ML19208A699
| ML19208A699 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/30/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Arenal A SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 7909170306 | |
| Download: ML19208A699 (1) | |
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UNITED STATES h
NUCLEAR REGULATORY COMMISSION y
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1990 N. CALIFORNI A BOULEVARD SUITE 202, W ALNUT CREE K PLAZA
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August 30, 1979 Docket No. 50-361 Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention: Mr. A. Arenal Vice President, Advanced Engineering 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, b
R. H. Engelken Director
Enclosures:
1.
IE Bulletin No. 79-13, Revision 1 2.
List of IE Bulletins Issued in Last Six Months 3.
Designated Applicants for Operating Licenses cc/w/ enclosures:
J. H. Drake, SCE 3hb.INO q < 0917 0 3Of' h
Accession No: 7908220101 SSINS No.: 6830 UNITED STATES MUCLEAR REGULATORY C0imISSION 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 30, 1979 IE Bulletin No. 79-13 Revision 1 CRACKI.':3 IN FEEL'ATER SYSTEM PIPING Description of Circumstances:
On May 20, 1979, Indiana and Michigan Power Company notified the 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 to 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 location on both Units 1 and 2.
On May 25, 1979, a letter was sent to all PWR licensees by the Office of Nuclear Reactor Regulation which informed 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 volumetric examination of certain feedwater piping welds.
As a result of these actions, several other licensees with Westinghouse steam generators reported crack indications. Southern California Edison reported on June 5,1979, that radiographic examination revealed indications of cracking in feedwater nozzle-to-piping welds on two of three steam generators of San Onofre Unit 1.
On June 15, 1979, Carolina Power and Light reported that radiography showed crack indications in similar locations at their H. B.
Robinson Unit 2.
Duquesne Power and Light confimed on June 18, 1979, that radiography has shown cracking in their Beaver Valley Unit I feedwater piping to vessel nozzle weld. Public Service Electric and Gas Company 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 welds without finding cracking indications.
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W~-u DUPLICATE DOCUMENT (A' MEO The feedwater nozzle-to-pipe configu d Jo nt eta 1 ng pr n i Entire document previously entered into system under:
Cnofre are shown on the attached fig ANO f 0 $Q Q 0 /0 /
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