ML19254F137
| ML19254F137 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/17/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Dunn C DUQUESNE LIGHT CO. |
| References | |
| NUDOCS 7911070097 | |
| Download: ML19254F137 (1) | |
Text
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--72 UNITED STATES
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NUCLEAR REGULATORY COMMISSION hh.
.E REGION I 3 f;
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631 PARK AVENUE S, 'A U
KING OF PRUS',la, PENNSYLVANIA 19406 9....
October 17, 1979 Docket No. 50-334 Duquesne Light Company ATTN: Mr. C. N. Dunn Vice President Operations Division 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Gentlemen:
Enclosed is IE Bulletin 70-13, Revision 2, which requires action'by you with regard to your power rector facility (ies) with an operating license.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely,
/
oyce H.
rier Director
Enclosures:
1.
IE Bulletin No. 79-13 w/ Attachments 2.
Listing of IE Bulletins Issued in Last 6 Months cc w/encls:
F. Bissert, Technical Assistant Nuclear R. Washabaugh, QA Manager J. Werling, Station Superintendent G. Moore, Gereral Superintendent, Power Stations Department J. J. Carey, Nuclear Technical Assistant R. Martin, fluclear Engineer CONTACT:
L. E. Tripp 337-5282 1290 357 7911070 099
ENCLOSURE 1 SSINS:
6830 Accession No.:
7908220135 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 October 17, 1979 IE Bulletin No. 79-13 Revision 2 Page 1 of 5 CRACKING IN FEEDWATER SYSTEM PIPING Description of Circumstances:
This revision to IE Rulletin No. 79-13 is based on the results of the radiographic examinations and ongoing investigation of the subject problem to date since the initial Bulletin was issued.
The revision reduces in scope the number and R2 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 dis: overed following a shutdown on May 19 to investigate leakage inside contain-ment.
Leaking circumferential cracks were identified in the 16-inch feedwater elb1ws adjacent to two steam generator rozzle elbow welds. Subsequent radiographic exan.ination revealed crack indications il all eight steam generator feedwater lines at this location on both Units 1 and 2.
On May i'5,1979, a letter was sent to all PWR licensees by the Office of auclear Reactor kagulation which informed licensees of the D. C. Cook failures and requested specific information on feedwater system design, fabrication, inspec-tion and operating histories. To further explore the generic nature of the cracking problem, tne Office of Inspection and Enforcerent requested licensees of PWR plaats 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 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.
W i s c - - ' - "" * - " --" "- ---" d a d d a d aa June 20, 1979 to cut out a feedwater noz able indication, for metallurgical exami May 25, 1979 seven other PWR facilities pipe welds without finding cracking indi DUPLICATE DOCUMENT NOTE: R1 and R2 indicates lines revi. sed Ertire document previouslyOg jhg entered into system under: y ANO No. of pages: .}}