ML20064N260
| ML20064N260 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 02/09/1983 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 5964N, NUDOCS 8302160165 | |
| Download: ML20064N260 (2) | |
Text
..A N Commonwealth Edison r
[
C ) Ons First N!tional Pl;za, Chicrgo. Illinois k
O 7 Address Reply to: Post Office Box 767
\\
,/ Chicago, Illinois 60690 February 9, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Steam Generator Tube Vibration NRC Docket Nos. 50-454, 50-455, 50-456, and 50-457-References (a):
January 20, 1982 letter frota D.
G. Eisenhut to L. O. DelGeorge.
(b):
March 15, 1982 letter from T. R. Tramm to H. R. Denton.
(c):
Summary of February 19, 1982 NRC meeting with Westinghouse regarding Model D steam generators.
(d):
July 27, 1982 letter from B. J. Youngblood to L. O. DelGeorge.
(e):
October 28, 1982 summary of October 22, 1982 NRC meeting with Westinghouse regarding Model D steam generators.
Dear Mr. Denton:
This letter will document our intentions with regnrd to modification of the Byron /Braidwood steam generators to minimize tube degradation associated with flow induced vibration.
This supplements Commonwealth Edison's response to the NRC's request for information in reference (a).
We presently intend to modify to the exter.t necessary the Byron /Braidwood steam generators prior to loading fuel at each unit.
If a satisfactory modification cannot be engineered, tested, reviewed, approved and installed prior to fuel load on any of these units, we will do the modification work at the first opportunity and restrict power during the interim operation period.
Westinghouse's testing program has demonstrated that steam i
generators of this type can be operated indefinitely at 70% power.
This information has been reviewed with the NRC in meetings documented in references (c), (d), and (e).
Commonwealth Edison will use this gl 8302160165 830209 DR ADOCK 05000454 PDR i
3.
T 1
o i
.H.
R. Denton. February 9,.1983-information as the basis.for establishing a. specific power restriction during interim operation of the-Byron /Braidwood units.
Weodo not intend to operate any unmodified steam generators at power levels exceeding.
those judged acceptable at Westinghouse.
It is requested that the NRC approve this interim power restriction option ~so that plant startup may proceed in the event'that steam generator modifications cannot be completed prior to fuel-load.
We would be happy.to discuss this matter further at your convenience.
Please contact this office.
Very truly yours, T. R. Tramm Nuclear Licensing Administrator 1m 5964N