ML19331B939

Responds to IE Bulletin 79-03A, Longitudinal Weld Defects in ASME SA-312,Type 304 Stainless Steel Pipe. Ratio of Calculated Hoop Stress to Allowable Stress at Design Temp Does Not Exceed 0.85.Evaluation Results Encl

ML19331B939
Person / Time
Site:	Hatch
Issue date:	08/05/1980
From:	Widner W GEORGIA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-03A, IEB-79-3A, NUDOCS 8008130572
Download: ML19331B939 (6)

Text

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w. A wiann GeorgiaPower August 5, 1980 ,, 3,,,,,,,, y,y,7c s ,.y,,,

United States Nuclear Regulatory Commission Office of Inspection and Enforcement

REFERENCE:

Region II - Suite 3100 RII: JP0 101 Marietta Street, NW 50-321/50-366 Atlanta, Georgia 30303 I&E Bulletin 79-03A ATTENTION: Mr. James P. O'Reilly Gentlemen:

In accordance with I&E Bulletin 79-03A, " Longitudinal Weld Defects In ASME SA-312, Type 304 Stainless Steel Pipe", P& ids, piping specifications, and other appropriate documents have been reviewed to ascertain the use of the referenced seam welded pip-:ng material. Thr hoop stresses have been calculated based upon code requirements for pr.:ssure design. In each case, the ratio of calculated hoop stess to the al'iowable stress at the design temperature does not exceed 0.85 for both tt e Hatch units. Consequently, no further action is required to comply with the action items of the subject bulletin. Attachments 1 and 2 summarize the results of the evaluation.

If you have any questions or comments in this regard, please contact my office.

Sincerely yours, W. A. Widner cd JAE/mb Attachment xc: Director of the Office of Inspection and Enforcement firector of the Division of Operating Reactors, Office of Nuclear Reactor Regulation /

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THIS DOCUMENT CONTAINS POOR QUALITY PAGES 8008130 Q L

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• MPL Code Cll - Control Rod Drive Sys. '

C41 - Standby Liquid Control Sys.

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Pil - Condensate Transfer & Storage Sys.

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2E41 - HPCI Sys.

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2Gll - Radwaste Sys.

2G41 - Fuel Pool Cooling & Clean-Up Sys.

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