

Two indications were found during the radiographic testing, one in the main feedwater nozzle of Steam Generator "C," and the other in the auxiliary feedwater nozzle of Steam Generator "A."

Subsequent examinations revealed that neithe-indication was located in the nozzle base material, and both ii dications were accepted. The dis-position of each indication is 21scussed in greater detail in the attachment.

Mr. B. R. Crowley, NRC/01E, has reviewed our radiographic examination and disposition of the indications. His inspections are described in IE Inspection Report Nos. 50-369/79-38 and 50-369/79-40.

Ve j truly yours, s

A liam O. Parker, Jr.

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MCCUIRE NUCLEAR STATION RESPONSE TO IE BULLETIN 79-13, REVISION 2 Item G Duke Power Company conducted radiographic examinations of both the main and auxiliary feedwater nozzle-to-piping welds on the four Unit 1 steam generators.

These examinations were conducted in accordance with the bulletin require-ments, and they revealed two indications.

The disposition of these indications is discussed below:

(a) An indication was found in the primary feedwater nozzle on Unit 1 Steam Generator C.

It was determined based on a review of the radiographs (direct and parallax) that the indication is in a fillet weld joining the feedwater flow limiter to the flow limiter sleeve and not in the nozzle base material. An indication in this fillet weld is acceptable and no further corrective action is required.

(b) An indication was found in the auxiliary feedwater nozzle on Unit 1 Steam Generator A.

This indication was subsequently examined using ultrasonic tests and fiber optics (visual). The ultrasonic tests revealed no indi-cations in the nozzle base material.

The visual examination revealed surf ace irregularities in the clad on the inside of the nozzle.

Based on the visual and ultrasonic inspections, it has been determined that the indication was caused by a lack of fusion between the inconel clad overlay and c.he nozzle base material.

The indication is acceptable because the clad is not a pressure boundary and provides only crosion/

corrosion protection.

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