ML19327A293

Forwards Westinghouse Rept, ECCS Performance Analysis W/ Rate Dependent Burst Model.

ML19327A293
Person / Time
Site:	Sequoyah
Issue date:	07/31/1980
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML19327A294	List: ML19327A293 ML19327A295
References
NUDOCS 8008050319
Download: ML19327A293 (1)

Text

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400 Chestnut Street Tower Il July 31, 1980 Director of Nuclear Reactor Regulation .

Attention: Mr. A. Schwencer, Chief Light Water Reactors Branch No. 2 Division of Licensing

'U.S. Nuclear Regulatory Commission Washington, DC. 20555 D',ar Mr. Schwencer:

In the Matter of the Application of ) Docket No. 50-327 Tennessee Valley Authority )

' Westinghouse has performed an evaluation which describes the effect of a rate dependent burst model on emergency core cooling system per- ,

formance for the Sequoyah Nuclear Plant unit 1. The net effect is a reduction in allowed total peaking factor to 2.237.

Enclosed for your review is the Sequoyah evaluation. The results are 1 based on a full "18 case" analysis with a +5% AI Constant Axial Offset i Control 3and. The standard synthesis procedure described in WCAP-8535 l was used with the following technical specification radial peaking factors.

Unrodded plane F (Z) d' F""# x 1.03 x 1.05 = 1.50 xy Rodded plane F (Z) r dded F

xy- x 1.03 x 1.05 = 1.71 The necessary technical specification for the total and radial peaking factors will be revised in accordance with 10 CFR Part 50.59.

Very truly yours, TENNESSEE VALLEY AUTHORITY

.TW.WA

. M. Mills, Manager Nuclear Regulation and Safety Enclosure s

8008050$1j

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