B12633, Responds to Request for Addl Info Re Question 10 Concerning NULAP5.Current Results w/NULAP5 Shown to Predict All Test Data Pertinent to Major Phenomenon Associated W/Small Break LOCA Response.Evaluation Will Be Submitted by Nov 1988
| ML20236C779 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/15/1987 |
| From: | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| B12633, NUDOCS 8710270329 | |
| Download: ML20236C779 (51) | |
Text
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ATOMIC POWER COMPANY C CONNECTICUT YANKEE TELEPHONE -
P.o, box 270 B E R L I N, CONNECTICUT HARTFORD. CONNECTICUT 06141-0270 203-866-5000 October 15,1987 Docket No. 50-213 B12633 h
e e Re: 10CFR50.46 O Un y N
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U. S. Nuclear Regulatory Commission Attn: Document Control Desk
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p '.'7 2 1
Washington, D. C. 20555 W g
References:
(1) E. 3. Mroczka letter to U. S. Nuclear Regulatory Commissiohj
" Additional Information on NULAP5," dated July 10,1987.
(2) F. M. Akstulewicz letter to E. 3. Mroczka, "Small Break LOCA Code - NULAP5," dated April 27,1987.
Gentlemen:
i Haddam Neck Plant Response to Requests for AdditionalInformation on NULAP5 In Reference (i),' a response to Question 10 of those requested by Reference (2) l was made. Subsequently, during a July 17, 1987 conference call with the NRC Staff and their consultant, additional information pertaining to Question 10 was requested.
In response to your verbal requests, Connecticut Yankee Atomic Power Company (CYAPCO) hereby provides the following figures:
o Log of surface heat transfer coefficient vs. time (where the heat transfer coefficient has units of BTU /hr/f t2 /op), ,
o Steam velocity vs. time (in the node with peak clad temperature (PCT)). ]
o Liquid velocity vs. time (in the node with PCT). j o Void fraction vs. time (in the node with PCT).
o Coolant temperature vs. time (in the node with PCT).
These figures are provided in Attachment I for each of the four small break cases submitted in response to Question 10. (The cases included are the 0.1 f t2 discharge leg break with reactor coolant pumps off and the three 0.02 ft 2 discharge leg breaks, all run with varying time step sizes). These figures provide clarification for the clad surface temperature response calculated by l 8710270329 871015 PDR ADC':K 05000213 I g
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( U. S. Nuclear Regulatory Commission
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l B12633/Page 2 ;
October 15,1987 I
NULAPS . during the loop seal clearing portion of the small break LOCA j transient. As the loop seal begins to clear, the core level is depressed causing an !
Increase in clad surface temperature. During the loop seal clearing process, the clad surface heat transfer coefficient may increase slightly due to an increase in .
the coolant velocity in the core. This phenomenon is shown on Figure 1-A and 1-B between 180 and 250 seconds. The increase in clad surface heat transfer coefficient causes a reduction in the rate of clad heat-up. This increase in coolant velocity and heat transfer coefficient is mainly attributed to transient ' :
core-level behavior that results from the slow drainage of water held in the steam generator tubes during the loop seal clearing process.
During another conference call held on August 12,1987 with the NRC Staff and their consultant, further information was requested on time step sensitivities of the loop seal clearing portion of the small break LOCA transient. Attachment 2 provides figures for the 0.1 f t2d scharge leg break with RCPs of f. These were plotted based on an input time step of 0.002 seconds. In addition, other figures are'provided to clarify the reason why the coolant velocity increases in the hot assembly channel during the loop seal clearing process. j Figures 5-A through 5-F provide the surface heat transfer coefficient, coolant velocity, void fraction, coolant temperature, and hot rod clad surface temperature for the node with the peak clad temperature. Figure 5-G shows the collapsed water level in the 36 assembly center channel. Figure 5-H shows the liquid mass contained in the upside of the steam generator tubes for each loop.
Figure 5-1 provides the pressure transient.
1 Figures'5-3 through 5-Y are additional figures provided to clarify the reason why the coolant velocity increases in the hot assembly channel during the loop seal clearin'g process as core level reaches a minimum value. Figures 5-3 through 5-Q {
provide junction vapor velocities for the lower plenum regions as well as the first l and last junctions in each of the two core channel volumes. Figures 5-R through 5-W provide volume void fractions for the lower and upper plenum volumes.
Figures 5-X and 5-Y provide a comparison of the density head in each of the two core channels. Figure 5-Y shows this comparison on an expanded vertical scale.
The time frame of interest is between 180-240 seconds. As the core level reaches a minimum, water from the steam generator tubes flows back into the upper plenum and down the outer core channel. As indicated on Figures 5-K, During this 5-N, and 5-0, the vapor velocity is also in(the downward direction. time frame, the elevation of this volume corresponds to the bottom of the core barrel. Since this volume contains steam, the volumetric displacement of coolant downward in the outer core channel causes steam in volume 335 to flow upward in the center core channel 343. This is the least resistant path for the displacement of steam. The I
flowpaths in the core bypass volume,345, have a small area and high resistance factor. As indicated on Figure 5-M, there is little change in the velocity in this region.
(1) See Figure 2.4.1-1, pg.169, of " Calculative Methods for the Northeast Utilities Small Break LOCA ECCS Evaluation Model," July,1984. (All ;
volumes identified herein are shown on Figure 2.4.4-1.) {
I
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s -t U. S. Nuclear Regulatory Commission B12633/Page 3 .
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. October 15,1987- !
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As indicated on Figure 5-3,' there is little flow into the lower plenum volume 320. I Figure 5-R shows that volume 320 does void slightly, however the preferential ]
flow path for the displacement of steam is back up through the center core j channel. j i
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The increased steam flow up the core channel must flow through volumes 358, 362,360, and 355. The void fraction for these upper plenum volumes are shown on Figures 5-T, 5-U, 5-V, and 5-W. Figure 5-T shows that the void fraction in volume 355 between 180 and 240 seconds is less than 1.0 due to the water flowing back from the steam generators. Steam exiting the center core channel interacts with the water flowing back from the hot legs and preferentially flows
. downward in the outer core channel due to the high interfacial drag inherent in the NULAP5 code.
Figures 5-X and 5-Y identify the reason for the increase in the steam velocity.
Due to down flow of two-phase coolant in the outer core channel and up flow of
- steam in the center channel, there is a difference in the density head terms in each channel beginning at 180 seconds. This density head difference occurs at the same time volume 335 reaches the maximum void fraction. This density head difference causes a flow to develop and displaces steam .from the lower plenum up the center core channel. Since the velocity increase between 180 and .
240 seconds is relatively constant, it appears that this density head difference is offset mainly by interfacial drag and wall friction losses. All other momentum terms are negligible.
This phenomenon is a result of:
- 1. High interfacial drag modelin NULAPS
- 2. Dual core channel modeling The use of a less conservative interfacial drag model would allow the steam generators to drain earlier which would produce little or no core uncovery. The dual channel model, on the other hand, allows modeling of a hot rod in a hot assembly channel and prevents any water that drains back from the steam generators during the loop seal clearing process from quenching the rods near the top of the core.
During the August 12,1987 call, the following question was also raised:
What would the effect be on results if our version of NULAPS was j
upgraded to the Cycle 29 version?
in particular, the following " update item numbers" were asked to be considered and included:
18.1 21.3 19.2 21.4 19.12 21.5 19.14 21.11 l
20.1 h _ ____-__--_____-__a
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- 4: : U. S.' Nuclear. Regulatory Commission i
l B12633/Page 4 -
' October 15, 1987'-
p.. ,
p On August.-20,'1987, a conference call was again held with.the NRC Staff and L
theirl consultants. ~1t was agreed that the above modifications to the code would i: 1 be.made, if applicable, as previously discussed. :lt is important to note that the current results with NULAP5 have been shown.to predict, quite well, all of the'
?j
> test data pertinent to the major phenomenon associated with small break LOCA' y: : response.n Nevertheless, by: November 1988,' CYAPCO commits;to provide the-results of a.NULAP5 evaluation to the NRC considering the line items above.
~As discussed with' the NRC .Staf f, the NULAPS model and analysis results are specific to the ' Haddam Neck Plant. -Approval of these - methodologies and
- analysis results therefore does not constitute a generic approval request. -
- Should .you have any further : questions, please contact our Licensing representative directly.-
Very truly yours,
' CONNECTICUT YANKEE ATOMIC POWER COMPANY '
E.7/. 01r6czka f Serdor Vice Presrdent
.cca W. T4 Russell, Region I Administrator F. M. Akstulewicz, NRC Project Manager, Haddam. Neck Plant
- 3. T. .Shediosky,l Reside'nt inspector, Haddam Neck Plant
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y W 0
( t 1- ?
ca -
0, , , , , , ,
0 100 200 300 . 400
, TINE ISEC) j CURVE CNTRLVRR 296
~ ~ ~ '
. . _ _ . . - . , _ . _ _ _ _ .j
i FIGURE 5-B l
HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF-COOLANT VELOCITY - NODE 22
.i (DELT=.0020 S34321)30 CURVE =VELGJ I
~
30-
'20 ,
.f ;
F1 i
V 10-i @h$9 p/S I i
_ d g
~ '
i i i i 0 100 200 300 400 l
T1HE (SEC) ,
CURVE VELGJ 34321000 .,
l
- . . - -- -____-----A
. .I
.e. c.
l FIGURE 5-C i I
HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 S0 FT DISCHARGE LEG BREAK,RCPS OFF COOLANT VELOCITY - NODE-22 CU{DELT=.002 VE=VELFJ 34321000 S) 30-20-
- h. .
7 A y b y ' 10 -
),
0- V' I 3 l
_F_
[;
1 -
4
, 1
- h ,
~ '
. i e i i
0 100 200 300 400 TIME (SEC) ,
CURVE VELFJ 34321000
l FIGURE 5-D HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF VOID FRACTION-NODE 22 CU{DELT=.002 VE=.V01DG 34322000 S) 1.2-1.0- , , g 0.8-0
[
!S C
k ) : ;
I l l l 0.4- I'
) (4fg a \t i
0.2-a ' ..
) U g g g g 0 100 200 300 400 TIME ISEC)
CURVE V010G 34322000
..~ . !
1 i
I FIGURE 5-E HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF COOLANT TEMPERATURE-NODE 22 (DELT=.002 S34322]00 CURVE TEMPG 2500-2000-C L-N I
1500-T H
-P E.
'R
.T U 1000-R E
m.._.
~
500-
~
- r. . , ;p .
y 0- i i- - i i i ,
0 100 200 300 400 T1HE (SEC)
CURVE TEMhG34322000
____i.__i_._____._____
7
/
=
FIGURE 5-F s HADDAM NECK PLANT SMALL BREAK ANALYSIS 3
'0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF !
CLAD SURFACE TEMPERATURE-HOT ROD CUR (DELT=.002 E=HTTEMP 0720 S}010 l
i 2500- .
C 2000-A
'D S.
U I
.f .
A 1500- -
C E
i T
P
-E j 1000-
-T U
R E
F :500-pma 0- i i - e i i 0 100 200 300 400 TIME ISEC)
HTTEMP 07200010 CURVE h-- - - _ _ _ __ _ _ _ _ _ _ _ _ . _ _ _ _
j i
j FIGURE 5-G HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF COLL' APSED WATER LEVEL-IN 36 CENTER ASSEMBLIES NORMALIZED TO ACTIVE CORE LENGTH q CURVE =CNTRLVAR 041 j 1.2- -
4 1.0-g0.8-R'
- y ;
\ s 0
-E E
L 0. 4 -
i 0.2- \
0.0 3b0 yb0 '
b lb0 2b0 TIME (SEC)
CURVE CNTRLVRR 041 4
?
FIGURE .5-H HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1.SQ FT-DISCHARGE LEG BREAK,RCPS OFF LIQUID MASS-STEAM GENEPATOR TUBES (UPSIDE)
(DELT=.002 PLOT =1 S) <
l 30000-h20000-0 0.
1 0
N A
S S
l10000-
't........-.**,
i, , ,,,,..,
~ '~,...
+ .
d i,4 gg'e 4
0 100 200 300 400 TlHE ISECl
- - ~
CURVE CNTALVAR 207 -- ---. CNTRLVAA 212 E __ _ __ _ _ _
' ^'
t t
1 FIGURE 5-1 HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF' !
PRESSURIZER AND UPPER PLENUM PRESSURE i
(DELT=.002 PLOT =1 S) 2500-2000- ;
\, . l
\ .t
\
R E
S-1500- '
S -
U~
P E
{1000-1-
A l
- 500-
)
~
e i i e i 1
0 100 200 300 400 TIME (SEC)
~
CURVE P 35501000 ------- P 410 0 8 0
_ _ _ _ _ . _ _ _ . __ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _a
i
+ .: 1 l
i
( l FIGURE 5-J ,
l HA'DDAM NECK PLANT SMALL BREAK-ANALYSIS 0'.1. SQ FT DISCHARGE LEG BREAK,RCPS OFF JUNCTION VAPOR VELOCITY - J (DELT=.002 S) 4 CURVE =VELGJ 32002000 j 30-FROM VOL TO VOL, 320 335 l
P ,
0- .10-R.-
V E
L 0
0- .
T T
F T ,
/ S E
C t ,
-30 , , , , ,
0 100 200 300 1400 TIME ISEC)
CURVE VELGJ 32002000 i
. . , ~ _ .. . _. .. -
r-
'fr .- e t'
a
-"r. s L
1
~
FIGUREL 5-K'
-HADDAM NECK PLANT SMALL-BREAK ANALYSIS 0.1' SQ FT DISCHARGE LEG BREAK,RCPS OFF JUNCTION VAPOR VELOCITY - J .
- (DELT=.002 S)
CURVE =VELGJ'33501000 30-FROM VOL' .TO VOL '
335 34001 .
-1 20- j l
((f, i P 4 1
0 10- '
R y i E
D- y f' i 1
Y F
T . ,
/ S E-C .
l l
)
i I
-0, , , , ,
0 100 200 300 400
-C- 11ME (SEC1 CURVE VELGJ 33503000 i
_n____________.___ __ _ )
y, g 1 m
< ;;gp y '
yy 3, ' .
fr vi,
_ sc s w . ,
+
m:gj~. g;;, ,
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t 4
(== ,, t !.
' (
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!by R' . 8 5-L %. a w - HL * .
;,.r LFIGURE ,
i' %. m , 9,HADDAM NECK PLANT SMALL BREAK ANALYSIS' V11SQTT Dl. CHARGE S LEGIBREAK;RCPS OFF , JUNCTiOtJ VAPOR VELOCITY --J - ' i (DELT=.002 S) 1
< CUR, VENVELGJ 33502000 l r'.; 1
~'/,
r, .
?YM/E 30-TO VOL. i
;;9:: T . .,
FROM VOL 335- 34301 4.i;/:q N:f k. i.y,,x. i, , s.- 5\l
'+n
..i ;;; .,:( i 5 *
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3; g.j , .
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i:h[. .-2Cl.. 4
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( St. : ' .y
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\
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TIME (SEC) i l l CURNE VELGJ 33502000-i
\ \
by wa a
e , , -
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.+
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' FIGURE 5-M i HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE. LEG BREAK,RCPS OFF-
'"D JUNCTION VAPOR VELOCITY - J ' '
CU{DELT=.002
.VE=VELGJ 335030 S)00 '[=
~
r: 1
,p. t
~ '
E< 30- g .- t .
. f "j
4' i FROM VOL TO VOL. ,,
> 34501.
335 y, . 20 r '
.e
. i
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>p
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l L,-l A ,, ) P. \ t 1
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a
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)
< ft , ,a . ;I,- =
F - T . >.
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. C. '
,/ TIME (SEC)' .
CURVE VELGJ 33503000 l
. .. .1 ,
I .. , .. n e.' - . .. . . . . . . , _ ,_ _ _ , . _ .
/
_ _ , , _ f
7 ~- ;qp; , , ; y%{,di?il b .. M4 bw ':) l: ,{p, < s t ' { . L-l 9 .. j .c s;-
'1 ,m
{; - 4 - - y n ( y:$r m
- w. ;'}s f f ..$p.
.s./-v1 t a
.g-e FIGURE 5-N
- HADDAM NECK PLANT SMALL BREAK ANALYSIS YiO.1?SQ FT DISCH,A GE LEG . BREAK,RCPS OFF !
Yo 6 JUNCllON 4 APOR VELOCITY -. J
- u o .
(DELT=.002 S) ' M.ll c , ? . g. t . CUAVE=VELGJ 34001000
,p ,
4. 30- .g - d s
'E ,/ . . FROM VOL. TO VOL
< /.; '
34001 34002
- j.
r; J;.
.. ^ .
y .,
20- .ij;. J
.f C y 13' ,
f' ,gg 4. . P . o
< 1 l
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-{ 4 i
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, y. '
t W sj , N _l 1 (sff, y ', . Th. j. hf b.,j.. I cp:y p f. , , . '-
** T 8']' '
E. / ,s
;' . s I
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<I. ), C ;ft t.
( '
~$f?'.2
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' 20-
- i
,/ ,,
4 / 1 L
- l
+1;
} vl. i_ . b ,1b0 2b0 3b0 4b0 f/' I. :[ % I 11ME (SEC)
-\
q f ' }f CURVE -p VELGJ 34001000 oe s w m _
.. t ,
, I I
2, h4 L( u u q 1 1 5-0
. FIGURE
- HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG-BREAK,RCPS OFF !
JUNCTION VAPOR VELOCITY - J (DELT=.002 S) . CURVE =VELGJ 34023000 30-FROM VOL. TO VOL - 34023 34024
' i 20-
. (? j' ,
.P ..
0 10 ; R' '
'E. %
02 , T Y F , T . j i { .E C-
-20 g l ,, 5 l 5 0 100 200 300 400
~
TIME (SEC) CURVE VELGJ 34023000 j
'\.,
f -
. q.
I s
' FIGURE 5-P HADDAM' NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF JUNCTION VAPOR VELOCITY - J (DELT=.002 S34301}00-CURVE =vELGJ 30-FROM VOL TO VOL. -
34301 34302 20-
)
( 'n P 0 10-R j + %%% w T 1 F-T
/ S E:
C-I 100 200 300 400 ' e 0 TIME (SEC) CURVE VELGJ 34301000
)
i 4 E ""r:M- rr_z_1__ - m __. ~n . - . . . - _ - . . - - . . .._ , . _ , , , _ , , _ . , j
i. g . 1 l
,P' C; '
1 ' FIGURE 5-0 HADDAM NECK PLANT:SMALL BREAK ANALYSIS s 0.1.SQ FT DISCHARGE-LEG BREAK,RCPS OFF l JUNCTION VAPOR VELOCITY - J I (DELT=.002 S -34323}00 CURVE =VELGJ l 30-FROM VOL. TO VOL 34323 34324 20-l (_ i - ;h ; P . O 10- ; j dh( I WA T l Y-i
,F- !
T
/ ~ 10 -
S E C k 1 i i e i i 1
- - 0 100 200 300 400 TIME (SEC) j CURVE VELGJ 34323000 ~
l W .__r : " t T~ ._
* ' * ' ' ~ ~ ~ ~ ' - * ~ ~ ~ ""*? * ' - ' ' ~ ' '
'l te n.
p c-- , 4 I 1(C d j FIGURE 5-R
)
HADDAM NLCK PLANT SMALL BRE'AK ANALYSIS-0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF VOLUME VOID FRACTION - VOL. (DELT=.002 S)- CURVE =V010G 32001000 1,2-1.0-0.8- .,. -]
, V i i ..
l D
- F R 0.5 -
A C T 'i, N 0.4-
\ 1 m!{
0.2 -
- 0. 0 ,- .
300 400 l 100 200 0
-(. ' TIME (SEC)
~ CURVE V010G 3E901000
--- u
.y v.
1 V 8, FIGURE .5-S HADDAM NECK PLANT SMALL BREAK ANALYSIS
~0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF i
- VOLUME VOID FRACTION - VOL.
(DELT=.002 S)
. CURVE =V010G 33501000 I
. - 1. 2 -
f :- i 1.0-l I 0.8-V. 1 0 F
'A 0.6- j R- 1 C ]
1 1
) i i 0 1 0.4-
{ J "D.2 - 0.0 , ,, , 400 100 200 300 ; f 0.
- TIME (SEC)
CURVE V010G 33501000 l J
- x. ..
i
+
. ri.
FIG U R E .5-T HADDAM NECK PLANT SMALL BREAK ' ANALYSIS a 0.1 SQ FT DISCHARGE LEG BREAK,RCPS .0FF VOLUME VOID. FRACTION - VOL. ; i CU{DE LT=.002.S)00 VE=V0100 355010 1.2- ,
.I 1.0- p .
l l
}
0.8-e. 0 1 } D. f ". 1
.p R 0.6-n f
C T 0.4-fltY 4 l 1 0.2 f i l I I 0.0- , , , 0 100 200 300 400 TIME ISEC) CURVE V010G 35501000 J
4 M i I FIGURE 5-U - HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF. VOLUME V0lD FRACTION - VOL. (DEL 1 =.002 S) ~ CURVE =V010G S5801000 1.2-
* ~ ,v--
c I 0.8-0 i 1 0 0.6-C 1 { L 0 . N
- 0. 4 -
lY i
- 0. 2 -
n1 0.0 -- , ,
. , . , i 200 300 400 l , . .
0 100 TIME (SEC) CURVE v010G 35801000 I. k......_. _ _ . _ _ _ _ . . . _ . . . - _ . 1. _ _ _, ,
7
-- s :,; >
}
i () ,. l q l
.I FIGURE 5-V HADDAM; NECK PLANT SMALL BREAK ANALYSIS i i
- 0.1 SQ FT DISCHARGE. LEG BREAK,RCPS OFF -l VOLUME VOID FRACTION - VOL. j
-j CU{DELT=.002 VE=v01DG 360010 S)00 '
1.2-1.0- po , - - -
. .~ i
.(
4 0.8- h
.v
'0 1
0 . F , R 0.6- 1 R.
- C. I T l
.1 )
-0 l N i
- 0. 4 -
D.2-l l i l l 0.0 ,- , , r . -, - , - , , 0 '100 200 300 400 l' TIME ISEC1 l CURVE VOIDG 36001000 l 1
' ~ ' ' * ' ' '
- 1
- v. a 4
1 i I , J i FIGU R E 5-W. HADDAM' NECK PLANT SMALL BREAK ANALYSIS-0.1- SQ FT DISCHARGE LEG BREAK,RCPS OFF VOLUME VolD FRACTION - VOL. (DELT=.002 S CURVE =V010G36201]00 1.2-1.0-W xW . t 0.8-V l ! O 3 ) 0 4 [ F I R 0. 6 - R
\ ,
C T
) l i
1 I
'O .
l N 1
- 0. 4 -
0.2-V oo 2 r , , , L ! 0 100 200 300 400 TIME (SEC1 CURVE V010G 36201000
.1 ,
Q. 1 FIGURE 5-X HADDAM NECK PLANT SMALL BREAK ANALYSIS 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF DENSITY HEAD IN CORE CHANNELS (DELTs.002 S) u- l
* ,3- ' en .,
0 '. 4 t, ' E N ::. I t
- i
}
i,' ,T i i ' 14. i ! ! : l
,: .it - .
E 2- :,f.!: E R t , 0 ',i i P $* 5 1 1-udM 0 . q~ 200 300 400 L O 100 TIME (SEC1 CURVE RH0H340 ..-- RH0H34 3 J l.
f (. I 1 1 k l 1 FIGURE 5-Y HADDAM NECK PLANT SMALL BREAK ANALYSIS l 0.1 SQ FT DISCHARGE LEG BREAK,RCPS OFF DENSITY HEAD IN CORE CHANNELS (DELT=.002 S) f 1.0-0.8-D' E N i T
- 0. 6 ) !
T H E R D ,! 0.4-i
,1 0.2- } jiNge.W%')
L4 0*U , . . . . { 0 100 200 300 400 TIME (SEC) CURVE - RH0H340 - - RH0H343 { i L - -.. . . .
, - i}}