ML19247A567
| ML19247A567 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/17/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7908010323 | |
| Download: ML19247A567 (1) | |
Text
hlh5 pa nuo UNITED STATES
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NllCLEAR REGULATORY COMMISSION f,
REGION IV u,.
611 RYAN PLAZA DRIVE, SUITE 1000 S
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July 17, 1979 In Reply Refer To:
RIV Docket No.
STN 50-482/IE Information Notice No. 79-19 Kansas Gas & Electric Co.
Attn:
Mr. Glenn L. Koester Vice President-Operations Post Office Box 208 Wichita, Kansas 67201 Gentlemen:
This IE Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No response is requested at this time however licensees should be aware that the NRC is evaluating the issuance of a Bulletin to operating PWR's requesting information on precious inservice inspections of stagnant borated water systems and requesting inspection of systems which have not been inspected recently.
If you have questions or comments regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely,
'l' S
qt nLt U).X 1
K trl V. Seyfrit rector
Enclosures:
1.
IE Information Notice No. 79-19 2.
List of IE Information Notice Issued in 1979 cc: w/ enclosures Messrs. Nicholas A. Petrick, SNUPPS ff3(d'21 D. T. McPhee, Kansas City Power and Light Company Gerald Charnof f, Shaw, Pittman, Potts 6 Trowbridge E. W. Creel, Kansas Gas and Electric Company Iw) gosoton3
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASifINGTON, D. C.
20555 IE Information Notice No. 79-19 Date: July 17, 1979 Page 1 of 2 PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT PWR PLANTS Description of Circumstances:
During che period of November 1974 to February 1977 a number of cracking incidents have been experienced in safety-related stainless steel piping systems and portions of systems which contain oxygenated, stagnant or essentially stagnant borated 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 intergranular 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 One Unit 1, R. E. Cinna, H. B. Robinson Unit 2, Crystal River Unit 3, San Onofre Unit 1, and Surry Units 1 and 2.
The NRC issued IE Circular 76-06 (copy attached) in view of the apparent generic nature of the problem.
During the refueling outage of Three Mile Island Unit I which began in February of this year, visual inspections disclosed five (5) through-wall cracks at welds in the spent fuel cooling system piping and one (1) at a weld in the decay heat removal system. These cracks were found as a result of local boric acid build-up and later confirmed by liquid penetrant tests. This initial identification of cracking was reported to the NRC in a Licensee Event Report (LER) dated May 16, 1979. A preliminary metallurgical analysis was performed by the licensee on a section of cracked and leaking weld joint from the spent fuel cooling system.
The conclusion of this analysis was that cracking was due to Intergranular Stress Corrosion Cracking (IGSCC) originating on the pipe I.D.
The cracking was localized to the heat affected zone where the type 304 stainless steel is sensitized (precipitated carbides) during welding.
In addition to the main through-wall crack, incipient cracks were observed at several locations in the weld heat affected zone including the weld root fusion area where a miniscule lack of fusion had occurred.
The stresses responsible for cracking are believed to be primarily residual welding stresses inasmuch as the calculated applied stresses were found to be less than, code design limits. There is no conclusive P'7N'
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evidence at this time to identify t%, '
promoted this IGSCC attack. Furth( h DUPLICATE DOCUMENT other system welds are being pursue p gggg Entire document previously entered e
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