ML20042C103
| ML20042C103 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 03/15/1982 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 3622N, NUDOCS 8203300203 | |
| Download: ML20042C103 (2) | |
Text
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'7 Commonwealth Edison
) one Fwst National Plata. Chicago Ilknots C-( O ~ Address Renly to: Pos' Office Box 767 CN,ago, Illinois twA March 15, 1982 x
Mr. Harold R. Denton, Director d' c, '
'7 Of fice of Nuclear Reactor Regulation
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U.S. Nuclear Regulatory Commission 4
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Subject:
Byron Station Units 1 and 2 g',
Braidwood Station Units 1 and 2
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Steam Generator Vibration Monitoring NRC Docket Nos. 50-454, 50-455, 50-456 and 50-457 Reference (a):
January 20, 1982 letter from D.
G. Eisenhut to L. O. De1 George.
Dear Mr. Denton:
This is to provide information requested in reference (a) regarding reports of tube damage in steam generators similar to those to be used at Byron and Braidwood.
In late October,1981 a foreign plant with Model D-3 steam generators experienced a steam generator tube leak.
Subsequent inspections o f the steam generators of that plant and the D-3 steam generators o f another foreign plant showed that the tubes were experiencing vibration and wear in the pre-heater area.
The Byron /Braidwood plants utilize model D-4 and D-5 steam generators which are similar in configuration to the D-3 steam generators.
Westinghouse has identified to us the nature of the mechanism observed in two non-domestic plants with Model D-3 steam generators.
We have discussed with Westinghouse the program that is in place to understand the nature of phenomena and to justify operation of all pre-heat steam generators.
The Westinghouse program includes the use of scale model testing, analytical studies, wear testing, periodic eddy current inspection of operating units, and the use o f diagnostic internal and external instrumentation in selected operating plants.
In our review of the Westinghouse program, we have determined we will rely on the results of the Westinghouse analysis and test programs and the experience and data gained at operating plants.
At the present time one Model D-3 unit - (split flow pre-heater) and one Model D-4 unit (counter flow pre-heater)
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// O 8203300203 020315 PDR ADOCK 05000454 A
e' H. R. Denton March 15, 1982 are equipped with diagnostic internal and external instrumentation as part o f the Westinghouse program.
After the data from these units are collecteo and evaluated, we will be able to determine if any diagnostic instrumentation should be attached to or installed in the steam generators at our plant.
This determination should be made by September 1,1982 and a further response will be submitted at that time.
If you have any questions concerning this matter, please contact this office.
One (1) signed original and fifty-nine (59) copies o f this letter are provided for your use.
Very truly yours, 7/N, M*h T.R.
Tramm Nuclear Licensing Administrator 1m 3622N