ML19261B156
| ML19261B156 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/08/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7902140084 | |
| Download: ML19261B156 (2) | |
Text
e TENNESSEE VALLEY AUTHORITY CH ATTANCO O A. TENN ESSEZ 37401 500C Chestnut Street Tower II FES 8 1979 Director of Nuclear Reactor Regulation Attention:
Mr. S. A. Varga, Chief Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Com:aission Washington, DC 20555
Dear Mr. Varga:
In the Matter of the Application of
)
Docket No. 50-327 Tennessee Valley Authority
)
Enclosed is the information requested by the Core Performance Branch reviewer during the telephone conversation on January 10, 1979. This fig.re provides the results of the Westinghouse analyses of the total core peaking factor, F (z).x Prel, as a function of core height for normal plant operations durin Cycle 1 of Sequoyah Unit 1.
The results were based on a full "18 case" analysis with a 15%AI Constant Axial Offset Control (CAOC) band.
These results were-obtained by the standard synthesis procedure described in WCAP 8385 utilizing the following technical specification consistent radial peaking factors:
Unrodded Plane F (z)
F "#
x 1.03 x 1.05 = 1.52 xy Rodded Plane F (z) dded F
x 1.03 x 1.05 - 1.71 xy The figure illustrates that the limiting Fh(z) x Prel calculated points as a function of core elevation will not exceed the current 2.25 x K(z)
LOCA limit.
Therefore, no APDMS surveillance will be required for 100 percent power operations.
Very truly yours, n
~
S f.'
/
J. E. Gilleland Assistant Manager of Pcwer Enclosure b b* \\
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Bottom CORE HEIGHT (FT)
Top SEQUOYAH UNIT 1 MAXIMUM F T.P VS.
AXIAL HEIGHT q
REL DURING NORMAL PLANT OPERATION L
2.25 F
=
q