ML20056F062

Quad-Cities Nuclear Power Station,Unit 1 Cycle 12 Startup Test Results

ML20056F062
Person / Time
Site:	Quad Cities
Issue date:	08/19/1993
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20056F058	List: ML20056F057 ML20056F062 ML20056F063
References
NUDOCS 9308260015
Download: ML20056F062 (9)

Text

-,

+

6 QUAD-CITIES NUCLEAR POWER STATION UNIT 1 CYCLE 12 STARTUP TEST RESULTS 1

l t

l smGOUisTRTUP

}

9308260015 930819 D DR ADOCK 0500 4 y6 t

gu >

i . (

r i i . ,

~

l \

l .

l i i

i I

l i

i i

i TABLE OF CONTENTS Test No. Title Page .

1 Shutdown Margin 1

{

2 Core Verification 2  !

3 Initial Criticality 2  ;

1 4 TIP Reproducibility and 3 Core Power Symmetry Analysis  :

l 1

SDdGR'.UISTVTUP

'1. Shutdown Margin Demonstration and Control Rod Functional Checks  ;

Purpose l 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  ;

i fully inserted.

criteria If a shutdown margin of 0.322% oK (0.25% + R + B 4 C settling penalty) cannot be demonstrated with the strongest control rod fully withdrawn, i the core loading must be altered to achieve this margin. The core reactivity has been calculated to be at a maximum 4000 mwd /ST into the cycle and R is given as 0.032% AK. The control rod B4 C settling penalty for Unit One is 0.04% AK.

Results and Discussion On January 5, 1991 and April 19, 1991, control rod M-7 was fully withdrawn to demonstrate that the reactor would remain subcritical with the strongest rod out. This maneuver was performed twice due to a change in the cooling water alignment in the reactor between the two dates. Rod M-7 was calculated by GE to have the highest worth with the ,

core fully loaded. The strongest rod out maneuver was performed to -

allow single control rod withdrawals for CR0 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 No unexpected reactivity insertions were observed when any of the 177 control rods were withdrawn and all control rod drives functioned properly.  !

General Electric provided rod worth information for the two strongest diagonally adjacent rods L-6 and N-6 with rod M-7 full out. This method provided an adequate reactivity insertion to demonstrate the desired shutdown margin. On April 21, 1991, a diagonally adjacent shutdown margin demonstration was successfully performed. Using the G.E.

supplied rod worth for M-7 (the strongest rod) and diagonally adjacent  ;

rods L-6 and N-6, it was determined that with M-7 at position 48, L-6 at position 48, and N-6 at position 08, a moderator temperature of 134cF, i and the reactor subcritical, a shutdown margin of 0.926% AK was i demonstrated. The G.E. calculated shutdown margin with M-7 withdrawns )

and 68cf reactor water temperature was 2.533% AK at the beginning of J cycle 12.

l At approximately 4000 mwd /ST into cycle 12 a minimum calculated shutdown l margin of 2.501% oK will occur with M-7 fully withdrawn.

1 l

snaontuisnerce I

3

~

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 0.065% oK after correcting for temperature and .

period. This initial critical demonstrated that the actual shutdown  :

margin at the beginning of cycle 12 was 2.598% AK and 2.566% AK at 4000  :

mwd /ST into cycle 12.

2. Core Verification Purpose  :

The purpose of this test is to verify proper core location and orientation for each core fuel assembly.

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 One Cycle 12 core was verified on January 4,1991. Fuel assembly orientation, seating, and ID serial number were verified for each assembly. Two passes were made over each assembly. The first pass to verify orientation and seating of assemblies. The second pass 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 January 8, 1991, 16 fuel assemblies were reverified due to moving 4 fuel assemblies for LPRM flange work. Two passes were again made for orientation, seating and ID verification. All 16 assemblies were found to be properly seated and orientated in their designated location.  !

The bundle ID numbers are shown in Figure 1. f

3. Initial Critical Prediction Purpose The purpose of this test is to demonstrate General Electric's ability to >

calculate control rod worths and shutdown margin by predicting the insequence critical.

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

STMGRiUISTRTUP

^

?

Results and Discussion

{

On April 24,1991, at 0424 hours0.00491 days <br />0.118 hours <br />7.010582e-4 weeks <br />1.61332e-4 months <br /> the reactor was brought critical with reactor water temperature at the time of criticality of 170cF. The oK difference between the expected critical rod pattern at 680F and the actual critical rod pattern at 170oF was 0.00276 AK from rod worth tables supplied by General Electric. The temperature effect was

-0.00175 oX from General Electric supplied corrections. The excess reactivity yielding the 166 second positive period was 0.00036 AK. These reactivities result in a 0.00065 AK difference (0.0656% AK) between the expected critical rod pattern and the actual rod pattern. This is within the 1% AK required in the criteria of this test, and General Electric's ability to predict control rod worth is, therefore, successfully demonstrated.

i

4. Core Power Distribution Symmetry Analysis I

Purpose The purpose of this test is to determine the magnitude of indicated core power distribution asymmetries using data (TIP traces and OD-1)  ;

collected in conjunction with the CMC update. '

Criteria A. The total TIP uncertainty (including random noise and geometric f uncertainties obtained by averaging the uncertainties for all data sets) must be less than 9%.

t B. The gross check of TIP signal symmetry should yield a maximum deviation between symmetrically located pairs of less than 25%. [

t Results and Discussion  !

Core power symmetry calculations were carried out based upon a computer [

program OD-1 data run on May 9, 1991 and July 9, 1991 at 100% power. l The average total TIP uncertainty from the two TIP sets was 4.260%.

The random noise uncertainty was 0.926%. This yields a geometrical '

noise uncertainty of 4.158%. The total TIP uncertainty was well within the 9% limit. l r

Table 1 lists the symmetrical TIP pairs and their respective average -

deviations. Figure 1 shows the core location of the TIP pairs and their '

average TIP readings. The maximum deviation between the symmetrical pairs was 12.763% for pair 32-41. The maximum deviation between symmetrically located pairs for the single 0D-1 data run was well within the 25% limit.

stucasuisirnir  ;

i l

I 5

~

The method used to obtain the uncertainties consisted of calculating the i

average of the nodal ratio of TIP pairs by:

3 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)2 1/2 o_= j=1 i=5 4

R (18n - 1)  ;

o is multiplied by 100 to express o, as a percentage of the ideal  ;

value of o, of 1.0.

% o, = g,x 100 l

The total TIP uncertainty is calculated by dividing % ir, byV 2 in i 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 i each node for nodes 5 through 22 is calculated by:

~

MT NT

= 1 I I BASE (N, M, K)

BASE (K) NT x MT M=1 N=1

~

where NT = number of runs per machine - 5 MT = number of machines = 5 BASE (K) = average reading at nodal level K, K = 5 through 22 1

1 The random noise is derived from the average of the nodal variances by:

22 MT NT

~

1/2

%g noise = K= M= N= Bd5 (k) x 100 18 (NT x MT -1)

Finally the TIP geometric uncertainty can be calculated by:

% o geometric = (% s total' - % o noise')2/* l Table 1 STMGR\UISTRTUP l

.i, CORE SYMMETRY i Based on OD-l's From 1 05-09-91 and 07-09-91 (100% power) l

, 1 SYMMETRICAL TIP AVERAGE PAIR NUMBERS ABSOLUTE DIFFERENCE  % DEVIATION a-b T= T - T,  % = 100 X T/((T + T,)/2) 1-6 3.770 4.376 2-12 6.230 6.677 3-19 6.030 6.508 ,

4-26 4.600 5.043 5-33 2.785 5.448 8-13 6.930 5.560  !

4 9-20 2.645 2.270 10-27 2.550 2.239 11-34 1.875 1.807 15-21 13.750 11.159 l 16-28 11.255 9.013  ;

17-35 3.280 2.901  !

18-39 1.590 2.638 i 23-29 4.180 3.326  ;

24-36 3.040 2.797 ,

25-40 2.150 3.315 l 31-37 2.380 2.040  ;

32-41 5.760 12.763  :

t 22 Average % Deviation = 5.021 1 T,= lE T,(K) /18 l i=5 '

t i

i i  :

l l

l STMGR\UISTRTUP 1

. }

l FIGURE 1  !

j. .. .

=n i

OUAD CITIES UNIT 1 REACTOR i j ,_ w X s=raa -m l 7 $3 Ms $3: E udT1h8CSaft AmeCl WO*! - 9.S *.

i. x. m's m's m's m'm aa a X .- - - -- - m l j;

<p y L y y y w y up y, . - t $$ 79 4 .

M

[ sg2 m .gia"l'np y i"p' sp mg. sp y sp 't*p l t <am ma mm an sa ma mm mm mm mm mm e,. i

[ & '* =m * "i Wim m 'a ma sp" m* p"* 11' !E l' " l

.M 310 77 1. . ..1 3, 3 7 ogg j e

sp a Es-Es Es En Es Es is Es is mp m,m c mm m= ma mm ma mm ma ta m mm mm mm mm 1i%'n i

4 C e!$ n mg mp EI'E3 yy ES E3 EE y EI ES EI  ;

,_ ='m =m mm mm mm mar, m == m 'i mm mm == mm mm %m'.

=  :

.% S- E I =

,_ m'a me =m wmS mm mm mm mm mmW mm me == =m mm m=  ;

w

-s v LWD LTJ mm tv

~

m+0 LTJ m>

tg LW

• =f' mm lT#J mm LW m'=fW m m+J kTa .LW my.

4W, m

y mamm LW W yW 9 yW 9 mm mm mm mm 9 2 LWJ.

nW.p9 LTJ Lg5 mm 9 LTJ Lig ms y

1 l

,- eg i'=y mp EiB Es %B um EP E3 EN EN %g E3 my E3 E3 l

,,_ ma mm mm m%ss m'm mm mm mm m'm mm mm ma ns l,

4 , _ . . .l.D W.qE mp sp E3 mp m_45mp sp E3 mp a mm mm ma ss am mm mm mm a tuse ss um mm m's y mp m4m mp a ,

4 49 mp m4m sp y mm mm am mm mm mm mm .m' a nn um mm mm ms y mp siu mp m4m ig4s y Spa s  !

Y "# mm Y YY mm Y mm Y mm Y mm Y mm Y mm Y YY

. .,m ma mm mmmm ms  :

I~

f= mg QiED 45 EJ ES E3 yi EK'EP n l

&a mm mm mm mm m_45 mm.m m mm mm mm as .

. 49 ED ED ED 45 49 49 45 &] )

l. A 443 4 Am mm mm mm e n: m am mm ms =4 4 4 4 l

~

& E3 ES ED Epm 45 a:

I 4

, sa mm mm mm ma 1 1 1 o . j.I . , .. .,, , .. .j . ,,.I .,.1.I .!.L ?.

. . ... f .j . . .j . . . . . E

. .,, ,,, ,. . f .j . .f ... .g

\ ,

I J

4 i

._______.._._--.__.....____.,__l

1

~

FIGURE 2 e c :nm l UNIT ONE l 4 . . i i l

2 61 '06 0l .63I.7g0l 48!0g .

i i . . . .

S ,

i a

_3y _ _ _ , . _ _ 60_, , _ . _ _ (U,_ _ ,,i

, , ,-- TIP/LPRM i . Axis of ig i i 8 i e i-g '

j j j j l , , j Symmetry 52

{l ,

30 l4 . 7p 0 10$!.{25j 11f,41{ l .11b. y0! .11 $ .g5!

. . . i i

,g . ,.l.

e e s 33 . _ _ 14.i _l, _i_ . '.35'. ' '.

8 i

__ _ 2 08 *  !

u . . . . 3 6._- _ _ ' _3.7._ . _ _. . . .

e

. I e i . . . .

i e i 3 . .

3 . . . .

u . . .

___i..

i . 8 i 8 .

. __.__ _ i . __.. _ _i

• L191.2g5l 43.2g0 L 12B.y5!  %. [.

l 8(l.960

. .! d. , . . . . .

. . _ . . _ . _z7_, .__ 28 i .n  ;.9 31 __ _ _ . _ _ .12. _ _

, i m._ i

_ _i i .

. i i_ ...

i. e . , _ .1._ g .

. . . . ; . ) i '

i i . . _.,_

I e . . . I i i e P 11$.1 B0 l 10J.35 i Iz7. or55l 107 170l l 6 '{ . 9g0 l l 94l.1!<5 l 11b .e',50j e'i 4 .

l el e, r

' i 22;____l- 2 31

• l 19 l Ji i 21i 1 24 __ 23!

, i i

i i  ; .

. ., , . . . . e.

g g i

. . i

... . g . . . . . _._

a6  ; 90l.1 5! 121.g5I 12il .c l 139100l L 3Cl.5 0l 114.go] .58 4 0l l l 12i i 13 I l Id lg16!  ! '17 l_ _ _ *_ ' _1_81

-i. 86 M.. .

. i i

, e i . .

3 f i__ i 3

=--Li  :  : l' i '

I'  : 'i'i! t 1: 76' 74 5l 116.5 -

l 112p.105l 111 8q $5 i l 1115.o 85l 104 7 30 t o l e

!c6i 9! I. 'All 7: 8i i l 10!  !

16 a

i i

e i

.O 1 i.

, .

• i . . . i . . .

u i . i e i i . i l l to l 71 815 8

96)415 j al(11oi  ! _92l.4;aO l 52ISI-d

' ! l c4 i

. c. 1

.e.

. 2. . Ji e. 4.

i

,_ i_ _5

. i 06

/ '

I i.

i

e. t.

g

. e.

)

l 7 L7 i  :  !

l

_l iI i. i, , . . t l 01 03 o$ of op 11 13 15 17 19 m r3 25 rr a R 33 36 Ir 3 h1 636567he SL S1 55 57 2 e uuna sammu.m (snuar tastestae ti. etas) Base e uma t use. (ommme i - =.- tur att Tzr unsuase) Avera Q .

Strto- .io . .

e um t ue==

a susta==u =e UNIT ONE POk'ER SYMMETRY AVERAGE BASE READINGS e asi- tamous"* (NODE 5-22)

BASSED ON OD-l's from 5-9-91 (100% PO'w'ER) 7-9-91 (100% POk'ER)

.