ML19211C687
| ML19211C687 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/09/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001140219 | |
| Download: ML19211C687 (1) | |
Text
TENNESSEE val?.EY AUTHCGl?(
CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Strset Tower II January 9, 1980 Mr. Darrell G. Eisenhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regplation U. S. Nuclear Regulatory Comission Washington, DC 20555
Dear Mr. Eisenhut:
In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 This is in response to your letters dated November 9, 1979, and November 27, 1979, requesting confirmation that the fuel rod strain-flow blockage models used on Browns Ferry are conservative with respect to the NRC's model derived from ORNL multi-rod burst test facility data. Since TVA does not have or use our own models in this area, we rely on General Electric Company approved models in association with the operation of Browns Ferry. We are aware of the review effort GE has applied to this ist,ue and of the communications between GE and the NRC on this subject.
We herein affirm that, based on our ccrrespondence from GE, it is our understanding that over the operating range of interest pertinent to Browns Ferry the models applied by GE and approved by the NRC are of a conservative level equivalent to the NRC model.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. hills, Ma ager Nuclear Regulation cnd Safety Subscribed and sworn to before me this G/
day of (/ enu o > <1980.
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