ML19254F200
| ML19254F200 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/17/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Boyer V PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 7911070324 | |
| Download: ML19254F200 (1) | |
Text
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October 17, 079 Docket flon. 50-352 50-353 Philadelphia Electric Company ATTN: Mr. V. S. Boyer Vice President Engineering and Research 2301 Market Street Philadelphia, PA 19101 Gentlemen:
The enclosed IE Bulletin 73-13, Revision 2, is forwarded to you for informa tion.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, d
A Boyce H. Grier
- Director
Enclosures:
1.
IE Bulletin flo. 79-13 w/ Attachments 2.
Listing of IE Bulletins Isrued in Last 6 Months CONTACT:
L. E. Tripp 337-5282
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E_NCLOSURE 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 ho. 79-13 Revision 2 Page 1 of 5 CRACKING IN FEEDWATER SYSTEM PIPING Description of Circumstances:
This revision to IE Bulletin No. 79-13 is based on the results of the radiogrephic l
examinations and ongoing investigation of the subject problem to date since the t
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 discovered following a shutdown on May 19 to investigate leakage inside contain-ment.
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 bil 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, inspec-tion and operating histories.
To further explore the generic nature of the cracking problem, the Office of Inspection and Enforcement requested licensees of FWR 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 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.
Wis June 20, 1979 to cut out a feedwater no able indication, for metallurgical exami May 25, 1979 seven other PWR facilities DUPLICATE DOCUMENT pipe welds without finding cracking indi Entire document previously NOTE: R1 and R2 indicates lines revise entered into system under:
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