ML20056A720

Proposed Tech Spec Page 3.10-9

ML20056A720
Person / Time
Site:	Indian Point
Issue date:	07/27/1990
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20056A719	List: ML20056A718 ML20056A720
References
NUDOCS 9008090088
Download: ML20056A720 (1)

Text

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e Fnt Enrincerinr Heat Flux Hot Channel Factor, is defined as the allowance on heat flux required. for manufacturing tolerances. The engineering factor allows for local variations in enrichne ,t , pellet density and diameter, surface area of the fuel rod and eccentricity of the gap between pellet and clad. Combined statistically tha net effect is a factor of 1.03 to be applied to fuel rod surface heat flux.

Fa" Nuclenr Enthniny Rise Hot Chcnnel Paetor, is defined as the t itio of the integral of linear power along the rod with the highest integtated power to the average rod power.

It should be noted that Fa" is based on an integral and is use6 as such in the DNB calculations. 1,ocal heat fluxes are obtained by usirg hot channel and adj acent channel explicit power shapes which tak:, inte account variations in horizontal (x.y) power shapes throughout the core. Thus the w' horizontal power shape at the point of maximum heat flux is not necessarily directly related to Fu"-

An vpper bound envelope of Fn*" specified in the COM times the normalized peaking factor axial dependence of K(Z) specified in the COM has been determined consistent with Appendix K criteria and is satisfied for' OFA transition mixed cores m by all operating maneuvers consistent with the technical specifications on power distribution control as given in Section

_ 3.10. The results of the loss of coolant accident analysis based on this 5 upper bound normalized envelope , K(Z) , specified in the COM demonstrates l a peak clad temocrature not greater than 2049'F, which is below peak clad temperature limit of 2200 F. m When an Fg measurement is taken, both experimental error and manufa,turing tolerance must be allowed for. Five percent is the appropriate allowance for a full core map taken with the movable incore detector flux mapping system and three percent is the appropriate allowance for manufacturing tolerance, r

In the specified limit of Fa" there is an 8 percent allowance for uncertainties which means that normal operation of the core is expected to result in Fa" s Fa "/1.04, R

where Fa k" is the Fa" limit at Rated Therma 1 Power specified in the COM. The logic behind the larger uncertainty in this case is that (a) normal parturbations in the radial power shape L

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__ 3.10 9 Amendment No. JJ, #p, #f. fl. 7J, FF,

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