ML19256E445
| ML19256E445 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/17/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Jones OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 7911070082 | |
| Download: ML19256E445 (1) | |
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October 17, 1979 9,,,, #
Docket. No.
50-285 Omaha Pu' ic Power District ATTN:
K. C. Jones, Division Manager -
Production Opera' ons 1623 Harney Street Omaha, Nebraska 68102 Gentlemen:
Enclosed is IE Bulletin No. 79-13, Revision 2 which requires action by you with regard to your power reactor facility.
Should you have any questions regarding this IE Bulletin or the actions required by,you, please contact this office.
Sincerely f
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'Karl V. Seyfrit Director
Enclosures:
1.
IE Bulletin No. 79-13, Revision 2 2.
List of IE Bulletins Issued in the Last Six Months cc:
S. C. Stevens, Manager Fort Calhoun Station Post Office Box 98 Fort Calhoun, Nebraska 68102 1 " 3 028 D81-7911070 I4
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SSINS:
6830 Accession No.:
7908220135 UNITED STATES NUCLEAR REGULATORY COMML3SION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-13 Revision 2 October 16, 1979 Page 1 of 5 CRACKING IN FEEDWATER SYSTEM PIPING Lescription of Circumstances:
This revision to IE Bulletin No. 79-13 is based on the results of the radio-graphic examinations and ongoing investigation of the subject problem to date since the initial Bulletin was issued. The revision reduces in scope the R2 number and extent of the piping system welds required to be examined. The requirements for reporting and action time frame remain unchanged.
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 pipe 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 confirmed on Jane 18, 1979, that radiography has shown cracking in the' to-vessel nozzle weld. Public Servic NOTE: R1 and R2 indicates lines revi DUPLICATE DOCUMENT Entire document previously entered into system under:
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