ML20056F063

Quad-Cities Nuclear Power Station,Unit 2 Cycle 12 Startup Test Results

ML20056F063
Person / Time
Site:	Quad Cities
Issue date:	08/19/1993
From:	COMMONWEALTH EDISON CO.
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ML20056F058	List: ML20056F057 ML20056F062 ML20056F063
References
NUDOCS 9308260016
Download: ML20056F063 (9)

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i QUAD-CITIES NUCLEAR POWER STATION  !

UNIT 2 CYCLE 12 -

i STARTUP TEST RESULTS '

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l STMGR!tCSTRTUP 9308260016 930819 Qj PDR ADDCK 05000254 N:*

P PDR l} . . .

I TABLE OF CONTENTS l

l Test No. Title Page l

l 1 Shutdown Margin 1 2 Core Verification 2 3 Initial Critical 3 4 TIP Reproducibility and Core Power Symmetry 3 l

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- 1. Shutdown Marain Demonstration and Control Rod Functional Checks Purpose The purpose of this test is to demonstrate for this core loading in the most reactive condition during the operating cycle, that the reactor is subcritical with the strongest control rod full out and all other rods fully inserted.

l Criteria l

If a shutdown margin of 0.333% oK (=0.25% + R + 4B C :ettling penalty) cannot be demonstrated with the strongest control rod fully withdrawn, the core loading must be altered to achieve this l margin. The core reactivity has been calculated to be at a maximum 4000 mwd /ST into the cycle and R is given as 0.033% AK.

The control rod B4 C settling penalty for Unit Two is 0.05% oK.

Results and Discussion On April 11, 1992, control rod H-9 was fully withdrawn to l

demonstrate that the reactor would remain subtritical with the strongest rod out. This rod was calculated by GE to have the highest worth with the core fully loaded at the beginning of the cycle. The strongest rod out maneuver was performed to allow single control rod withdrawals for CRD testing.

Control Rod functional subcritical checks were performed as part of control rod friction testing. No unexpected reactivity insertions were observed when any of the 177 control rods were withdrawn.

General Electric provided rod worth information for the two strongest diagonally adjacent rods G-10 and J-10 with rod H-9 l fully withdrawn. This method provided an adequate reactivity  !

insertion to demonstrate the desired shutdown margin. On April j 11, 1992, a diagonally adjacent shutdown margin demonstration was l successfully performed. Using the G.E. supplied rod worth for H-9 (the strongest rod) and diagonally adjacent rod G-10, it was determined that with H-9 at position 48, and G-10 at position 24, a moderator temperature of 137oF, and the reactor subcritical, a shutdown margin of 0.592% AK was demonstrated. The G.E.

calculated shutdown margin with H-9 withdrawn and 680F reactor 1 water temperature was 3.001% AK at the beginning of Cycle 12.  !

At approximately 4000 mwd /ST into Cycle 12 a minimum calculated shutdown margin of 2.968% oK will occur with E-4 fully withdrawn.

G.E.'s ability to determine rod worth was demonstrated by the accuracy of their in-sequence criticality prediction. The oK difference between the expected critical rod pattern and the actual critical rod pattern was determined to be 0.1154% AK after 1 correcting for temperature and period. This initial critical demonstrated that the actual shutdown margin at the beginning of cycle 12 was 3.1164% oK and 3.0834% oK at 4000 mwd /ST into cycle 12.

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2. Core Verification i Purpose  !

The purpose of this test is to verify proper core location and .

orientation for aach core fuel assembly. 1 Criteria Prior to reactor startup, the actual core configuration shall be verified to be identical to the planned core configuration.

Results and Discussion The Unit Two Cycle 12 core was verified on March 17, 1992. Fuel ,

assembly orientation, seating, and ID serial number were verified for each assembly. Two inspection passes were made over each ,

assembly. The first pass was made to verify orientation and seating of rissemblies. The second pass was made to verify bundle ID numbers. A video camera was used during the inspection. All assemblies were found to be properly seated-and orientated in their designated locations.

On March 21, 1992, 24 fuel assemblies were reverified due to the unload and reload of 4 fuel assemblies for control rod J-14 drive replacement. Two passes were again made for orientation, seating ,

and ID verification. All 24 assemblies were found to be properly  ;

seated and orientated in their designated location. Similarly, on 1 March 23, 1992, 22 fuel assemblies were reverified due to the 1 unload and reload of eight fuel assemblies to allow drive I replacement for control rods P-10 and P-ll. Two passes were again 1 made for orientation, seating and ID verification. All 22 fuel assemblies were found to be properly seated and orientated in the ,

designated locations.  :

The bundle ID numbers are shown in Figure 1.

3. Initial Critical Prediction Purpose  ;

i The purpose of this test is to demonstrate General Electric's I ability to calculate control rod worths and shutdown margin by l predicting the insequence critical.

Criteria General Electric's prediction for the critical rod pattern must agree within 1% 6K to actual rod pattern. A discrepancy greater than 1% AK will be cause for an On-Site Review and investigation by Nuclear Fuel Services.

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l Results and Discussion On May 8, 1992, at 2041 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.766005e-4 months <br /> the reactor was brought critical with reactor water temperature at the time of criticality of 165cF. The oK difference between the expected critical rod pattern at 68cF and the actual critical rod pattern at 165oF was 0.002894 from rod worth tables supplied by General Electric. The ,

temperature effect was -0.00145 oK from General Electric supplied  ;

corrections. The excess reactivity yielding the 215 second  !

positive period was 0.00029 AK. These reactivities-resulted in a 1 0.001154 AK difference (0.1154% oK) between the expected critical rod pattern and the actual rod pattern. This is within the 1% oK  ;

required in the criteria of this test, and General Electric's ability to predict control rod worth is, therefore, successfully demonstrated.

4. Core Power Distribution Symmetry Analysis Purpose The purpose of this test was to determine the magnitude of l indicated core power distribution asymmetries using data (TIP traces and OD-1) collected in conjunction with the CMC update.

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l A. The total TIP uncertainty (including random noise and geometric uncertainties obtained by averaging the  ;

uncertainties for all data sets) must be less than 9%.

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j l 3 B. The gross check c? TIP signal symmetry should yield a maximum deviation between symmetrically located pairs of less than 25%.

Results and Discussion Core power symmetry calculations were performed based upon computer program 00-1 data runs on May 20 at 1303 and 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />, i both at 99.2.% and 98.9%, power respectively. The average total TIP uncertainty from the two TIP sets was 3.230%. The random ,

noise uncertainty was 1.150%. This yields a geometrical uncertainty of 3.018%. The total TIP uncertainty was well within  :

l the 9% limit. I Table 1 lists the symmetrical TIP pairs and their respective average deviations. Figure 1 shows the core location of the TIP pairs and the average TIP readings. The maximum deviation between symmetrical TIP pairs was 8.51% for pair 5-33. Thus, the second criterion, mentioned above, was also met.

1 STMGR\U2STRTUP

The method used to obtain the uncertainties consisted of calculating the average of the nodal ratio of TIP pairs by:

n 22 1 I I Rij

_R = 18n j=1 i=5 where Rij is the ratio for the ith node of TIP pair j, there being

n such pairs, where n=18. ,

Next the standard deviation of the ratios is calculated by:

n 22 I I (Rij - R)" 1/2 o_= j=1 i=5 R (18n - 1)

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as is multiplied by 100 to express ok as a percentage of the ideal value of og of 1.0.

% oi = ok x 100 The total TIP uncertainty is calculated by dividing % ok by T/ 2 -

in order to account for data being taken at 3 inch intervals and analyzed on a 6 inch nodal basis.

In order to calculate random noise uncertainty the average reading at each node for nodes 5 through 22 is calculated by:

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1 I I BASE (N, M, K) l BASE (K) = NT x MT M=1 N=1 ,

where NT = number of runs per machine = 5 l MT = number of machines = 5 l BASE (K) = average reading at nodal level K, K = 5 through 22 The random noise is derived from the average of the nodal variances by:

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-2 1/2 i I I I BASE (N, M K) - BASE (K) '

%s noise = K=5 M=1 N=1 BASE (K) x 100 l 18 (NT x MT -1)

Finally th'e TIP geometric uncertainty can be calculated by:

% a geometric = (% o total - % o noise")'/2

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Table 1  !

I CORE SYMMETRY l Based on OD-l's From i 05-20-92 at 1303 Hours and 2045 Hours  !

(99.2% and 98.9% Power Respectively) l l

SYMMETRICAL TIP AVERAGE l

% DEVIATION PAIR NUMBERS ABSOLUTE DIFFERENCE a-b T= T - T,  % = 100 X T/((T + T,)/2) ,

1-6 0.48 0.71 2-12 5.06 5.48 .

3-19 3.32 3.33 4-26 2.66 3.07  !

5-33 3.15 8.51 ,

8-13 1.43 1.28  !

, 9-20 1.87 1.86  ;

l 10-27 1.38 1.33 11-34 5.51 6.07 i 15-21 2.18 2.02 16-28 3.54 3.53 l 17-35 2.60 2.52 l 18-39 2.11 3.59 j 23-29 1.14 1.07 .,

24-36 5.57 5.56 ]

25-40 3.65 5.32 '

31-37 6.95 7.06 32-41 0.46 1.13  :

1 22 Average Deviation = 3.52 T,= I T,(K) /18 i=5 l '

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