ML20108A492

Cycle 8 Startup Test Results

ML20108A492
Person / Time
Site:	Quad Cities
Issue date:	11/08/1984
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20108A480	List: ML20108A477 ML20108A492
References
ID-TS2-B, ID-TS2-B-03, ID-TS2-B-3, NUDOCS 8411150012
Download: ML20108A492 (10)

Text

{{#Wiki_filter:.,;_'.i *'.

-q 3

'I ^ ) .[ 4 o s 4 V t r. 'h[y.. .~ 4 s L, ; + 1 f+i:,$: d S ( 4 - 3 1 ID/TS2-B" 4 . QUAD-CITIES NUCLEAR POWER STATION ~ UNIT 1 CYCLE 8 STARTUP TEST RESULTS l l I I 1 _m PDR '..p_ _ _ 3-

.[ m.pt i mg ,<3..,.,.t- =v ! r.. - m' -g.pp t-- t

. s,-.-

s e.* f. D.i.r' i c.,.. c' .,-, A.y ~ t' ~.e

+3_ W,,T

6:, ~.- S. i l 4

iW .A e t s -i x_+ ;s u.-; -..,. * . ~, n

y, :s,sA_ y.q t

M_ - f g t. s f. g s [ ara s' J4e f j-r i- ~ j .e',

_

- - J, y,

1 .s. 6 .+. v_ . y m g=, w o_ .c 1 c --u' ,,4 a .s..,..

m. -

s s s w ,,~

~

_ v s = (.. w= 1 1 4 s " 1 y yL ? y'cs p( e , l9,2 s t t, g .t v (. -: +

• s p"0,.

si p r s '? ] * - _ ^ "-N b __. _ - _ - + ~ .a ,.,I .h= . I ._3 ,l' a 4 9'.: - 4-m..- c s a. 4-r. 3. U h '5 s xo - ' ~ + y v1 -. n 3.. n,. h ~,; c- ,., 3' ..$.... 5 ) t t 4 s n _ g;_ .:r:. n y 't

"[

c - 3: y 1, g.= ,.#. m 1 r ( t w.c s ~ ,.,,s 3 .a c s 2 x w =, l ? 4 i = n.; o ~ L-I h.' 1. TABLE OF' CONTENTS' O V- -4 Test No.

Title:

Page ,x a il -

Scram Timing 1

a '[ ',' '^.. 2: jShutdown Margin' - 3 i 1, fl (o ~3 >

Initial Critical.

'4 ' - . 4~

TIP Reproducibility and-Core Power Symmetry 4

5 ) L 0 e i 155, a. 1 a 4 L =b?. e. .+,.h,y.--,.c, .,,,4w,-+...e#.

&y m

4= y,.

9

-8 n;- p' ' g,;a-ay,lyx-p r w, ++ +m v ~,c bl -jQ fjji w.- ), d y j.:9 ' pl;,,, ..g, e t x . 3' y ,=

, ( ++,

~ ,j, 1 Kb!l"J2~ "I'. : 3ControlRodScramTiming) ] 8 + -- Pu-- + 'rpose.. r g',,(' L;- W( i y The. purpose'of this~testiis to demonstrate;thelscram capability ofi ..A4 -all ofithe~operableicontrol' rods'in compliance with Technicall 4 " N, Specifications 4.3.C.'1'and.4.3.C.2-- 4 t. . Criteria ' "A. -The' average'~ scram insertion time,. based (on.the--de-energization cf.the scram pilotcvalve..solenoidszas time'zero,1of'all. operable 1 A ,' ~ control. rods:duringTreactor power operation _shallibe no' greater

than:

.% INSERTED FRON~ cAVG. SCRAM INSERTION. -FULLY WITHDRAWN. TIMES-(sec) S' O.375. - 20

. 0.900 -

550 .2.000~ 90 3.500~ .The average of the : scram insertion' times for the three fastest - E control rods of.all/ groups of four-rods in a two by two array. shall be no greater than: % INSERTED FROM AVG. SCRAM INSERTION FULLY WITHDRAWN TIMES (sec) 5 0.398 20 0.954 50' 2.120 90 3.800 If these times cannot be met, the reactor shall not be made supercritical; if operating, the reactor shall be shutdown immediately upon determination that average scram time is deficient. B. The maximum insertion time for 90% insertion of any operable control rod shall not exceed 7.00 seconds. If this requirement cannot be' met, the deficient control rods shall be considered inoperable,-fully inserted into the core, and electrically disarmed. Results and Discussion i .All 177 control rods were scram tested. The results are presented in Table 1. -The' maximum 90% insertion time'was 3.39 seconds for control rod P-5 (54-19).. Both criteria A and B were met. m1 ( _1 -L-.f

. 3 - j, -{'. '(j .q-4 1 i Table ~ 1". 2'~ t Control Rod' Scram Results' ~ , NUMBER [ REACTOR - ' AVERAGE TIMES FOR % INSERTED, SEC' '0F RODS ' CONDITIONS; ~ 5%' 20% 50%- 90%. 1 a

177 Cold

0.26'

0.49-

'O.961 1.66 177 Ho t'

0.28 10.67.

-1.45 - 2.55' i . t- ! '),* 1 1! J J 2 e / i l l t i {.,L

+ t ~ ~ j $;; M J M l i h s M. p px v y. yif K 4v.. km <3 y ~q .h U g' t Fc ~ -..Y J 22 IShutdown'Marain' Demonstration and Control. Rod Functional-Checks-W - 7 "E.

Purpose:

~ s s K (The:purpos'e of;this;! est' is' to demonstrate. for this corelloadingtin., 2 t S

thelmost reactive condition ~during-the operating cycle, that the-r f,

reactor

islsubcritical.with the strongest: control Jrod i full ~out. and ;

g ~" cN 'r calliother rodsifu11y5 inserted. a

Criterial -

r If.a : shutdown margin Lof' O.751% AK1(-0.25% +7R +lB C. settling penalty)~ 4 'cannot:be demonstrated with the strongest; control rod = fully withdrawn,~- cthel core loading must be' altered-to achieve;this'. margin.. The core ~ reactivity has beenicalculated to be.at a maximum 5000. MWD /T into

the, cycle,and R is givenLas 0.461%AK. The control rod B C settling 4

= penalty for Unit _ One is 0.04%aK.- Results'and~Discussionz On' June 25, 1984,- Leontrol rod C-11f(the rod which was calc'ulated by. ' General Electric.to-be~of the' highest worth) was fully.. withdrawn to

demonstrate that the reactor would remain subcritical with.the

-strongest rod full-out..This maneuver was performed to' allow cold control rod testing prior to the shutdown margin demonstration. Control Rod functional suberitical checks were performed as part of the-cold scram timing and 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 D-10 and D-12 with rod C-11 full out. This method provided an adequate reactivity insertion to demonstrate the desired shutdown margin. On-August 4, 1984, a diagonally adjacent shutdown margin demonstration was successfully performed. Using the G.E. supplied rod worth for C-11 (the strongest rod) and diagonally adjacent rods D-10 and D-12, it was determined that with C-11 and D-10 at position 48, and D-12 at position 12, a moderator temperature of 160 F, and the reactor suberitical, a shutdown margin of 1.208% A K was demonstrated. The G.E.-calculated shutdown margin with C-11 withdrawn and 68'F reactor water temperature was 2.227% A K at the -beginning of cycle 8. At approximately 5000 MWD /T into cycle 8 a minimum calculated shutdown margin of 1.766% A K will occur with G-13 fully withdrawn. Note that the' minimum shutdown margin shifts from rod C-11 at beginning of cycle to rod G-13 at 5000 MWD /T. m :d. 4 b

W. f.;;f L I ~' F ~ ? s

m. x mv Y.

j s. N e ,= --, x k ^ y wt J 'v' ';?G.E.'s'abilityft6ideterminerodworth[wasdemonstratediby;th'eTaccuracy-h w sof their in-sequence criticality' prediction. The A-K difference? !betweenfthe expected-critical rod pattern and;the actual critical'~ ( . rod: pattern wasl determined-to be;-0.15% A K., This' initial.' critical; y Edemonstrated that the~actualishutdown margin'at the beginning of-o scycle 8:was_2.077% A'Koa'nd that the predicted SDM will.;be.approximatelyj t L1.616% 'A KEat 5000 mwd /t -into (cycle 8. .~ s I ~ L3.. ; Initial'CEitical' Pre' diction '.lI~ ' Purpose l ~ ~ > / The' purpose of 'this test. is -to ' demonstrate General Electric's; ability' ~ ~ Lto calculate' control' rod worths ~and shutdown margin by predicting' ' the insequence critical. ' Criteria-General Electric's prediction for the~. critical' rod ~ pattern must? Y agree within 1%'A-K to. actual rod pattern. 'A discrepancy. greater 'than'1% A K in the non-conservative direction will be~cause for an-10n-Site Review and investigation;by Nuclear Fuel. Services. Results and Discussion 'On August 16,'1984, at 0940 hours the' reactor was brought criti. cal-with a reactor water temperature at the time of criticality of. -191*F. :The AK difference-between the' expected critical rod pattern at 68'F'and the actual' critical rod pattern at 191'F was 0.0014 from rod worth tables supplied by. General' Electric. The' temperature effect was -0.0023 AK from' General Electric-supplied corrections. ~ The excess reactivity yielding the.92'second positive period was 0.0006 AK.~ Thesel reactivities-result in a -0.0015 AK difference (-0.15% 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 pre. dict control rod worths is, therefore, successfully demonstrated. 4. Core Power Distribution Symmetry Analysis Purpose The purpose of this-test was to determine the magnitude of indicated core power distribution asymmetries using data (TIP traces and OD-1) collected in conjunction with the P-1 update. Criteria-L A. The total'TIP uncertainty.(including random noise aud geometric i-uncertainties obtained by averaging the uncertainties'for all data sets) must be less than 9%;' I B. The gross check:of TIP signal symmetry should yield a maximum deviation between symmetrically located pairs of less than 25%. 4. i-, --.-.,,-+.5-,---<--,,yvg---y.-- ~.-e.~--,,w r9 w. ~ w ,p+--.p,--#,~_ y m., 3 -<,,p. 9=v y,

, y _. u; i 3 'Re'sult's and Discussion Core. power' symmetry calculations were performed based upon computer program.0D-1 data. runs'on September. 25,1984,l at 99.7% power, and October 18,_1984, at 99.4% power..The average total.TIP uncertainty - from the two.TIP. sets was 4.056%. The random noise-uncertainty-was 0.935%. This yields a geometrical 1 uncertainty of 3.947%. The total ~ TIP. uncertainty was well'within.the 9% limit. Table ~2 lists the symmetrical TIP pairs and their respective deviations. Figure 1 shows the core location of the TIP pairs and the average TIP readings. The maximum deviation between_ symmetrical TIP pairs was 18.620% for pair 8-13. Thus, the second criterionf mentioned above, was also met. 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-o_= j!1 i=g (Rij - R)2 \\ R-(18n - 1) O is multiplied by 100 to express O as a percentage of the ideal R R value of U f 1.0. R %OR * "R x 100 The total TIP uncertainty is calculated by dividing % a, by 4 2 in order to account for data being taken at 3 inch intervaIs 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: MT NT 1 I I BASE (N, M, K) BASE (K) : NT. MT M=1 N=1 where NT = number of runs per machine = 4 MT = number of machines = 5 BASE (K) = average reading at nodal level K, K = 5 through 22.

. pp-. 7, _s: r. N.

g,.

~ ~ The random noise is derived from the average of the nodal variances - by: 22. MT NT ~ .-2 I 'I-

I-BASE (N, M, K)~- BASE (K)

. %a noise =! K=5,M=1 N=1 . BASE:(K) x 100 -18 (NT x MT.-1) Finally the TIP geometric uncertainty can be calculated by: % a: geometric ~=-(% a tota 1 - % a noise )\\ 2 2 9 1 L.

k .o 'a-4 j. Table 2 - i~ a ~ CORE-SYlefETRY h-Based'on OD-l's From 09-25-84-(99.7% power), and 10-18-84-(99.4% power) = .y- % = 100-x T/-T, + Tb - SYlefETRICAL TIP T= T, - Tb-PAIR-NUMBERS -ABSOLUTE DIFFERENCE % DEV!ATION-2 -a' b- ,1 '6 5.866 4.787 -2 '12.- 1.388 0.977-3 19 2.226 1.542 41 26 1.079 0.761 5 33~ 4.307 '6.761 8 13 17.581 11.969 9 20 10.016 7.679 10 27 9.166 '6.268 ' 11' 34 3.222 -2.670 15 '21 5.391 4.793 16 28 2.315 3.689 17 35 2.648 .1.824 18 39. ,3.007 2.672 23 29 6.700 5.740 24 36-4.021 3.015 25 40 0.338 0.347 31 37 11.434 7.563 32 41 5.551 7.366 22 Average Deviation = T = I T (K) /18 5.347% g g i=5 e...

x b FidultE 1 a l l i l l l l-m.T(_l 92+ L ! 78.A T# M l_L___L___.__* M. __l__"M.___L_g I a M'S # ## ifL _ _ l_ _ 1 / i i l I i, i i l i i, e i__ / P, l l i l l l l 1 L i o ffr'l.[T7TigT~i)Tg5i lifJ,p! isi.yl tz S __L. >_a_ ,L_1A, I 3 1 _ &, __,_ _ _M,.__ _ ' ___*S___L_ u i i I ,3 u i i i l i c/ l

• _- iS.'fi,~ T '151.l{, l2'7_. __W_

[2_9_ ^ I5 l I2s l 131 6f~~l6.Q3-l 7L4[\\_ ~" l 26 L M._ __I_ _ _ 2 1 3L 3 *- i 8 I i i l i !.i I I i l l l i i i i i ~i~ [5} l 0S.Q ! 109 7 l10 9 ~l II3. l fl1 22_. _l q_\\_.131.Q_j_ 97,7l' F 34 __I__ __!_ _19 i ab i 3' 4 2 15 l 2t_ l 2 5 I I I l l l ? i ol l l l l l e i__ l I I I L_ _I_ l I __l__ _E!.9]i lM_.gI II1.9/_IIS".IJ! L I l _ L_ f IlS.{'Sl l I l i 125.gll MW. I I J i 13 __./f_ _ _ _ i /F /6 i 17_ __l /J._ = _ _ ', i i !a l !a! I l l l ! l l l I I I l i I.. I m-171.Q'-, ; /S$.fp$/5,f'I gg i 1244[Il t i la a Gi vi __L_. 1 9, I /0 i l a i i e; i i Ia-.I lo l l i i i i I l I l l ~ C lif.,Ql,,!16.fli la ~ "~j)[3l_t_.___,g. l p I tt] J_(difl to m.. a / _t i i zi +: _ t. s i a. i i l l l 7 / .. _ _. l._ __ I__ _ _ L. __ L _ _ _ l_ _ a I i l 01 03 05 07 09 11 13 15 17 19 al 23 25 27 29 31 33 35 17 39 41 43 45 47 49 51 51 55 ST 59 G LPse, Loestion (Letter insteatee TIF asettne) g BASE 9 !#In,14eation (e-loestion for all TIF asettaea) O STRIN4 e nu r,eatt - NitMBER a som e.it.a. ~ . - -.}}