ML19254E187
| ML19254E187 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 10/19/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 7910310266 | |
| Download: ML19254E187 (1) | |
Text
'
'o UNITED STATES
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REGION lli
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799 ROOSEVELT ROAI.
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o GLEN ELLN. ILLINDIS 6o137 OCT 191979 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:
Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 Gentlemen:
Enclosed is IE Bulletin No. 7's-13, Revision 2 which requires action by you with regard to your pressurized water power reactor facility.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely,
% 0.
yff Keppler!
ames t.
Director
Enclosures:
1.
IE Bulletin No. 79-13, Rev. 2 2.
List of IE Bulletins Issued in the Last Six Months cc w/ encl:
Mr. G. A. Reed, Plant Manager Central Files Director, NRR/DPM Director, NRR/ DOR C. M. Trammell, ORB /NRR PDR Local PDR NSIC TIC Sandra A. Bast, Lakeshore Citizens for Safe Energy
/
00 1248 0%&
2C,5 7910310 i
SSINS:
6830 Accession No.:
7908220135 UNITED STATES 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 Nt. 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 re.quirements 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 investigcte 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 cf 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 Ono % Unit 1 On June 15, 1979, Caralina Power and Light reported that radiography showed crack indications en 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 Gcs Company reported on June 20, 1979 that Salem Unit I also has crack indications. Wisconsin Public Service company decided on June 20, 1979
" - '--^ -+ - - "la-tn-nina weld which contained questionable indicat As of June 22, 1979 ar.d since May 25, 197 inspected the feedwater nozzle-to pipe we DUPLICATE DOCUMENT L
i Entire document previously ntered into system under:
NOTE:
R1 and R2 indicates lines revit MO 1248 00 0 m
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