ML19256E705
| ML19256E705 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/29/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 7911150040 | |
| Download: ML19256E705 (1) | |
Text
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,o KING OF PRUSSIA, PENNSYLVANIA 19406 OCT 23 g Docket No. 50-219 Jersey Central Power and Light Company ATTN:
Mr. Ivan R. Finfrock, Jr.
Vice President Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Gentlemen:
The enclosed IE Bulletin 79-17, Revision 1, is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, Y
MA Boyce H. Grier Director
Enclosures:
1.
IE Bulletin No. 79-17, Revision 1 w/ Attachment 2.
List of IE Bulletins Issued in the Last Six Months CONTACT:
L. E. Tripp 215-337-5282 cc w/encls:
J. T. Carroll, Station Superintendent 1337 294 7911150 04-0
ENCLOSURE 1 UNITED STATES SSINS No.:
6820 NUCLEAR REGULATORY COMMISSION Accession No.:
0FFICE OF INSPECTION AND ENFORCEMENT 7908220157i 3 7 WASHINGTON, D.C.
20555 IE Bulletin No. 79-17 Revision 1 Date:
October 29, 1979 Page 1 of 5 PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT PWR PLANTS Description of Circumstances:
IE Bulletin No. 79-17, issued July 26, 1979, provided information on the R1 cracking experienced to date in safety-related stair,less steel piping R1 systems at PWR plants.
Certain actions were requirad of all PWR R1 facilities with an operating license within a specified 90-day time R1 frame.
After several discussions with licensee owner group representatives and R1 inspection agencies it has been determined that the requirements of Item 2, R1 particularly the ultrasonic examination, may be impractical because of un-R1 availability of qualified personnel in certain cases to complete the in-R1 spections within the time :,pecified by the Bulletin. To alleviate this R1 situation and allow liccasees the resour es of improved ultrasonic inspec-R1 tion capabilities, a time extension a.M clarifications to the bulletin have R1 been made.
These are referenced ts che affected items of the original R1 bulletin.
furing the period of November 1974 to February 1977 a number of cracking incidents have been experienced in safety-related stainless steel piping systems and por-tions of systems which contain oxygenated, stagnant or essentially stagnant bor-ated water.
Metallurgical investigations revealed these cracks occurred in the weld heat affected zone of 8-inch to 10-inch type 304 material (schedule 10 and 40), initiating on the piping I.D. surface and propagating in either an inter-granular or transgranular mode typical of Stress Corrosion Cracking.
Analysis indicated the probable corrodents to be chloride and oxygen contamination in the affected systems.
Plants affected up to this time were Arkansas Nuclear Unit 1, R. E. Ginna, H. B. Robinson Unit 2, Crystal River unit 3, San Onofre Unit 1, and Surry Units 1 and 2.
The NRC issued Circular No. 76-06 (copy attached) in view of the apparent generic nature of the problem.
During the refurling outage of Three of this year, visual inspections disc in the spent fuel cooling system pipi DUPLICATE DOCUMENT removal system.
These cracks were fo and later confirmed by liquid penetra Entire document p-eviously cracking was reported to the NRC in a entered into sys e under:
ggg /[7 1979.
A preliminary metallurgical an section of cracked and leaking weld j ANO
_,4 1337 295 no. or gases:
F Identifies those additions or re