ML19260A183
| ML19260A183 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Perkins, Cherokee  |
| Issue date: | 10/17/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7911070194 | |
| Download: ML19260A183 (2) | |
Text
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o, UNITED STATES NUCLEAR REGULATORY COMMISSION g
- a REGION 11 b[
0, 101 MARIETTA ST N.W.. SulTE 3100 o
ATLANTA. GEORGIA 30303 In Reply Refer To:
OCT 171979 RII:JPO 50-413, 50-414 50 M N 5491,I50T88'
- 493, 50-4 9~, 50-490 Duke Power Company Attn:
L. C. Dail, Vice President Design Engineering P. O. Box 33189 Charlotte, North Carolina 28242 Gentlemen:
The enclosed Bulletin No. 79-13, Revision 2 is forwarded to you for infor-mation. No written responce is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
\\
\\
b Sm ames P. O'Reilly
- rector
Enclosures:
1.
IE Bulletin No. 79-13, Rev on 2.
Listing of IE Bulletins Issued in Last Six Months 7299 298 L
7011070\\o-44
DCT 171979 Duke Power Company,
cc w/ encl:
D. G. Beam, Project Manager Post Office Box 223 Clover, South Carolina 29710 J. T. Moore, Project Manager Post Office Box 422 Gaffney, South Carolina 29340
!299 299
SSINS:
6830 Accession No.:
7908220135 UNITED STARES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 October 16, 1979 IE Bulletin No. 79-13 Revision 2 CRACKING IN FEEDWATER SYSTEM PIPING Description 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 explor" 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 co radiagraphy has shown cracking in their B to-vessel nozzle weld. Public Service El June 20, 1979 that Salem Unit 1 also has DUPLICATE DOCUMENT Smcvice company decided on June 20, 1979 weld which contained questionable indicat Entire docnnnent previcxisly As of June 22, 1979 and since May 25, 197 entered into system under:
inspected the feedwater nozzle-to pipe we 7,<66KL2s/35 12O,9 300 ANO r
1 No. of pages:
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NOTE:
R1 and R2 indicates lines revis