ML19224D607
| ML19224D607 | |
| Person / Time | |
|---|---|
| Site: | Bailly |
| Issue date: | 06/25/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shorb E NORTHERN INDIANA PUBLIC SERVICE CO. |
| References | |
| NUDOCS 7907130131 | |
| Download: ML19224D607 (1) | |
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UNITED STATES 4
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PJUCLEAR REGULATORY COMMISSION f [i.;; f j i
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g o te s e ttv s. it uNois 6013 7 June 25, 1979 Docket No. 50-367 North en Indiana Public Service Company ATTN:
Mr. Eugene M. Shorb Senior Vice President 5265 Hohman Avenue Hammond, IN 46325 Gentlemen:
The enclosed IE Bulletin No. 79-13 is forwarded to you for information. No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, 0'
James G. Kepple Director
Enclosures:
- 2. Listing of IE Bulletins Issued in Last 12 Months cc w/encls:
Central Files Director, NRR/ DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General 369 og,
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U.S. NUCLEAR REGULAT0nY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III June 25, 1979 IE Bulletin No. 79-13 CRACKING IN FEEDWATER 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. Ccak Unit 2 facility. The cracting was discovered following a shutdown on K 19 to investigate leakag2 inside containment. Leaking circumferential cr.cks were identified in the 16-inch feedwater elbows adjacent to two steam generator nozzle elbow welds.
Subsequent radiographic examination revealed crack indications in al] eight steam generator feedwater lines at this location on both Units 1 and 2.
On May 25, 1979, a letter was sent to a]l PWR licensees by the Office of Nuclear Reactor Regulation which informed licensees of the D. C. Cook fmilures 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 stest generators reported crack indications. Southern California Edison reported on June 5, 1979, that radiographic extrination 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 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 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.
The feedwater nozzle-to-pipe configurations for D.C. Cook and for San Onofre are shown on the attached figures 1 and 2.
A typical feedweter pipe-to-nozzle weld joint detail showing the principal crack locations for D.C. Cook and San Onofre are shown on the attached figure 3.
On March 17, 1977, during heat-up for hot' 7 UPLICATE DOCUMENT ~ ~~^"
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Unit 1, a leak was discovered in the vess
!D the 16-inch diameter feedwater piping to nondestructive examination of all nozzle
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