ML19253A531

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Forwards IE Bulletin 79-13,Revision 1, Cracking in Feedwater Sys Piping. Action Required
ML19253A531
Person / Time
Site: McGuire 
Issue date: 08/30/1979
From: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Parker W
DUKE POWER CO.
References
NUDOCS 7909100224
Download: ML19253A531 (2)


Text

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NUCLEAR REGULATORY COMMISSION n

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101 MARIETTA ST., N.W., SulTE 3100 g

g' ATLANTA, GEORGIA 30303 AUG 3 01979 In Reply Refer To:

RII:JPO 50-369 Duke Power Company Attn:

W. O. Parker, Jr.

Vice President, Steam Production Post Office Box 2178 Charlotte, North Carolina 28242 Gentlemen:

Enclosed is IE Bulletin 79-13, Revision 1 which requires action by you with regard to your power reactor facility (ies) identified in Enclosure 3.

Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.

Sincerely,

'w

w James P. O' Reil y Director

Enclosures:

1.

IE Bulletin No. 79-13, P;.

, ion 1 2.

Lisc of IE Bulletins Issued in Last Six Months 3.

Designated Applicants for Operating Licenses 79091002[

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@[;. 9 Y Duke Power Company.

cc w/ encl:

M. D. McIntosh, Plant Manager Post Office Box 488 Cornelius, North Carolina 28031 J. C. Rogers, Project Manager Post Office Box 33189 Charlotte, North Carolina 28242 (t

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Accession No: 7908220101 SSINS No.- 6830 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 August 30, 1979 IE Bulletin No. 79-13 Revision 1 CRACKING IN FEEDWATER SYSTEM PIPING Description of Circumstances:

On May 20, 1979, Indiana and Michigan Power Company notified tne NRC of cracking in two feedwater lines at their D. C. Cook Unit 2 facility.

The cracking was discovered following a shutdown on May 19 te investigate leakage inside containment.

Leaking circumferential cracks were identified in the 16-inch feedwater elbows adjacent to two steam generator nozzle elbow welds.

Subsequent radiographic examination revealed crack indications in all eight steam generator feedwater lines at this locatica on both Units 1 ad 2.

On May 25, 1979, a letter was sent to all WR licensees by the Office of Nuclear Reactor Regulation which snformed licensees of the D. C. Cook failures and requested specific information on feedwater system design, fabrication, inspection and operating histories.

To further explore the generic nature of the cracking problem, the Office of Inspection and Enforcement requested licensees of PWR plants in current outages to immediately conduct voltraetric examination of certain feedwater piping welds.

As a result of these actions, several other licensees with Westinghouse steam generators reported crack indications. Southern California Edisor reported on June 5, 1979, that radiographic examination revealed indications of cracking in feeds ".er nozzle to piping welds on two of three steam generatas of San Onofre Und 1.

On June 15, 1979, Carolina Power and Light reported that radiography showed crack indications in nimilar locations at their H. B.

Robinson Unit 2.

Duquesne Power and Light confirmed on June 18, 1979, that radiography has shown cracking in their Beaver Valley Unit 1 feedwater piping to vessel nozzle weld.

Public Service Electric and Gas Compm y reported on June 20, 1979 that Salem Unit 1 also has crack indications. Wisconsin Public Service company decided on June 20, 1979 to cut out a feedwater nozzle-to pipe weld which contained questionable indication, for metallurgical examination.

As of June 22, 1979 and since May 25, 1979 seven other PWR facilities have inspected the feedwater nozzle-to pipe we N

indications.

$DUPLICi.2E DOCUMENT 9

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Onofre are shown on the attached figure 3 j ANO 4

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