ML19321B252

Deficiency Rept Re Improper Weld Configuration on Steam Generator Encl Stiffener Ring Connections.Cause Not Stated. Welds Have Been Modified to Meet Design Drawings.Personnel Reinstructed to Assure Compliance W/Design Drawings

ML19321B252
Person / Time
Site:	McGuire
Issue date:	07/25/1980
From:	Parker W DUKE POWER CO.
To:
References
SD-369-80-08, SD-369-80-8, NUDOCS 8007300355
Download: ML19321B252 (2)

Text

--__ __

i c> -.

DUKE POWER COMPANY Powra Burtnixo 423 Sourn Cnuncu STuzer, Cluni.orTr. N. C. 2e242 w w a

o. a. a c a. a a.

July 25, 1980 (CF PetSiDfNt TELEPmCNC. AaC a 704 S y g4 w P*QDwC' TON 373-4083 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commissien Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: McGuire Nuclear Station Unit 1 Docket No. 50-369

Dear Mr. O'Reilly:

Pursuant to 10CFR 50.55e please find attached Significant Deficiency Report SD 369/80-08.

Ver truly yours,

) L.- 0. % /w N Willi m 0 Parker, Jr.

LJB:scs Attachment y

cc: Director Mr. T. J. Donat Office of Inspection & Enforcement NRC - McGuire Nuclear Station U. S. Nuclear Regulatory Commission Washington, D. C.

20555 t

S

\\

g 800730g g

n' DUKE POWER COMPANY MCGUIRE NUCLEAR STATION Report Number:

SD-369/80-08 Report Date: July 25, 1980 Facility: McGuire Nuclear Station, Unit 1 Identification of Deficiency:

Improper Weld Configuration on McGuire Unit 1 Steam Generator Enclosure Stiffener Ring Connections Description of Deficiency:

On June 26, 1980, Mr. J. R. Wells and Mr. S. B. Hager reported the following deficiency, by telephone, to Mr. John Rausch of NRC, Region II, Atlanta.

On McGuire Unit 1, steam generator enclosures A, B, C and D, the original weld-ing of circumferential stiffner ring connections was not performed in accordance with design drawings. Partial penetration welds were placed where full penetra-tion welds were required by.the drawings.

Analysis of Safety Implication:

An analysis of aa-erected weld configuration showed that stresses in excess of that allowed by the ASME Code were present. This could result in damage to or failure of the Steam Generator enclosures if subjected to accident conditions.

Corrective Action:

The welds have been modified to meet design drawings and found acceptable through non-destructive examinations. All Unit 2 steam generator enclosure welds have also been examined to assure that similar welds were properly made.

Appropriate personnel have been reinstructed in the procedures to assure com-pliance with design drawings. Corrective action was completed by ' July 18, 1980.

9 9

4 s

>