ML19317D651

Cycle 2 Power Distribution Comparison Rept.

ML19317D651
Person / Time
Site:	Oconee
Issue date:	06/03/1975
From:	DUKE POWER CO.
To:
Shared Package
ML19317D647	List: ML19317D646 ML19317D651
References
NUDOCS 7912060884
Download: ML19317D651 (2)

Text

(

f<

OCONEE NUCLEAR STATION UNIT 1 Cycle 2 Power Distribution Comparison Report This report provides a comparison of the radial power distributions measured shortly after the first refueling of Oconee Unit 1 with those predicted by Babcock & Wilcox Company's PDQ computer code calculations.

The measured core power distributions were obtained from the fixed incore detector data. The measured data were corrected wherever necessary by replacing signals from inoperative detectors with values obtained by interpolation or extrapolation of signals from adjacent detectors.

The predicted power distributions were obtained from two-dimensional PDQ thermal-hydraulic feedback calculations, using a standard two-zone repre-sentation for each fuel assembly in one-quarter core geometry.

Figure 1 shows the comparison of the measured and calculated radial power distributions corresponding to a core burnup of approximately 23 EFPD into Cycle 2. The difference between the measured and the calculated peak radial power is 4.49 percent, and the root mean square percent difference between the measured and the calculated radial power densities for all fuel as-semblies is 3.79 percent. Therefore, the measured and predicted core power distributions agree quite well.

l

' ' R &

L

. FIGURE 1 COMPARISON OF MEASURED AND CALCULATED RADIAL CORE POWER DISTRIBUTIONS 8 9 10 11 12 13 14 15 1.21 1.17 1.20 1.40 0.95 1.17 1.00 1.09 H

1.02 1.18 1.22 1.36 0.95 1.21 1.00 1.02 1.03 1.16 1.02 0.84 0.65 0.92 1.02 K

1.13 1.17 1.05 0.85 0.63 0.93 1.00 1.14 1.06 0.94 0.80 1.35 0.82 b 1.16 1.07 0.90 0.85 1.29 0.84 1.56 0.96 0.91 1.14 M

1.49 0.98 0.97 1.10 N 0.96 0.91 0.76 1.01 0.90 0.74 0 0.75 0.73 P

R xx.x Measured yy.y Calculated (PDQ)

CONDITIONS Measured Calculated Core Average Burnup (EFPD) 23 25 Power Level (%FP) 98 100 Boron Concentration (ppm) 782 782 Control Rod Group Position (%wd)

Groups 1-5 100 100 Group 6 88 100 Group 7 17 17 Group 8 7.2 37.5

. _ _ _ _ _ _ _ . , _ - - .~