appendix 6b. figures › docs › ml1830 › ml18305a300.pdf · 2 days ago · 0 5 10 15 25 30 35...
TRANSCRIPT
Catawba Nuclear Station UFSAR Appendix 6B. Figures
Appendix 6B. Figures
Ca
taw
ba
Nu
clea
r S
tati
on
UF
SA
R F
igu
re 6
-1 (
Pag
e 1
of
1)
(17
AP
R 2
01
2)
Fig
ure
6-1
. M
inim
um
Con
tain
men
t S
um
p p
H F
oll
ow
ing a
Des
ign
Basi
s L
OC
A
9.0
8.8
8.6
8.4
8.2
8.0
7.8
:c A.7.6 Q.
I u,7.4
7.2
7.0
6.8
6.6
6.4
6.2
6.0
I I I
. - '" I i I I
I
I ~
I ' '
I
I
.1-
I I
-I
-I
I
-,
I t · J __ .J l .
' ! i : ,-......,,._
- . ! I I
I ~
~ r---~ I u - •
~ I . . I
I I I
I . : t • I - l-~--
I l ' -
. ~ ~ ,.. I '
. 1·
I- +- • ~-
• -- ·- . ~
! ' [ I
I
I •
• j ' I . I
I
. I ! •
I '
0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100
Time (Minutes)
Catawba Nuclear Station UFSAR Figure 6-2 (Page 1 of 1)
(22 OCT 2001)
Figure 6-2. Sensitivity of Peak Pressure to Air Compression Ratio
~.o
3.0
-(/)
0.. .__..
UJ 2.0 (..) :ii: Lu t:C. Lu LI-LU a:: C,
en 1.0 0..
,..... r--
~ a: LI-
Lu 0 a: ::J VJ tl"J L.J a: 0..
~
< L&.I o.. -1.0 ...J
""' z: LL
LL 0 ;z
~ -2.0 ..... ,ci;
> w Q
-3.0
-~.o -15 -10 -5 O 5 10 15
CHANGE IN COMPRESSION RATIO (PERCENT}
Catawba Nuclear Station UFSAR Figure 6-3 (Page 1 of 1)
(22 OCT 2001)
Figure 6-3. Steam Concentration in a Vertical Distribution Channel
25 0
• < C/l
5 Cl')
0.. 20 a.. ~ ~
w LLJ QC 0::: ::::, ::::, en 10 en V')
15 c,? LU LI.I QC 0:: Q,, Q,,
__J _J ,c( 15 C(
I- 10 I-QC QC < < Q,, Q..
X 5 20 0::: ,c( w -< I-U')
0 25 0 10 20 30 ~
ELEVATION WITHIN CONDENSER, FT
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-4 (P
ag
e 1 o
f 1)
(22
OC
T 2
00
1)
Fig
ure 6
-4. P
eak
Com
pressio
n P
ressure V
ersus C
om
pressio
n R
atio
8.0, 7: P0L\'TR0PlC ~-n~l.20.
7.5
c.::,
~ 7.0
w a,:: ::> en Cl) L&J a,:: Q..
~ 6.5 Cl) Cl) uJ ~
~ u X 6.0 ~ CL
5.5
HPONE.NT ~
TYPICAL TEST
R-ESULT
5.0 1 L yv L I I I. 25 I. 30 I. 35 I • ll-0
COMPRESSION RATIO l.ll-5
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-5 (P
ag
e 1 o
f 1)
(22
OC
T 2
00
1)
Fig
ure 6
-5. U
pp
er Co
mp
artm
ent C
om
pressio
n P
ressure V
ersus E
nerg
y R
elease fo
r Tests a
t 11
0%
an
d 2
00%
of In
itial D
BA
Blo
wd
ow
n R
ate
IC!>
V) Q..
w a:;
10
8
~ 6 en w °" 0..
z:: 0
U> U> 1£1
i-= " I M: ~ U.I a..
2
0 50
---------------------·
--------· .--·---
-------- -----TESTS AT ZOO: INITIAL MHA BLOWOOIIIN RATE
TESTS AT 11or INITIAL MHA BLOWDOWN RATE
100 150 200
ENERGY RELEASE. PERCENT OF REACTOR COOLANT SYSTEM RELEASE 250
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-6 (P
ag
e 1 o
f 1)
(17
AP
R 2
01
2)
Fig
ure 6
-6. P
eak
Co
nta
inm
ent P
ressure T
ran
sient –
Pressu
re
16
14
12
& en (l_
~ 10 0:: :::J (/) (/) w 8: 8 1-z w 2 z 6
~ z 0 u 4
2
0
1
CNS ASYMMETRIC ICE MASS DISTRIBUTION COLD LEG PUMP DISCHARGE BREAK
I
'
- -I
~
A)r. + ....
rl
( I
I . '
'
I
i I ---·r
0 3000 6000 9000 12000 15000 18000 21000
TIME (SECONDS)
I 7 -- --J !
I
I
J~.~ I
i
24000 27000 30000 33000
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-7 (P
ag
e 1 o
f 1)
(17
AP
R 2
01
2)
Fig
ure 6
-7. P
eak
Co
nta
inm
ent P
ressure T
ran
sient - U
pp
er Con
tain
men
t Tem
pera
ture
200 j
180
Ci:' 0)
~ 160 w 0:: :)
~ 140 0:: w CL
~ 120 I-0::
~ 100
·. V\.._.....V I /"
~ 1 /
I :; I-z 80 w 2 z <(
60 I-z 0 (.)
0:: 40 w CL CL :)
20
0 l~~ r··-
0 3000 6000
CNS ASYMMETRIC ICE MASS DISTRIBUTION COLD LEG PUMP DISCHARGE BREAK
I -
I
I
'
'
I
9000 12000 15000 18000 21000
TIME (SECONDS)
I
-------
' ·~
··~
I '
24000 27000 30000 33000
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-8 (P
ag
e 1 o
f 1)
(17
AP
R 2
01
2)
Fig
ure 6
-8. P
eak
Co
nta
inm
ent P
ressure T
ran
sient - L
ow
er Con
tain
men
t Tem
pera
ture
300
i I ' [L Ol
~ 250 w 0::: :::, I-<( 0:::
~ 200 ~ w I- r 0::: 0
·- -- . D...
:';; 150 I-z w ~ z <{ !z 100 -0 u 0::: w s 0 50 -'
0 --
0 3000 6000
CNS ASYMMETRIC ICE MASS DISTRIBUTION COLD LEG PUMP DISCHARGE BREAK
I I I
i
- '
i I
9000 12000 15000 18000 21000
TIME (SECONDS)
I I 7
I -~
!
!
I I
24000 27000 30000 33000
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-9 (P
ag
e 1 o
f 1)
(17
AP
R 2
01
2)
Fig
ure 6
-9. P
eak
Co
nta
inm
ent P
ressure T
ran
sient - S
um
p T
emp
eratu
re
240
230
i:i:' 0) (I)
~ 220 w c:: ::J I-ti_ 210 w
\
\ , c.. ~ w
200 I-
9 ::J 0 ::J 190 c.. ::iE ::J en I- 180 z w ~ z ~ 170
\ \
\
' z 0 (.)
160
150 0 3000
- ~
6000
CNS ASYMMETRIC ICE MASS DISTRIBUTION COLD LEG PUMP DISCHARGE BREAK
J ...... ----i----
9000 12000 15000 18000 21000
TIME (SECONDS)
24000 27000 30000 33000
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-10
(Pa
ge 1
of 1
)
(17
AP
R 2
01
2)
Fig
ure 6
-10. P
eak
Co
nta
inm
ent P
ressure T
ran
sient - Ice M
elted
2500000
2000000
1500000
E @. I- 1000000 ...J UJ ::i: UJ ~
500000
0 0
CNS ASYMMETRIC ICE MASS DISTRIBUTION COLD LEG PUMP DISCHARGE BREAK
-----
V Ir
/
/ /
/ 1000 2000 3000 4000 5000 6000
TIME (SECONDS)
7000 8000 9000 10000
Catawba Nuclear Station UFSAR Figure 6-11 (Page 1 of 1)
(22 OCT 2001)
Figure 6-11. Containment Spray Return Drains from Air Return Pit Fans
• - -- 1111~1 -- -- ,_ , __ -
~/, • ,.I _,.; ," -. .~~o I -- ..... -- ~ . ·- ..._
-~
..... r-r
,- m
, __ A~;
-· ,_ ,_ ,_ -- --~
Ill ---- DA CONDITION 1 ..... laM'lf,, ......... __ ......,.
. -·---- CATMIBA IIJCLEM STIITIClt im 1 -·- REACTllR BLIJLDING IEFl.EUIG WIITER SYSTE'1
--• lllc::lliiii ,_ -,.- .. .. .. . - A =' - ... ... ~ ~ !!!" -• CN-FSM-Fm.s-11 IT -
Catawba Nuclear Station UFSAR Figure 6-12 (Page 1 of 1)
(22 OCT 2001)
Figure 6-12. Containment Spray Return Drains from Air Return Pit Fans
-_.., - -- ---...... - -- 5 -- --
-~==::::;::::::=-::::::::::;::--=:t=~ *
. ,•
.....
®
-----. ................
.................... l"T"
·- ..
DA CO~ITIDN 1 .... ............ CATMIIIA 111:LEM ITIITICN - 2
IIEIIICTDII BUILllDll IIEFlE.ING IIIIITEII SVSTEM
~~~~~~~~~§iii~&EEiLIRlnll-__ _ liiiij ., - II Ill'. - .,. ~ ~.&-12 IT
Catawba Nuclear Station UFSAR Figure 6-13 (Page 1 of 1)
(22 OCT 2001)
Figure 6-13. Drain Piping Arrangement Refueling Canal
Ca
taw
ba
Nu
clea
r S
tati
on
UF
SA
R F
igu
re 6
-14
(P
ag
e 1 o
f 1
)
(22
OC
T 2
00
1)
Fig
ure
6-1
4. Ic
e M
elte
d V
ersu
s E
ner
gy
Rel
ease
for
Tes
ts a
t D
iffe
ren
t B
low
dow
n R
ate
s
100
80
~-':!
60 C Lu f--' UJ ~
l.i.J (..)
40
20
0 (;
TfST AT lij[ INITIAL MHA BLOWOO\lf't RATE
TESTS 8£TWEfH f 10. ANO 200. INITIAL MHA BLOWDOWH RATE
100 200 ENERGY RELEASE. ,1J OF REACTOR COOLANT SYS TH4 RELEASE
300
Catawba Nuclear Station UFSAR Figure 6-15 (Page 1 of 1)
(22 OCT 2001)
Figure 6-15. Upper Compartment Peak Compression Pressure Versus Blowdown Rate for Tests
with 175% Energy Release
0 N 0
(DISd) 3!H1SS3Md llV3d JiWISS:. '.:lrl(Jj
8 N
0 i.n
0 0 z: -3:;
0 Cl 3 0 --' a:,
...J ..:[
t-u-, -,..._ z:
0 u")
0
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-16
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-16. P
eak
Rev
erse Differen
tial P
ressure T
ran
sient
ID
I \ LEGEMD:
UPPER COMPARTMEMT 9 L ,,
- - - LOWER COMPARTMENT
t ~ 8 \ -
\ en .a...
\ -u.l
' <>::
' => en 7
' U')
u.l
' QC , .... 6.. .... __ .... ___ 6
5
0 10 20 30 llO 50 60 70 80 90 100
TIME (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-17 (Page 1 of 1)
(22 OCT 2001)
Figure 6-17. Peak Reverse Differential Pressure Transient
f-z u; ,.. "" "" "-::,: 0 w
"' u.J JI: 0 ...J
--
2 N
0 :c
0 <O
..... % w :I: f-
"' ... 0..
:! V
"" w 0.. 0.. ::,
!~------
0 0
0 00
0 C
C a,
0 co
0 <+>
0 ...,
~
0 (',:,
0 t-,,j
0
0
VJ 0 z: 0 (....)
'-'-I Vl
..... ::E
~
Catawba Nuclear Station UFSAR Figure 6-18 (Page 1 of 1)
(22 OCT 2001)
Figure 6-18. Pressure Increase Versus Deck Area from Deck Leakage Tests
3.5
3.0
2.5 U)
0.
LLJ ti)
~ Qi:; ~ 2.0 z
w QI;
= "" "" w Cl:; ~
I. 5
I. 0
0.5
a '//
5
MEASURED INCREASE lN UPPER COMPARTMENT
PRESSURE AT END OF SLOWDOWN
,,,,,, _,,,.
_,,,,,,x ,,.,. ,,.,. _,,,,,,,
,.,x ,....., ~ t~EASURED I NCR EASE IN
,... UPPER COMPARTMENT COMPRESSION / PEAK PRESSURE
.,,,/ // I m ORE END OF BLDWDO .. )
15 25 35 4-S 55 PLANT EQUIVALENT DECK LEAKAGE AREA (FT2 )
65
Catawba Nuclear Station UFSAR Figure 6-19 (Page 1 of 1)
(22 OCT 2001)
Figure 6-19. Energy Release at Time of Compression Peak Pressure from Full-Scale Section Test
with 1-Foot Diameter Baskets
L.,I
! 80 ,_ Cl) V,
== EACH BAR REPRESENTS ONE TEST
TESTS AT I IS PERCENT AND 18S PERCENT OF REFERE~CE ENERGY ANO 65 PERCENT TO 210 PERCENT OF REFERENCE BLOWOOWN RATE
L1J ----• --•P-----• --- - """------ -----Cl:. c.. :.: ~ Q.
!;60·--CI) V, uJ 0::
~ c..,
ls ij() -
L.,I % I
I
'"' UJ
~ 20 UJ -I I.U Cc: ,.. (!) a:: u.J z: I.U 0
...
...
FULL-SCALE SECTION TESTS
Catawba Nuclear Station UFSAR Figure 6-20 (Page 1 of 1)
(22 OCT 2001)
Figure 6-20. Peak Containment Temperature Transient - Lower Containment Temperature
320
300
iZ 280
~ :::,
1i3 260 ~ E ID 1- 240
220
200 0
IV\ ()(\\, f ~~ r
' I - -I
I
' ' I I
' I
50
,,,.._ ~
---- ' - -
100
-~ ~
150
Time (sec)
-.,,.
200
1--2.4ft2 --1.4ft2 ----- o.astt2 I
- - - ~ -,
250 300
Catawba Nuclear Station UFSAR Figure 6-21 (Page 1 of 1)
(22 OCT 2001)
Figure 6-21. Peak Containment Temperature Transient - Break Compartment Temperature
340
320
300 ~
LL
!!! 280 i ai ~ 260 aJ 1-
240
220
200 0
I ..... 1
I \ , .. .. '-- \ ~
"" ~ 11,,. /
50 10•
...I " ['...., ~
15• nme (sec)
~ ~ - ...,
200
A r-,. i-- - -.,J ~ --
250 300
Catawba Nuclear Station UFSAR Figure 6-22 (Page 1 of 1)
(22 OCT 2001)
Figure 6-22. Deleted Per 1997 Update
Catawba Nuclear Station UFSAR Figure 6-23 (Page 1 of 1)
(22 OCT 2001)
Figure 6-23. Typical Upper and Lower Compartment Pressure Transient for Break Compartment
Having a DEHL Break
-(!J
<fl a. -LIJ a:: = Cf) Cl') UJ ai:: ~
~ z L&J % ~ Ille: 4[ i::a.. 2 0 c.)
~ ,ci ~ 0 ~
20
10
0
0
BREAK COMPARTMENT
UPPER CONTAINMENT
2
TIME AFTER BREAK (SECONDS)
3
Catawba Nuclear Station UFSAR Figure 6-24 (Page 1 of 1)
(22 OCT 2001)
Figure 6-24. Typical Upper and Lower Compartment Pressure Transient for Break Compartment
Having a DECL Break
-c:,
en 0.. -UJ a:: ::::) v,) Cl] LU a::: ~
I-z: uJ ~ I-01:: -< 0.. % 0 u ...J ~ I-0 I-
20 ,-------------------------
10
0
0
BREAK COMPARTMENT
UPPER COMPARTMENT
2
TIME AFTER BREAK (SECONDS)
3
Catawba Nuclear Station UFSAR Figure 6-25 (Page 1 of 1)
(22 OCT 2001)
Figure 6-25. Plan at Equipment Rooms Elevation
A
Catawba Nuclear Station UFSAR Figure 6-26 (Page 1 of 1)
(22 OCT 2001)
Figure 6-26. Compartment Section View
TOP DECK DOORS
119, 4-8, 4-7,
I HTERMED I ATE DECK DOORS---
2lt, 21, 18, 15, 12
23, 20, 17, I '+, I 1
22, 19, 16, 13, 10
4- 5 • 4-ll- , 4- 3 , ll-2 , 4- I
52, 34, 27, 35, 29, 50, 36, 31 • 37, 53
38
9
8
7
26, 28
I , 2, 3, 4-, 5 & 6
SECTION "A-A"
25 UPPER COMPARTMENT
2S
33
51
GATE
25
REFUELING CAUL
D
25
30 32
Catawba Nuclear Station UFSAR Figure 6-27 (Page 1 of 1)
(22 OCT 2001)
Figure 6-27. Plan View at Ice Condenser Elevation - Ice Condenser Compartments
ll4 • I 9 , 2 0 . 2 I . 48
3
4-1 , IO, I I • 12, 39
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-28
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-28. L
ay
ou
t of C
on
tain
men
t Sh
ell
25
TOP DECK DOORS\ INTERMEDiATE
DECK DOORS
I I I I I 38 I 39 I 46 I 4-7 I 48 I 49
I I I I I 9 I 12 I I !i I 18 I 21 J 24
I I I I I 8 I 11 I
14 I 17 I 20 I 23
I I I I I 7 I 10 I 13 I 16 I 19 I 22
40 I 41 I 42
I 43 I I
I I I I 44 I 45 I#
52/ ACC FAN ROOM !I.CC INSTR. ROOM Hx ACC FAM ROOM ACC
34 27 35 29 Room 36 31 37 ~3 50
I I I I
26 I 28 PI PE TRENCH 30 I 32 I I
?:ZZZ:Z.. Tl GHT SEAL BETWEEN LINER ANO COMP/IRTMENTS
Catawba Nuclear Station UFSAR Figure 6-29 (Page 1 of 1)
(22 OCT 2001)
Figure 6-29. TMD Code Network
Catawba Nuclear Station UFSAR Figure 6-30 (Page 1 of 1)
(22 OCT 2001)
Figure 6-30. Nine Volume Nodalization of the Steam Generator Enclosure
-
0
2 -©
©-G)
..... , ..... ......
I I
Catawba Nuclear Station UFSAR Figure 6-31 (Page 1 of 1)
(22 OCT 2001)
Figure 6-31. Double Ended Steam Line Break in Steam Generator Enclosure
,_, 5 v'I a..
N
~ ij ~
tn Li.I Cl 0 3 z: z: LJ.J uJ 3 1-- 2 Li.I a::i
.....J <: -I-z: Li.I 0:: w u... I.L. ..... 0 Cl
LJ.J 0::: ::::) V'I V1 -1 LiJ a:: 0 . 5 1.0 I. 5 2.0 2,5 3.0 3.5 ij, 0 a..
TfME (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-32 (Page 1 of 1)
(22 OCT 2001)
Figure 6-32. Double Ended Steam Line Break in Steam Generator Enclosure
....; 1.00 Vl a..
(Yl
oa .75 L.{)
Vl WJ 0 0 .50 :z :z w WJ 3 I- . 25 WJ o:J
_J
d;'. >-< I- 0 :z w a:: w LL LL >-< -.25 0
w c::: :::, Vl
-.50 U') w a:: 0 .5 1.0 1.5 2.0 2.5 3.0 3.5 ij,0 a..
TIME (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-33 (Page 1 of 1)
(22 OCT 2001)
Figure 6-33. Double Ended Steam Line Break in Steam Generator Enclosure
- ~ t/)
0...
lO
oe 3 co V)
w Cl 0 2 z: z: w w .3 I-w IJ:i
.-J -ct: ,.....
0 I-z u.J n: w I.L. LL.
Cl -1 w a:: :::::i V)
-2 V) w a:
0 .5 1.0 I. 5 2.0 2.5 3.0 3.5 ~.o 0...
TIME (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-34 (Page 1 of 1)
(22 OCT 2001)
Figure 6-34. Double Ended Steam Line Break in Steam Generator Enclosure
--VJ 1.00 0...
,..._
D<!l
er, .75 V, w Q 0 z: .50 z UJ UJ ::.: ~
. 25 w 00
_j .;r ,_. I-
0 :z: Lu 0::: u..J w.... w.... ,...... 0 -.25 w er:. ::, Uj ~
-.50 w Cl:'. 0.. 0 . s 1.0 1.5 2.0 2.5 3.0 3,5 4-. 0
TIME (SECONDS)
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-35
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-35. D
ou
ble E
nd
ed S
team
Lin
e Brea
k in
Stea
m G
enera
tor E
nclo
sure
-i
3: m
(I) m 0 0 :z C ti>
0
(71
0
-Ut
~ 0
N
u,
c.)
0
w U1
'r" 0
0
PRESSURF DIFFERENTIAL BETWEEN NODES 1 & UPPER COMPARTMENT {PSI)
N
u, U1
0
...., UT
0
0 N u, "'
0
Catawba Nuclear Station UFSAR Figure 6-36 (Page 1 of 1)
(22 OCT 2001)
Figure 6-36. Two Volume Nodalization of the Steam Generator Enclosure
2
STEAM GENERATOR
1
®
F LOWP ATH SE TWEEH
ENCLOSURES
@ 2
STEAM
GEH ER AT OR
Catawba Nuclear Station UFSAR Figure 6-37 (Page 1 of 1)
(22 OCT 2001)
Figure 6-37. Two Volume Nodalization of the Pressurizer Enclosure
'
CD
-----•-.i -- - -_.,. ... _ .. --- __ .,_ ... _ ..
Catawba Nuclear Station UFSAR Figure 6-38 (Page 1 of 1)
(22 OCT 2001)
Figure 6-38. Four Volume Nodalization of the Pressurizer Enclosure
0
0 0
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-39
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-39. D
evelo
ped
View
of th
e TM
D C
od
e Netw
ork
for th
e Rea
ctor C
avity
An
aly
sis
1-::c C>
w :c ...J w Cl)
UJ w >
--• r- •,,•-- -----
17
0
113
18
· VESSEL BOTTOM
19
0
411-
20
NOZZLE NEAREST BREAK
' \
\" 35
45 7 33 311
0 46
5 36 38
6 37 8
CIRCUMFERENCE
9 11 13 15
0 0 0 0
39 40 !JI ll2
10 12 14 16
Catawba Nuclear Station UFSAR Figure 6-40 (Page 1 of 1)
(22 OCT 2001)
Figure 6-40. Flowpath Connections for the Reactor Cavity Analysis
Catawba Nuclear Station UFSAR Figure 6-41 (Page 1 of 1)
(22 OCT 2001)
Figure 6-41. Containment Model for the Reactor Cavity Analysis
32
~8-52
~7
22,23 21 , 24-
2
Catawba Nuclear Station UFSAR Figure 6-42 (Page 1 of 1)
(22 OCT 2001)
Figure 6-42. Reactor Vessel Nozzle Break Restraints
(
• REACTOR VESSEL NOZZLE BREAK SUPPORTS
CA.TAMA NJCl.EAA STATION
Figure 6.2.1-37
Catawba Nuclear Station UFSAR Figure 6-43 (Page 1 of 1)
(22 OCT 2001)
Figure 6-43. Reactor Cavity Analysis, Element 1
300.0
<!l
cn 200.0 CL -UJ Q:; ::::i en en UJ a::: Q...
I-z u.J
~ 0:: <I: Q.
~ u ....I < 100.0 ~ I-0 I-
0 --------------1 ________ ____. 0 1.0 2.0
TIME AFTER BREAK (SECONDS}
Catawba Nuclear Station UFSAR Figure 6-44 (Page 1 of 1)
(22 OCT 2001)
Figure 6-44. Reactor Cavity Analysis, Element 2
4.0
3.0
CJ
<:I') c..
UJ Cl:: ::::> Cl) (/') UJ c::: c.. I- 2.0 z UJ X I-cc; < Q..
~ c_)
...J <( I-0 I-
1,0
0 0 1.0 2.0
TiME AFTER BREAK {SECONDS)
Catawba Nuclear Station UFSAR Figure 6-45 (Page 1 of 1)
(22 OCT 2001)
Figure 6-45. Reactor Cavity Analysis, Element 3
300,0
<;!:I
v., 200. 0 -0...
100.0 ,_
a I 0 1.0 2.0
TIME AFTER BREAK (SECONDS}
Catawba Nuclear Station UFSAR Figure 6-46 (Page 1 of 1)
(22 OCT 2001)
Figure 6-46. Reactor Cavity Analysis, Element 4
90.0
80.0
70.0
........ ,:.:,
(/)
60,0 0.. -1.1.J 0: ::::, (/) (/)
LI.I 50.0 a:: c:.. ~ z: w i! ~0.0 er:: < 0..
~ u _J 30.0 c:;( I-0 I-
20.0
10.0
o----------------------------0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-47 (Page 1 of 1)
(22 OCT 2001)
Figure 6-47. Reactor Cavity Analysis, Element 5
-LIJ et::: :;i (/) (/) LIJ ~ 0-
20.0
1- 10.0 -z w ~ et::: <(
~ 0 (..)
......J <[ 1--g
0 0
-- -- -
1
1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-48 (Page 1 of 1)
(22 OCT 2001)
Figure 6-48. Reactor Cavity Analysis, Element 6
8.0
7.0
6.0 -t:I Cl) 0.. --I.I.I 5.0 0:: ::::) en (I) ~ 01: 0..
f-- ~-0 z I.LI
~ CZ: ,ct 0..
~ 3.0 (.)
...J
""' ~
2.0
1.0
0 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-49 (Page 1 of 1)
(22 OCT 2001)
Figure 6-49. Reactor Cavity Analysis, Element 7
60.0
50.0 _(\~-------<::I
VJ c... 4-0.0 _,_
w ~ ::::, (/} (/}
w Cc: Cl..
~ 30.0 -LU :z: ~ ec: < Cl..
25 u .....J 4X 20.0 -I-0 I-
10.0 ,_
0 I
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-50 (Page 1 of 1)
(22 OCT 2001)
Figure 6-50. Reactor Cavity Analysis, Element 8
8.0
7.0
-i;,:, VJ 6.0 0.. .......,
LI.J Q:;
:::::i (./') (I') 5.0 I.LJ 0::: 0..
~ UJ ::E 4-.0 ~ a=: < 0..
! c_)
...J 3.0 c:i:: !--0 f-
2.0
1.0
0 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-51 (Page 1 of 1)
(22 OCT 2001)
Figure 6-51. Reactor Cavity Analysis, Element 9
9.0
8.0
7.0
-c:,
U) 6.0 a,_ -i...r a:::: ::::) cl'.) (lj
5.0 w 0:: 0..
I-:z:: UJ
~ 4.0 ~ ~ 0 u ...J 3.0 < f-0 f--
2.0
1.0
0 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-52 (Page 1 of 1)
(22 OCT 2001)
Figure 6-52. Reactor Cavity Analysis, Element 10
7.0
6.0 ........ ~
VJ c...
w 5.0 a:: :::, (I] (I] w c,::. 0..
f- ~-0 z w :I: f-a:: • ~ ! 3.0 u ..J < b """ 2.0
1.0
0 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-53 (Page 1 of 1)
(22 OCT 2001)
Figure 6-53. Reactor Cavity Analysis, Element 11
6 .o
5.0
-(,!:)
(/) ~.o 0... .__,
L.I.J c,::: => v.> (/)
UJ ex: Q..
I- 3.0 z: UJ ::E: I-et:: <I'. Q.
~ u _J 2.0 <[
I-0 r-
1.0
o----------------L-----------...1 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-54 (Page 1 of 1)
(22 OCT 2001)
Figure 6-54. Reactor Cavity Analysis, Element 12
- 5,0 C,
en Q.. -uJ a::: ::::::) cn
4,. 0 rn UJ a:: ~
~ z: LU
~ 0:: 3.0 • i::i..
! u ...I < 1--0 2.0 I-
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-55 (Page 1 of 1)
(22 OCT 2001)
Figure 6-55. Reactor Cavity Analysis, Element 13
6.0
5.0
--c.:,
V)
4.0 0.. -~ ~ ::::, VJ Cl') 1..1.J Ck:: 0..
f-- 3.0 z LJJ
i! ec:: <( a.. ~ u _j 2.0 <t: I-0 f--
1.0
0 0 1.0 2.0
TIME AFTER BREAK {SECONDS)
Catawba Nuclear Station UFSAR Figure 6-56 (Page 1 of 1)
(22 OCT 2001)
Figure 6-56. Reactor Cavity Analysis, Element 14
7.0
6.0
- 5.0 (!l
en a.. -uJ
°' ::, Cl)
4-. 0 Cl'.l UJ a:: a.. ._ :z uJ ::z: I-
3.0 Clll:: • 0..
~ u -I <I'. lo-0 2.0 I-
1.0
o.__ __________ ......_ _________ ____.
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-57 (Page 1 of 1)
(22 OCT 2001)
Figure 6-57. Reactor Cavity Analysis, Element 15
-~ Cl) ~.o 0.. -LLJ 0::: :::I C.I) Cl)
w 0::: 0..
r- 3.0 z: LLJ
~ ca:: < Q..
;§ u ...J 2.0 c:r: r-0 I-
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-58 (Page 1 of 1)
(22 OCT 2001)
Figure 6-58. Reactor Cavity Analysis, Element 16
7.0
6.0 -
C!:I 5.0 (/) c.. -w a:: ::::, GI')
4-. 0 en w a::: Q..
I-z: I.JJ
~ 0::: 3.0 -c[ CL
~ (.)
..J cl I-0 2.0 I-
1.0
o ___________ _._ __________ ....J
0 1.0 2.0
TIME AFTER BREAK {SECONDS)
Catawba Nuclear Station UFSAR Figure 6-59 (Page 1 of 1)
(22 OCT 2001)
Figure 6-59. Reactor Cavity Analysis, Element 17
7.0
-C,
(I) 6.0 c.. -UJ 0:: ::::, (I) (I)
5.0 LU 0::: c.. f-:z 1.J-1
i! ILQ cc: ct 0..
i! u ...J 3.0 -4 I--::
2.0
0 1.0 2.0 TIME AFTER ~~EAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-60 (Page 1 of 1)
(22 OCT 2001)
Figure 6-60. Reactor Cavity Analysis, Element 18
8.0
7.0
6.0 -~ en ~ -L..J 5.0 a:: ::::, V,) (/.) L..J Qr:: c... 1-- 4.0 :z UJ
~ ca:::; ~ Q.
! 3.0 t,J
...J ~ 1--0 1--
2,0
1.0
0 0 1.0 2.0
TIME AFTER BREAK (SECONDS}
Catawba Nuclear Station UFSAR Figure 6-61 (Page 1 of 1)
(22 OCT 2001)
Figure 6-61. Reactor Cavity Analysis, Element 19
60.0
50.0 °- ,\_'------.--. .... -------------
~
C/J l40.0 c... -UJ ~ :::, C/J C/J l.u a:: a.. I- 30.0 .... z: I.I.I
~ = <(
a.
~ 0
....J 20.0 < I-0 I-
10.0 --
0 I
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-62 (Page 1 of 1)
(22 OCT 2001)
Figure 6-62. Reactor Cavity Analysis, Element 20
6.0 -<!)
(/)
Cl.. .._...
LJ..I 5.0 IX :::> CJ') if)
UJ Cl: Q..
,- 4,, 0 z u.J
~ c.: c( Q..
~ 3.0 u ...J cf: I-0 I-
2.0
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-63 (Page 1 of 1)
(22 OCT 2001)
Figure 6-63. Reactor Cavity Analysis, Element 32
3.0
-(!I
(/)
0.. 2,0 -UJ i::c: ::, V, <n L.1.1 ei:::: 0..
I-:z:
~ cc: •er:: Q..
~ (.)
....J 1.0 • I-
0 I-
0------------.L--------------J 0 1,0 2.0
TIME AFTER BREAK {SECONDS}
Catawba Nuclear Station UFSAR Figure 6-64 (Page 1 of 1)
(22 OCT 2001)
Figure 6-64. Reactor Cavity Analysis, Element 33
I.I.I 0::: :::::, C/J (/) I.I.I
f
200,0
(\~_ ------
"'"" 100.0 ,_ ~
~ cc c.. ~ u ....I cc "'"" 0
"'""
0 ___________ ....1,1 ________ _____,J
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-65 (Page 1 of 1)
(22 OCT 2001)
Figure 6-65. Reactor Cavity Analysis, Element 34
200.0
(\"----_____ _ ,;!:I
V, a..
w a:: ::::, V, V, w a:: a.. t- 100.0 z: w j! a:: < Q.
~ w ....J <[ f--0 r-
0 I 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-66 (Page 1 of 1)
(22 OCT 2001)
Figure 6-66. Reactor Cavity Analysis, Element 35
80.0
70.0
-tP
VJ 60.0 Q.. ...... L&.I a=: :::, Cl) Cl) 50.0 L&.I ac: Q..
~ z I.U % 40.0 ~ 0,: -t Q.. % 0 u ....I 30.0 c:[ ~ 0 ~
20.0
10.0
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-67 (Page 1 of 1)
(22 OCT 2001)
Figure 6-67. Reactor Cavity Analysis, Element 36
en CL.
w 0:: :::, V"l en w 0:: c..
20.0
1- 10.0 --z UJ
~ Oc:: <
~ u ...J <t lo I-
-- -- -
0 ----------i..-1 ________ ___, 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-68 (Page 1 of 1)
(22 OCT 2001)
Figure 6-68. Reactor Cavity Analysis, Element 37
9.0
8.0
7.0
-(;!J,
V)
6.0 0.. ---w 0::
=-Cl) en Lu 5.0 0:: ~
I-z: w ~ 4.0 a: <( Cl. a <...)
...J 3.0 ,<[ )-0 I-
2.0
1.0
0
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-69 (Page 1 of 1)
(22 OCT 2001)
Figure 6-69. Reactor Cavity Analysis, Element 38
20.0
---
0 I 0 I. 0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-70 (Page 1 of 1)
(22 OCT 2001)
Figure 6-70. Reactor Cavity Analysis, Element 39
10.0
9.0
8.0
~ 7.0 en ~ -UJ ~ 6.0 :::::> ti) Cl') UJ Q:;: Q..
I- s.o :z: LL.I
~ a:: -< a.. IJ. 0 ~ t;,,)
....I -< I- 3.0 0 I-
2.0
l.O
o-------------1------------' 0 1.0 2.0
TIME AFTER BREAK (SECONDS}
Catawba Nuclear Station UFSAR Figure 6-71 (Page 1 of 1)
(22 OCT 2001)
Figure 6-71. Reactor Cavity Analysis, Element 40
6.0 -(.!:I U)
Q.. -u.J 5.0 a.::: ::::, c.t)
v::, u.J oc: c... I- ti.a z: u.J % I-cc:: <[ Q..
~ 3.0 c..,
....I ,er I-0 I-
2,0
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-72 (Page 1 of 1)
(22 OCT 2001)
Figure 6-72. Reactor Cavity Analysis, Element 41
7.0
6.0 -t.!:I en CL. --I.LI 5.0 01:: ::::) Cf) en uJ Cl: Q..
I- ~-0 z 1.1.,j
i! i::.:: <( 1:1..
~ 3.0 (.)
...J <( I-0 I-
2.0
1.0
o ...... ___________ .i...._ __________ ____.
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-73 (Page 1 of 1)
(22 OCT 2001)
Figure 6-73. Reactor Cavity Analysis, Element 42
6.0 -~ en a.. -LU 5.0 a= :::, en {/'}
u,.,I a::: a..
Sc ij,Q
L4J
i!: IX < c..
~ 3.0 ,._, ..J -ex: f-0 I---
2.0
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-74 (Page 1 of 1)
(22 OCT 2001)
Figure 6-74. Reactor Cavity Analysis, Element 43
(!:I 7.0 (/)
CL.
uJ a:: 6.0 =, Cl') u, UJ a:: CL
~ z: 5.0 w ~ Cl:: c:(
4,, 0 CL.
~ u ...J -er: I- 3.0 0 I-
2.0
0 l. 0 2.0
TIME AFTER BREAK {SECONDS)
Catawba Nuclear Station UFSAR Figure 6-75 (Page 1 of 1)
(22 OCT 2001)
Figure 6-75. Reactor Cavity Analysis, Element 44
20.0 ,-----------------------
-<;!)
""> c.. ........ w 0::: ... ::> u, -en LU a:: c.. .... 10.0 -:z: w ~ 0::: -ct 0.. ~ 0 u .....I <C .... 0 ....
0 ________ ..___! ______ ____.
0 1.0 2.0 TIME AFTER BREAK {SECONDS)
Catawba Nuclear Station UFSAR Figure 6-76 (Page 1 of 1)
(22 OCT 2001)
Figure 6-76. Reactor Cavity Analysis, Element 45
w 0::: ::, en GI) IJJ 01:: c..
200.0
(\~------
1- 100.0 ~ z: IJJ
~ < c..
§
0 0
I 1.0
TIME AFTER BREAK {SECONDS) 2.0
Catawba Nuclear Station UFSAR Figure 6-77 (Page 1 of 1)
(22 OCT 2001)
Figure 6-77. Reactor Cavity Analysis, Element 46
200.0
(\~_ --------------
100.0 -
0 I 0 1.0 2.0
TIME AFTER BREAK {SECONDS)
Catawba Nuclear Station UFSAR Figure 6-78 (Page 1 of 1)
(22 OCT 2001)
Figure 6-78. Reactor Cavity Analysis, Element 47
6.0
5.0
C!.'I
ti) ij. 0 0... ........
w a:: ::::) en Cl)
w
" 0..
1-- 3.0 z: LJ.J ~ I-~ ...:{ 0..
~ (..)
...J 2.0 <r I-0 I-
1.0
0 0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-79 (Page 1 of 1)
(22 OCT 2001)
Figure 6-79. Reactor Cavity Analysis, Element 53
300.0
"''---"'----------------~ 200.0 -
-,:.:::, ---
!i:: LJ_.j
~ ~ 0..
~ u
~ 100.0 -0 I-
0 .._ ________ ..._! ________ ___,J
0 1.0 2.0
TIME AFTER BREAK (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-80 (Page 1 of 1)
(22 OCT 2001)
Figure 6-80. Reactor Cavity Analysis, Element 54
300.0 .------------------------
: "-"- 200.0 - '------------------
IE u.J
~ 0::
'"" ~ (.)
~ 100.0 -~ 0 ~
0 0
I 1.0
TIME AFTER BREAK (SECONDS) 2.0
Catawba Nuclear Station UFSAR Figure 6-81 (Page 1 of 1)
(22 OCT 2001)
Figure 6-81. Hot Leg Double Ended Guillotine Break
u I.M 60 11'1 -~ .... ID
~ 55
-&: & -
w.l so .... .,c GI:
I.I.I e,., -c I.M
-- 45 I.M a,:
--!.;:I a,: w z w 1.10
0 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18 0. 20
TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-82 (Page 1 of 1)
(22 OCT 2001)
Figure 6-82. Hot Leg Double Ended Guillotine Break
90
u 80 w .., -s 11111
70 .... ..., 0
- 60 • -Ill ... -c 50 GI:
1M c,, • "" .... IJO I.U -0, ci,
i 30
2.0 0 0.02 O.OIJ 0.06 0,08 0.10 0.12 0.114 0.16 0.18 0.20
TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-83 (Page 1 of 1)
(22 OCT 2001)
Figure 6-83. Cold Leg Double Ended Guillotine Break
S5
u 50 w "' -:::, ,_ -~ q.5
-.I: • -c.u llO ,_ • Qt ...., en ,c
~ 35 I.I.I Ill: ,.. ~ -LI.I :z 30 LI.I
25 0 0.2 o." o.s o.s r.o 1.2 '·"' 1.6 1,8 2.0
TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-84 (Page 1 of 1)
(22 OCT 2001)
Figure 6-84. Cold Leg Double Ended Guillotine Break
100
90
80
70
-• - 60
50
iio
30
20
0 0.2 0.6 0.8 1.0 1,2 1.14 1.6 1.8 2.0 TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-85 (Page 1 of 1)
(22 OCT 2001)
Figure 6-85. Hot Leg Single Ended Split Break
50
u ... llS Cl) -=> I-ID
co 0
llO
-.a: • -""' 3S ,_ C a.: w Cl') ,c ... ~ 30 ... a: ~ c:, Git 1M z 1M 25
20
0 O.J 0.2 0.3 Q,ij 0.5 0.6 0.7 0.8 0.9 I .0 TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-86 (Page 1 of 1)
(22 OCT 2001)
Figure 6-86. Hot Leg Single Ended Split Break
90
u 80 w
"" -!i "b 70
- 60 • -..., I-.. - 50 w rn .. M.I -' M.I
"° ~
1111 rn ,c z
30
20 0 0.1 0.2 0.3 0.IJ 0.5 0.6 0.7 a.a 0.9 I. 0
TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-87 (Page 1 of 1)
(22 OCT 2001)
Figure 6-87. Cold Leg Single Ended Split Break
~5
u ..., c.,a - ~ ~ -~
3S -..i:: • -~ -c 30 -"" 4IJ -c ~ I.I.I m 25 ,.. c:J -""' z ...,
20
15
0 0.1 0 • .2 0.3 o. ii 0.5 0,6 0,7 0.8 0.9 1.0 TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-88 (Page 1 of 1)
(22 OCT 2001)
Figure 6-88. Cold Leg Single Ended Split Break
eo • C.> 1.1,1 ... ! 70
~ - 60 I -• -~
so C -"' ...
~ C I.I.I _. I.I.I -lilt 30 lilt
i 20 '--_ ..... ______ __,_ __ ..._ _ __,_ __ ..._ _ _., __ .,,__....., _ __,
0 0.1 0.2 0.3 o., 0.5 0,6 0.7 0.8 0.9 1.0
TIME AFTER BREAK (SEC)
Catawba Nuclear Station UFSAR Figure 6-89 (Page 1 of 1)
(22 OCT 2001)
Figure 6-89. Comparison of Satan to Henry Fauske
26
22
ZALOUDEK P SAT= I 000
20
18 ZALOUDEK P SAT= 1800
(.) LL.J
/ Cl)
...., 16 I I-
LL. HENRY--ii / FAUSKE ..J
PSAT=leoo CW] 14- I 0
/ X I c::i
12 I HEH RY-FAUSKE
PSAT = 1000
10
8
MOODY SATURATED 6
4 800 1000 1200 IIWO 1600 1800 2000 2200 2~0
PRESSURE-PS IA
Catawba Nuclear Station UFSAR Figure 6-90 (Page 1 of 1)
(22 OCT 2001)
Figure 6-90. Comparison of Satan to Moody Subcooled
26 -------------------------.
22
20
18
0 UJ Cl)
t-.; 16 t: -i /'\_MOODY
..J
~
Ill 0
/ SUBCOOLED X / Psn = 1000 C!J
/ 12 /
/ /
10 / I
I 8 MOODY SATURATED
6
800 1000 1200 I !JOO 1600 1800 2000 2200 2~00 PRESSURE - PS I A
Catawba Nuclear Station UFSAR Figure 6-91 (Page 1 of 1)
(22 OCT 2001)
Figure 6-91. Zaloudek Measured Data Versus Modified Zaloudek Correlation
20000
1:: I 16000
~ i ..J
• ... 12000 ... u
co f;3 a!:
~ 8000 ;
IIOOD
0
0 _____ ..,_ _______ ....., __ ---'~-------------0 8000 12000 16000 20000 28000 32000
MODIFIED ZALOUDEK PREDICTED GCAn -t.BM/SEC-FT2
Catawba Nuclear Station UFSAR Figure 6-92 (Page 1 of 1)
(22 OCT 2001)
Figure 6-92. Zaloudek Short Tube Data
10000
0 LID• I CD: I r:{J> 0 L/D• 2
• L/0 • 3 g 8000 V L/D = fl
0 ... ieo'8 I.: •
• M .,, 6000
oA~ -~ • C,
o •~ . ~ QC
~ ~ IIOOO ~
2000
0 0 2000 ltOQO 6000 8000 10000 12000 I IWOO
ZALOUDEK PREOI CTEI> G - LBM/ SEC - FT2
Catawba Nuclear Station UFSAR Figure 6-93 (Page 1 of 1)
(22 OCT 2001)
Figure 6-93. Exit Plane Quality as a Function of Upstream Pressure for Saturated Liquid
.20 ---------------------------,
• 15
.05
MOODY MODEL USED IN SAUN-V CODE
MODIFIED ZALOUDEK MODEL USED IN SATAN CODE
o,__ _____ .,__ _____ .,__ _____________________ _. 0 500 1000 1500 2000 2500
UPSTREAM PRESSURE (PSIA)
Catawba Nuclear Station UFSAR Figure 6-94 (Page 1 of 1)
(22 OCT 2001)
Figure 6-94. Henry ANL 7740 Data
8000 r-------------------~------....,..---. • • -c..a .. , .,. •
1: --u . _;. &000
e 0
0 0
• • •
2000 'IOOO IGOO . IOCD
CRIJICAL HASS VELOCITY flOM tGIFIED ZAI.OUDE• (L .. JFT2-SECI
• ••
10.000
Catawba Nuclear Station UFSAR Figure 6-95 (Page 1 of 1)
(22 OCT 2001)
Figure 6-95. Loft Tests 809 and 813 Gage P-1
- A flP[IINflf 109 - - I UPIIIMfll Ill ---- S&f.11 2000
1600
~\'"~ ". - ~ " ~i..---------"' ~----• 1200
800 ____ __,, ____ ..._ ___ ___,j..__...,... _______ L_. ________ _
D •• .012 .011 .0211 .030 .131 .OU 'JINE-S£COIIIIS !
Catawba Nuclear Station UFSAR Figure 6-96 - 6-101 (Page 1 of 1)
(22 OCT 2001)
Figure 6-96. Deleted Per 2001 Update
Figure 6-97. Deleted Per 2001 Update
Figure 6-98. Deleted Per 2001 Update
Figure 6-99. Deleted Per 2001 Update
Figure 6-100. Deleted Per 2001 Update
Figure 6-101. Deleted Per 2001 Update
Catawba Nuclear Station UFSAR Figure 6-102 (Page 1 of 1)
(22 OCT 2001)
Figure 6-102. Illustration of Choked Flow Characteristics
N 1-..... • '-.I
w en -:::E' = ~
N 1-.....
I u w (,I') -:E = ....
0 10 20 30 iio 50
Pu UPSTREA~ PRESSURE (PSIA)
100-----------------------------. 80
60
1+0
20
a _____ ...._ ____ _._ _________ __. ____ _.
0 10 20 30 iio 50
PD DOWNSTREAM PRESSURE (PSIA)
Catawba Nuclear Station UFSAR Figure 6-103 (Page 1 of 1)
(27 MAR 2003)
Figure 6-103. Flow Diagram of Containment Air Return Exchange & Hydrogen Skimmer System
'E...__.,._ l.llLl.m.Ull-""--""'"""""-""""""'--"--""""'-
~ ~rn:: <:: i ! :a::
Catawba Nuclear Station UFSAR Figure 6-104 (Page 1 of 1)
(22 OCT 2001)
Figure 6-104. Reactor Building Plan at Elev. 565 + 3 Hydrogen Skimmer System
Security-Related Information, Withhold under 10 CFR 2.390
Catawba Nuclear Station UFSAR Figure 6-105 (Page 1 of 1)
(22 OCT 2001)
Figure 6-105. Reactor Building Hydrogen Skimmer System
Security-Related Information, Withhold under 10 CFR 2.390
Catawba Nuclear Station UFSAR Figure 6-106 (Page 1 of 1)
(22 OCT 2001)
Figure 6-106. Containment Air Return Fan Performance Curve
I-! LL :j o OPERATING POINT
~ #
-d 8 @)
0 ~ . 6 z SYSTEM CURVE I
w 0:: ::J 4 ~ w 0:: a..
2 _J
~ 0 I-
0 10 20 30 40 50 60
VOLUME FLOW-CFM X 1000
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
07
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-107
. Hy
dro
gen
Sk
imm
er Fa
n P
erform
an
ce Cu
rve
60
i---: L_
a 50+ FAN CURVE
#' tO t{.) :::-: 40 C> @)
0 5 30
z I
(./) 20 ti) l..d 0:.: I 0 OPERATING POINT 0...
(,_) 10 t--~ U)
0 10 20 30 40 50 60 70 80
VOLUME FLOW - CFM x 100
Catawba Nuclear Station UFSAR Figure 6-108 (Page 1 of 1)
(22 OCT 2001)
Figure 6-108. Areas of Potential Hydrogen Pockets
Catawba Nuclear Station UFSAR Figure 6-109 (Page 1 of 1)
(17 OCT 2013)
Figure 6-109. Flow Diagram of Containment Spray System
··~r~~~ ... ~ri : ~m- lln1n
IG.CN-FSAR-FJ[i.6-llll9
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
10
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-110
. Co
nta
inm
ent S
pra
y P
um
p P
erform
an
ce Cu
rve
Efficiency %
90
80
500 70
I-L,J L,J 400 60 LL.
z -D 300 <C
50 L,J
::c u 2:
200 40
<C z >-C, 30 ..J .:c I-
H.P. 0 I-
I 500 20
B.H.P. 250 10
0 0 I I I I I
0 800 1600 2li00 3200 4ooo -'t8oo 5600
GALLONS PER MINUTE
Catawba Nuclear Station UFSAR Figure 6-111 (Page 1 of 1)
(05 APR 2015)
Figure 6-111. Recirculation Sump Strainer Assembly (Unit 1) (Unit 2 Similar)
Recirculation Sump Strainer Assembly
...
i g_ i J • I !!ls !
~·
~Iii~
,Ii ;
iii~ 1. !
I~ z
• tD i I
• I ~ . ! i I; i !
Id
! ! 5 !
f;i t e ie
! ~d I du11II ,~ 1" ,~
;" d .. ;i u
I Ii n -i z .. SIii >-' - .. c:, .. z~ C:, T u.: g!
Catawba Nuclear Station UFSAR Figure 6-112 (Page 1 of 1)
(22 OCT 2001)
Figure 6-112. Containment Piping Penetration Valve Arrangements
.. ---..
. -••
·---IIL
...
... -·--
- -
Catawba Nuclear Station UFSAR Figure 6-113 (Page 1 of 1)
(22 OCT 2001)
Figure 6-113. Containment Piping Penetration Valve Arrangements
., . . - I .i:;:i_ - - -
• . . - --
• . .. - -r ~ ..,. • _i:;:i_
' - - I .i:;:i_ II . .
- -• g_ . .. _I Cl • -
• . . _i:;:i - - -c.. . - .0 . .. - - --g_
• . ,,. _I 0
• • . _o_ - L_, - --·-·,.._,
iiiiiiii""irfl"'imi"iian :Ill
-• IHll"IIII I ,.._ 111m PJllll!II CIIIT- PIPNI ~
... REVl•I- - - ij_ .. --CN-t"--.•-U:11 I':"'
Catawba Nuclear Station UFSAR Figure 6-114 (Page 1 of 1)
(22 OCT 2001)
Figure 6-114. Containment Piping Penetration Valve Arrangements
I _c;J_ a • . ... u
"'~-• .. .... _ • - ..
--- ---1 ·-• - - -......._ ______ -- -1 ·---~---
• • - _I;]_
- --•--11-................. ~~ 11,1 -· CHPTEIIITIIII..EIIIIIIIFIIIIIEII
cmn!IINIITP'll'al'l!ll!lllll1ll WILIE-
_i-~ -____ ,.. .....
- ... MVE•I- - ~-1-114 I':""
Catawba Nuclear Station UFSAR Figure 6-115 (Page 1 of 1)
(22 OCT 2001)
Figure 6-115. Containment Piping Penetration Valve Arrangements
., ----• •• .. •
.. • • ..
.. •
. -··----••• i:u.111 ...... 111m1.
Ill,
. .. .. . . ..
- --
--·
------ ..... .. at-fllllll-llm.a-1:111
...
-I
Catawba Nuclear Station UFSAR Figure 6-116 (Page 1 of 1)
(17 APR 2012)
Figure 6-116. Flow Diagram of Containment Valve Injection Water System
~ "'~:I:_' ~~: ~E~eia
T
< >ELHOIEOF"'21l"F""""'"'EFFECl"."'1E,..,,_,. , "W>SEOFIJ12111rs<•IJ<\llrEEITTOT,O,TEIH0-2 "WISEOFIJ1'"'''""1P'111rEEITTOT,.,TE0-21
, IELE""''"''"""""'""m"mT .. ITliH'lRlLFIEL""""""" ...... L!'llATE
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
17
(Pa
ge 1
of 1
)
CT
200
1)
Fig
ure 6
-117
. Fu
el Tra
nsfer T
ub
e
Security-Related Information, Withhold under 10 CFR 2.390
Catawba Nuclear Station UFSAR Figure 6-118 (Page 1 of 1)
(24 APR 2006)
Figure 6-118. Model B Electric Hydrogen Recombiner-Cutaway
Historical information not required to be revised.
COOLING AIR
ELECTRIC HEATER
INTAKE
VERTICAL DUCT
PREHEATER
FLOW ORIFICE
SUPPORT BASE
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-11
9 (P
ag
e 1 o
f 1)
(24
AP
R 2
00
6)
Fig
ure 6
-119
. Reco
mb
iner C
on
trol S
ystem
Sch
ematic
Histo
rical in
form
atio
n n
ot req
uired
to b
e revised
.
,.-1 I
POWER SUPPLY
ONTROLPANE
REDUNDANT RECOMBINE A SYSTEM
CONTAINMENT
-+--------1 POWER SUPPLY
RECOMBINER
I ---, I I I I I L TEST --- rte- - -
INPUT POWER
CONTROL PANEL
Catawba Nuclear Station UFSAR Figure 6-120 (Page 1 of 1)
(22 OCT 2001)
Figure 6-120. Flow Diagram of Containment Hydrogen Sample & Purge System
.., .... 11
!!!!!!!I:
:::::::1:r !!!!!!!II Ii ••••aa•li
11
Catawba Nuclear Station UFSAR Figure 6-121 - 6-127 (Page 1 of 1)
(22 OCT 2001)
Figure 6-121. Deleted Per 1991 Update
Figure 6-122. Deleted Per 1991 Update
Figure 6-123. Deleted Per 1991 Update
Figure 6-124. Deleted Per 2004 Update
Figure 6-125. Deleted Per 2006 Update
Figure 6-126. Deleted Per 2006 Update
Figure 6-127. Deleted Per 2003 Update
Catawba Nuclear Station UFSAR Figure 6-128 (Page 1 of 1)
(18 APR 2009)
Figure 6-128. Flow Diagram of Safety Injection System
' ~ ~ l!jll : . o I -I
! i, f 1 f • L.. •I
rfl!jll =ir
I '
•I -I
-r 3 I f 'L. f
~
~~ : ~ o I
iJU • L..
I ' rflljll I
I ' " !
! 3 I f 'L •
Catawba Nuclear Station UFSAR Figure 6-129 (Page 1 of 1)
(21 OCT 2010)
Figure 6-129. Flow Diagram of Safety Injection System
,. ""'',;,i,;""'"'M• .. • ~ 0 • ._Ur,oo,~·•uD..,.Tl<cE"""""' ,. ~ ::,u fH""'H7' .. :"- ,.,.....,,_,.,
·~"':tl,f.J™.'"''"""""""
OACONDITIDN2
CA CONDITION I -··CATAWBA~LEARSTATiaN~ITl
Catawba Nuclear Station UFSAR Figure 6-130 (Page 1 of 1)
(17 OCT 2013)
Figure 6-130. Flow Diagram of Safety Injection System
~ '"""
[IE.........,,.,,.," ......... J.l!L.IJl!l!II ~ .!!!1111.!1. ..!l!!l!!!!l,!L --- .. ,. .....
I II H II 11
13 14 • WO, NO,CN-FSAR-FIG. S-130
OACONDITION2 •AC•NDITI•N 1
C•OTAWBA ,U::LEOII 51ATIO~ UNIT 1
FLOW 01~- OF SAFETY INJECTION SYSTEM
:::~-=~
Catawba Nuclear Station UFSAR Figure 6-131 (Page 1 of 1)
(17 APR 2012)
Figure 6-131. Flow Diagram of Safety Injection System
Catawba Nuclear Station UFSAR Figure 6-132 (Page 1 of 1)
(18 APR 2009)
Figure 6-132. Safety Injection System
-•Ir ~=1 111B1111 IIIIJ [!;;t'!~;.~~~~~~,,d'-<,7'H,,.,ir.,7'd"<-,J<,:~~,.,ir..-,,.,,,7',1:11f.,;<... ., .. --1
Catawba Nuclear Station UFSAR Figure 6-133 (Page 1 of 1)
(22 OCT 2001)
Figure 6-133. Residual Heat Removal Performance Curve
..-I-LU LU LL. - 200 .0,
• LL.I :c
0 1000 2000 3000 4-000 5000
FLOW (GPM)
Catawba Nuclear Station UFSAR Figure 6-134 (Page 1 of 1)
(22 OCT 2001)
Figure 6-134. Centrifugal Charging Pump Performance Curve
7000
6000
5000
ij000 -t-LL.I I.LI I.I.. -Q ,c I.LI ::i:::: 3000
2000
1000
0
0 100 200 300
FLOW (GPM)
ijQO 500 600
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-13
5 (P
ag
e 1 o
f 1)
(22
OC
T 2
00
1)
Fig
ure 6
-135
. Safety
Injectio
n P
um
p P
erform
an
ce Cu
rve
3500
3000
-1-LLI
~ 2500 0 ...:c UJ ::c
2000
1500 0 100 200 300 ~00 500 600 700
FLOW {GPM)
Catawba Nuclear Station UFSAR Figure 6-136 (Page 1 of 4)
(17 APR 2012)
Figure 6-136. Safety Injection/Residual Heat Removal System Process Flow Diagram
~: ~:
~:
~:
~--- .... ·••m....aa:1'1.111 __ _ uan:11111.LPLIIIII • -- I • II I I I , I I • U • D Lt • • D' •
NIB TI t 11111 I I ,, 111111
Catawba Nuclear Station UFSAR Figure 6-136 (Page 2 of 4)
(17 APR 2012)
<.am~ , __ j_---C01_1~--~--~~~~.i1 1
1
- '
COL• LEG INJECTmN IMINI
~E~0wH~ ~w~u~msiR~:x> ~t~ m~g~~ ~sX:~~R!~=} LOCATl•N<ALLFLOWSINGPMJ
rncB H~ 1:mrnii~ =~~) ~t~ m~8~~ ~Bx ~~~Ri~=~
~ I I
~
I FEUloSICOFlat20l2,-LPO,JEEFFECr.2-'1-t> 1H:
IE.E .. EDFtJ1 .... FS"ILl'll•TE
--CAT ...... NUCLE<>RSTATHJIJ
eccsaRtlCESSR<l'll • l«;R ...
Catawba Nuclear Station UFSAR Figure 6-136 (Page 3 of 4)
(17 APR 2012)
1!1:121-l'I.JIII-IIIIIWll!NI ~1Dlw.LFUMIINll'IO I 2 3 4 • I 7 I
~w.LFUMIINll'IO • B 21 II II 14 B B 11 B B • a1 • :D M • •
= = = = =· = = = = = = = = = = = = • '9411 i iJiililTrTT.L.Lii
Catawba Nuclear Station UFSAR Figure 6-136 (Page 4 of 4)
(17 APR 2012)
NOTES TO Figure 6-136
ECCS Process Flow Diagram (Notes)
1. The cold leg injection mode of operation assumes single train ECCS operation at minimum
safeguards conditions, and two train ECCS operation at maximum safeguards conditions. Minimum
injection flow rates are representqative of three NV/NI lines at the minimum of the flow balance TAC
windows and the single NV/NI line (attached to a broken loop) at the maximum of the flow balance
TAC windows. Maximum injection flow rates are representative of all NV/NI lines at the maximum
of the flow balance TAC windows.
2. Maximum water temperatures are 100°F (at the FWST) and 150°F (at the ND HX outlet) for injection
and recirculation modes, respectively. Reference RCS pressure for all ECCS modes is 0 psig.
3. For minimum cold leg injection and recirculation conditions, seal injection flow rates are maximum
values, thereby reducing the cold leg injection flow. For maximum cold leg injection conditions, the
seal injection flow rate is a conservative nominal value of 32 gpm, thereby maximizing the cold leg
injection flow rates.
4. The recirculation modes of operation assume single train ECCS operation at runout conditions.
Runout flow rates are 560 gpm, 675 gpm, and 4500 gpm for a single NV, NI, and ND pump,
respectively. The NV and NI injection lines are assumed to be balanced at their maximum flow
balance TAC values. ND injection lines are not required to be balanced, but are assumed to be
balanced equally for illustrative purposes of this diagram. The same is true for NI hot leg injection
lines.
5. All flow rates are either taken directly, or indirectly determined from calculation file DPC-1552.08-
00-0109, Safety Injection Flows for Safety Analysis.
Catawba Nuclear Station UFSAR Figure 6-137 (Page 1 of 1)
(22 OCT 2001)
Figure 6-137. Ice Condenser
-11:n.at11. •~
.. ----aml8I ~ mlll'l'HIII Llll'm M -·· CIW'IIRITaalllllllntl-• --
~- IIIL llt. at·FN-F"HLa-lD -I
Catawba Nuclear Station UFSAR Figure 6-138 (Page 1 of 1)
(22 OCT 2001)
Figure 6-138. Isometric of Ice Condenser
TURNING VANES
Al R HAND LI NG U"IT---
INTERMEDIATE
OECK --~--t--;;J;~d.J....[.~~
LOWER INLET DOORS
ICI con._
---UHE
Catawba Nuclear Station UFSAR Figure 6-139 (Page 1 of 1)
(22 OCT 2001)
Figure 6-139. Floor Structure
.,... __ COlfTAlll4EJIT SHEL~
STEEL ,UTE
EMIEDOED COOLING PIPES (FLOOR COOLING SYST91)
L STRUCTURAL SOB FLOOR
I NSUU. TI OI SECT I ON
WEAR SW
FLOOR DRAIN (TYPICAL)
LMa la.ET DOOR
Catawba Nuclear Station UFSAR Figure 6-140 (Page 1 of 1)
(22 OCT 2001)
Figure 6-140. Wear Slab Top Surface Area Showing Typical Coolant Piping Layout
TOTll SURFACE AREA - 139 FT2
COOUNT INPUT/OUTPUT CONNECTION
11 11
\111 --'
- ---...----~ I I
--- - __;,,...- - - • ...J
• 1 t I I ----- _____ ....__ ___ """"
I --- - __,, I BAY
------.. ---, I I ____ ___J ____ ~
--- ~'--- - --... I I .,, ______ __.., ____ _,,
~I I I L..__ _,__,_ '------.--....
.. ~ 1 -- , __ ___.., ·-, ~-----~
Catawba Nuclear Station UFSAR Figure 6-141 (Page 1 of 1)
(22 OCT 2001)
Figure 6-141. Lattice Frame Orientation
ASSl.l4ED ARBITRARY DIRECTION OF SEISMIC INCIDENT
CONTAINMENT WALL
NOTES:
REF: LATTICE FRAME ORIENTATION
90° FROM REF
I. MAXIU T~GENTIAL ANO RADIAL SEISMIC LOADS CANNOT OCCUR SUilJLTANEOUSLY. 2. TANGENTIAL AND RADIAL SEISMIC LOADS ~5 DEGREES FROM THE REFERENCE DIRECTION
OF SEISMIC INPUT OCCUR SIMJLTANEOUSLY AND THE MAGNITUDE IS THE AVERAGE OF MAX114JM RADIAL ANO MAXlU TANGENTIAL TIMES THE COSINE OF ij50, OR (RAOIAL+;ANGENTIAL) _707 _
3. "ORIZONTAL AND VERTICAL SEISMIC LOADS CAN OCCUR HORIZONTALLY. ~. BLOWDO~ LOADS, TANGENTIAL, RADIAL AND VERTICAL CAN OCCUR SIMULTANEOUSLY.
RADIAL BLOWDOl'N LOADS ALWAYS OCCUR IN THE DIRECTION OF THE CONTAINMENT WALL
* In an individual lattice frame.
Catawba Nuclear Station UFSAR Figure 6-142 (Page 1 of 1)
(22 OCT 2001)
Figure 6-142. Load Distribution For Tangential Seismic And Blowdown Loads In Analytical Model
ALL TANGENTIAL LOADS ARE TAKEN OH ONE SIDE ONLY
CRANE WALL T SEISMIC BLOWDOWN ...
LOADS LOADS
L/3 17.0% T 33 I /3% T
t-L L/3
t-3lLQ% T 33 I /3% T
L/3 49.0% T • 33 1/3% T
Catawba Nuclear Station UFSAR Figure 6-143 (Page 1 of 1)
(22 OCT 2001)
Figure 6-143. Lattice Frame
(
( LATTICE FRAME
• CATAWBA JIIJCLEAFI STATION
Figure 6.7,3-3
Catawba Nuclear Station UFSAR Figure 6-144 (Page 1 of 1)
(22 OCT 2001)
Figure 6-144. Lattice Frame Analysis Model
Catawba Nuclear Station UFSAR Figure 6-145 (Page 1 of 1)
(22 OCT 2001)
Figure 6-145. Typical Bottom Ice Basket Assembly
PERFORATIONS ( I. 0 ~ I. 0 OH I .25 CENTERS)
~1~----- 12,090 DIA REF
0 0
• ••••••, •• \ 11 ____ l
I I
• •:
6~.60
ST\ FFENER ASSEMBLY ....___.,-••- r:u:u::J~• :• .• :._ -------- -----------------,1
COUP LI NG SCREWS
BASK ET END
GRID BARS--
MOUHTING BRACKET ~SSEMBLY CLEVIS PIH
® 11 _,.,. 'C ""'1
II ---- - - -- -----11 -=--------------------..--::.-_-__. - J.1 14-2. 57 REF
I I
1.00
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
46
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-146
. Co
mb
ina
tion
s of C
on
centric A
xia
l Load
an
d D
istribu
tion
Load
~ u..
tO
10.000
9000
8000
7000
0 6000 al .....I
0 <(
g 5000 0 uJ I-
~ 4.000 0::: IC/)
0 3000
2000
1000
0 C,
PLASTIC COLLAPSE OF COMPRESSION SIDE
PLASTIC YIELD OF COMPRESSION S10E
ALL THE. Dl.S I(:!-! & TEST LOAD5 LiE TH I~ EHHLOPE
. SijEAR YIELD OF NEUTRAL PLANE
PLASTiC YIELD OF NEUTRAL SURFACE LI HE ELEMENTS
10 20
CONCENTRiC AX;AL LOAD (KIPS)
30
Catawba Nuclear Station UFSAR Figure 6-147 (Page 1 of 1)
(22 OCT 2001)
Figure 6-147. Crane Assembly
Security-Related Information, Withhold under 10 CFR 2.390
Catawba Nuclear Station UFSAR Figure 6-148 (Page 1 of 1)
(22 OCT 2001)
Figure 6-148. Crane Rail Assembly
•
CRANE AAIL ASSEMBLY
CATAWBA NJCL£AA STATION
Figure 6. 7.5-2
Catawba Nuclear Station UFSAR Figure 6-149 (Page 1 of 1)
(22 OCT 2001)
Figure 6-149. Refrigerant Cycle Diagram
•~g : r £ ~~-:..:--=- -=--=-~---=--~ 7 ~ I I EXPAIIS ION I I I ' VALVE I
I i I I
I t I :
REFIIGEIUT EVAPORATOR
r'~-@---~.......,. __ ___-... REFRIGERANT CClft[SSOR
I I
I I
I .._. ___ __, ---~GLYCOL
I REFRIGWTIOI I . IN
L_ COl!fll_!O!_ ___ ----- - ------- -- _J
TO & FROM NOii-ESSENTiAL SERVICE •ATER SYSTEM
GLYCOi. CHILL[RS (TYPICAL)
GLYCOL OUT
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
50
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-150
. Gly
col C
ycle to
Ea
ch C
on
tain
men
t
COIIIMINMENT "2
THROTTLE VALVE
EXPANSION TANK
30 AIR
HANOLlNG PACKAGES
..... FLOOR COOLING PUMPS
24 FLOOR COOLING COILS
24 BEAM COOLERS
...,.._ I I I I _____________ J
COtiTAINMENT ISOLATION VAi.YES SEE SECTION 6.7.2
PRESSURE -RELIEF
CHILLER UNITS
1-- _____ J I -+-
!SEE REFRIGERANT
CYCLE DIAGRAM)
1 I I I I I I I I I I I I I L __ _
FLOOR COOLING PIMPS
24 FLOOR COOLING COILS
2-4 BEAM COOLERS
---1 I
I I I I -+L __
CONTAINMENT • I
THROTTLE VAL VE ,---- <SEE AIR
COOLING CYCLE OIAGRAMJ
30 I EXPANSION AIR TANK
HANDLING PACKAGES
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-15
1 (P
ag
e 1 o
f 1)
(22
OC
T 2
00
1)
Fig
ure 6
-151
. Sch
ematic F
low
Dia
gra
ms o
f Air C
oolin
g C
ycle
- - - - _:1,- UPPER PLENIM
I
.-1 i I I , I I'
AIR HANDLING UNIT
BACKDRAFT DAMPER
AIR DISTRIBUTION HEADER
BACKDRAFT DAMPERS
\ \+
AIR _/ DISTRIBUTION HEADER
ICE BED
l t
v CROSSECTIONAL
VIEW
WALL PUEL
WALL PANELS
l I
AHU 1
I
t
!
\!.J.
t 1 •
l i
I I
AHU I I
r
J
t
t
I I
AIIU I
i
t
Catawba Nuclear Station UFSAR Figure 6-152 (Page 1 of 1)
(22 OCT 2001)
Figure 6-152. Air Handling Unit Support Structure
• < • .. i
I
Catawba Nuclear Station UFSAR Figure 6-153 (Page 1 of 1)
(21 OCT 2010)
Figure 6-153. Deleted Per 2010 Update
Catawba Nuclear Station UFSAR Figure 6-154 (Page 1 of 1)
(22 OCT 2001)
Figure 6-154. Lower Inlet Door Assembly
~--tl~~-----L,__, --
o,, .. ,-0
l.llti LOWER INLET DOOR ASSEMBLY
~ CATAWBA r,.a.JCLEAR STATION
Figure 6.7 .8-2
Catawba Nuclear Station UFSAR Figure 6-155 (Page 1 of 1)
(22 OCT 2001)
Figure 6-155. Details of Lower Inlet Door Showing Hinge, Proportioning Mechanism Limit
Switches and Seals
.,
'· _,_.,,,
" ....... __ ,,.., ... __ ,, ___ ,,,,,, ... ,~ .. , __ ..., __ ,,_,
~ ~~~:;-~~-.: .. _"
.......... _.,_,_..,,. n._,_..,,..,...,, .•.. ..,,.,
. -"· ,,,..,. • .,.,.,..,,n,.
ll
•· ... _ .... ,..,_.,,.. DETAILS OF LOWER INLET DOOR Sf-!OWING >!'.NG£, PROPORTIONING MlCHAHISM LIMIT SWI i'CHES AND SEALS
CATAWBA MJCLEAR STATION
Figurf' 6.7.8-3
Catawba Nuclear Station UFSAR Figure 6-156 (Page 1 of 1)
(22 OCT 2001)
Figure 6-156. Inlet Door Frame Assembly
8 .,; 1~1-::t I
I.__ v 0 CCTI 0 r· I g g ~Tl 0
0
<.O en 1.0 ,.._
<.O . i.n N ::t
...... a. ~>----- -11.l------ :,g1--
Cl.. >-0 ..... u:J
~
rn
~~ -- -r""t"- (")1---::t fil~_J
• >-::t 1---,.._
8 g g g J g
~
g
' i ff~~ I w
I u,
<[
NO
·::;:, +I c:c: I'- :::r::: ::t 1--
.ci;
c:') a:i
z: 0
,. ij B U)
Catawba Nuclear Station UFSAR Figure 6-157 (Page 1 of 1)
(22 OCT 2001)
Figure 6-157. Inlet Door Panel Assembly
FRONT PLATE I ."7 l.b------------
BACK COVER
i 15.00
69. l 2 ±.06
92.SO I 15.00
t-38.12±.06
I 15.00
~,~1------- "2.00 -----"""'•,
-- .., - ==:::,
r = = = = = = ~ _---_ -=-· = = = = ~ -J
CJ
L~~========:JI 7.12±.06
INSULATION
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-15
8 (P
ag
e 1 o
f 1)
(22
OC
T 2
00
1)
Fig
ure 6
-158
. Low
er Inlet D
oo
r Sh
ock
Ab
sorb
er Assem
bly
R.ACK-U PL.,TE
I
DETAIL-A SCALE-1:1
SEE OETAIL - A
/ SEE OETA,L . 11!1:
I I
INNER SUPPORT
/
IMl'ACTSUAF ... CE
AESTRAININO PIPE . \ \\ RESTRAJNING STRAP
SEE DETAIL-C
OETAIL ·B SCALE· l;1
HO~~N_/ STRAP
,,..,..
INNER/ SUPPORT
FRONT HDLC-OOWN
STRAP
B:l_OOREF.
113.00
DE:lAiL, C
SCALE· .l:1
u';.;. ~J .1•m1 -I I
c:;}
I I
I I M-;.---- -;r--~1 I ~ I I 11 I
~ I I Ii : I I I 11 1
I I Iii
l+ •! hl I 1tr
----+··Ju I
~ l J, '- .-,..::r:..--~~-~
RESTFl"'""NG STRAP RESTRAINING PIPE
Catawba Nuclear Station UFSAR Figure 6-159 (Page 1 of 1)
(22 OCT 2001)
Figure 6-159. Four Loop Ice Condenser Lower Support Structure Conceptual Plan and Sections
Security-Related Information, Withhold under 10 CFR 2.390
Catawba Nuclear Station UFSAR Figure 6-160 (Page 1 of 1)
(22 OCT 2001)
Figure 6-160. Four Loop Ice Condenser Lower Support Structure General Assembly
• e • •
• e • .,
\. n
\.. _,I
! ~
i q :-
<>;,}~ IF•~ .::·::~~ ~}: ~,
~t
. .
. I
•
• ! rl. ;; •• YI ~i
"'?! ~iii-~ ~Is •• ~~
::•
11 :, ~~u i .. ~rl.
~~1~ Ii te
FOUR LOOP ICE CONDENSER LOWER SUPP( STRUCTURE GENERAL ASSEMBLY
CATAWBA NUCLEAR STATION
Figure 6.7.9-2
Catawba Nuclear Station UFSAR Figure 6-161 (Page 1 of 1)
(22 OCT 2001)
Figure 6-161. Ansys Model Assembly
411 I I I I
-,___ I I _J.---'
I " I I oc
•I I ·- ~
i r<l I I I ' I I DI I 17'- 'I I 1 -,
[/ " ....... ..,, ' I, ~
.A I .... ~
111, '-~
V ..... ~
~ ~
ANSYS MODEL ASSEMBLY
CATAWBA NUCLEAR STATION
Figure 6.7.9-3
~
Catawba Nuclear Station UFSAR Figure 6-162 (Page 1 of 1)
(22 OCT 2001)
Figure 6-162. Finite Element Model of Postal Frame
DOOR ARRESTOR LOAD APPLIED OVER SHADED
ELEMENTS
TRIANGULAR SHELL ELEMENT (TYPICAL)
SPAR REPRESENTATION OF PORTAL FRAME LINK
RIGID LINK (TYPICAL TO PRESERVE GEOMETRIC COMPATIBILITY AT PLATE CONNECTIONS TO COLUMNS)
JET IMPINGEMENT SHIELD ATTACHMENT POINT
THREE TURNING VANE ATTACHMENT POINTS
FLOOR NOT INCLUDED IN MODEL
Catawba Nuclear Station UFSAR Figure 6-163 (Page 1 of 1)
(22 OCT 2001)
Figure 6-163. Schematic Diagram of Force Applied to Three Pier Lower Support Structure
A ___ tEISMIC EXCITATION STRUCTURAL FORCES
BLOWOOYIN FORCES ON
IMPINGEMENT PLATE
DRAG ON OUTER CIRCUMFERENTIAL BEAM
RAOIM. AND TANGENTIAL
8LOW00WN FORCES FROM ICE BASKtT DRAG ---~-- -~~~------ff- HORIZONTAL RADIAL t.ND TANGENTIAL
( TYPI CAI.. ON EACH RAD1-AL BEAM]
DOOR IMPACT
DRAu ON INTERMEDIATE DECK,
LATTICE FRAMES ANO COLUMNS½
INTERMEDIATE DECK WEIGHT--...! LATTICE FRAME AND_......
COLUMN WEIGHT -
DRAG ON CROSS BRACING
•
WALL PANEL/ WEIGHT /
-SEISMIC EXCITA'TION STRUCTURAL fORCES
PLAN
1CE BASKET DRAG
TURNING \fANE
LOADS
fLOOR VANE
SECTION A-A
SEISMIC DRCE.S FROM ICE vN STRUC1'URE ( T'l'PICAL ON EACH RADIAL BEAM l
DOOR IMPACT
'DRAG ON INTERMEDIATE DECK, LATTICE
FRAMES AND COLUMNS
r INTERMEOIA'TE DECK WEIGHT
LATTICE FRAME AND COLUMN WEIGHT
DRAG ON RADIAL BEAMS
FORCES ON IMPINGEMENT
Catawba Nuclear Station UFSAR Figure 6-164 (Page 1 of 1)
(22 OCT 2001)
Figure 6-164. Force Transient Hot Leg Break
0
0
0
N
(/.I 0 l"'1 ("") (Al
0 :z 0 CJ) -
0 . U"I
0 O')
0
APPLIED FORCE RATIO F/F PEAK 0 0 0 . . . N += O')
0
co . 0
Ca
taw
ba
Nu
clea
r S
tati
on
U
FS
AR
Fig
ure
6-1
65
(P
ag
e 1
of
1)
(22
OC
T 2
00
1)
Fig
ure
6-1
65
. D
LF
Sp
ectr
a H
ot
Leg
Bre
ak
Forc
e T
ran
sien
t
2.0
I. 5
-LL. ...J 0 -Cl<: 0 I-c..> < LL.
0 1.0 < 0 ...J
u
~ z: >-0
0.5
0 0
.... , ,. \ I \
I •~ ,.r ~\ ,., ....... ,, / ·•••• ~\ I '- ~-,~ ~,.,.,_____ .... .._ -.. .. . - --- --. ·. " ~ ",t /\. ~ .... '-·-·----........ L-.. • ••••• • - -••••••L . .;,•-•--~
LEGEND
-- - - 0% CRITICAL DAMPING
-•-•- 5% CRITICAL DAMPING
•••••••••• JO% CRITICAL DAMPING
5
20¾ CRITICAL DAMPING
10 15
FREQUENCY - (hz) 20
,,,,._
25 30
Catawba Nuclear Station UFSAR Figure 6-166 (Page 1 of 1)
(22 OCT 2001)
Figure 6-166. Top Deck Test Assembly
(
(
• TOP DECK TEST ASSEMBLY
CATAWBA NJCLEAR STATION
Figure 6.7.10-1
Catawba Nuclear Station UFSAR Figure 6-167 (Page 1 of 1)
(22 OCT 2001)
Figure 6-167. Details of Top Deck Door Assembly
(
(
·~~-~ ·--·--......- ...... ~ . ..,.
- _.. .... ~
(
t:-=-' -- 'C
✓---·
t
.-........ ----p, =- ,;,· / , • ...... T ..
·~·;. ......
• DETAILS OF TOP DECK DOOR ASSEMBLY
CATAWBA NJCLEAR STATION
Figure 6.7.10-2
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 6
-16
8 (P
ag
e 1 o
f 1)
(22
OC
T 2
00
1)
Fig
ure 6
-168
. Interm
edia
te Deck
Do
or A
ssemb
ly
AIR HAHDLl~G UNIT
CONTAINMENT WALL
AIR DISTRIBUTION DUCT
INTERMEDIATE DECK BEAM INTERMEDIATE DECK DOORS
I CE BASKET LATTICE FRAHE
Catawba Nuclear Station UFSAR Figure 6-169 (Page 1 of 1)
(22 OCT 2001)
Figure 6-169. Air Distribution Duct
r7 \~c{( u ,_
~- .. ~-.., ... ,,.,_, ........ ., ....... _,_.., ..._,. J.,.- -·~ ..... , .. ~ ... ...,-
(,
"'-M' "'"'' 1 ~-==~-~S', '. ·-· ' ,·.---,1+1 ~- rl -----r .. , ... I
<"!/~~' LJ~TI -- J -~~-"o - ~ I ,.
r•:f.~?_:::,: ~ ,. ~., .. ~ .,.,..v,,..,,.. ... -....:::,
J (Iv' 1 ----,----'=rtt-·· ·---,- ~ tr I r. __ -- r J UJ I I
~ .• L__"~~-- J
Catawba Nuclear Station UFSAR Figure 6-170 (Page 1 of 1)
(22 OCT 2001)
Figure 6-170. Air Distribution Duct
( '
U.7oa',__c.__
I .... ,... CEl.'Jo~ i
L---~-----t
I. ~~_____J_~ , ......... -., •• ..,.AU. J I ~-'f-tt-6----"'-'"'_"'_'·"" ..... _·_·~_, ___ .,J.J.:!
~Ill +·:- FjK< ... -··
DE.TA.ILG ,.., ... ~ .. "'
.. .L. I
I ~ l J =--· ... ~-
---r ~T" ,_ .. ,.,..- ~ ]"-"!·°'~"' I l
.... ~ ·,':"t· I :L' I ~· . - " c__.l.,.l--.ta!.o.s I ~.00,1.0ll ~ ..... Off$n')
u~AIR 0Uc1 -lft::----.H-•-± "t--1-----..J_ ·='.:·:IR DISTRIBUTION DUCT
• CATAWBA MJCI.EAR STATION
Figure 6.7.12-2
Catawba Nuclear Station UFSAR Figure 6-171 (Page 1 of 1)
(22 OCT 2001)
Figure 6-171. Phase Diagram for Na2B4O7 - .10 H20 System at One Atmosphere
0
t:11;1 0 ,a 0 '& . '0 iw 0
w
' 0
Ut 0 ,,.. C,
~+2
N (.,J
-4 ,.. <'"" --4
n
~ ,,. I
~ I 0 •
c;,
I
m
I I I I I I
0
~ -0 n
TEMPERATURE. °C
0
w N
UI 0 r-~+ 0 ..
<n 0 r--C,
z GI
N a,, ~
0 ..., 0 ;i:'
N 0
Temoi:airature, °F
.. II .....
,._. Ill 0~ r- 0 c; ..., •• 0 0 --..., 0
0
(J\
a
Catawba Nuclear Station UFSAR Figure 6-172 (Page 1 of 1)
(22 OCT 2001)
Figure 6-172. Ice Bed Compaction Versus Time
28
2ij
I-
a I.IJ :c a 20 CD
~ u Li,. 0 ,~ - ,0 ;w; uJ u = :..J g_
:e <;,,
;:: 12 ~ ,c[ a;;...
i u = w m
8 ,.., ~
J
i t
~ I t ~ 1
r I
L ~
I j I
l 1 r-
0
o•
D' Tetraborate Flakice, 22 Feet
12
140HTHS
i6 2i.
Catawba Nuclear Station UFSAR Figure 6-173 (Page 1 of 1)
(22 OCT 2001)
Figure 6-173. Test Ice Bed Compaction Versus Ice Bed Height
,,1 (..l
32
(, ...
C
·-----·----.............. __ ............. ____._,.,, __ ........
f LAI ICF
3:)
Hf IGH) or :ct ABOVE f.(~f•f..t:"I 10t. TFSt B[{), FllT
Catawba Nuclear Station UFSAR Figure 6-174 (Page 1 of 1)
(22 OCT 2001)
Figure 6-174. Total Ice Compaction Versus Ice Bed Height
16 :...
tj LA.I i-
0:: 12 C ...., • .... ~ - I ~
•
r -! a ;-u ct A-s l
1 Q r LU
It CD SUPPORT l.w
INTERVAi.. ~
0 0 10 20 30 50
HEIGHi OF ICE 8£0 Fi£T
Ca
taw
ba
Nu
clea
r S
tati
on
UF
SA
R F
igu
re 6
-17
5 (
Pa
ge
1 o
f 1
)
(22
OC
T 2
00
1)
Fig
ure
6-1
75
. Ic
e C
on
den
ser
RT
D L
oca
tion
BIIW I
RIIOlll!. LOCA TI~ I
ll,l!JIAL LlllC~rnou z M!lllill ~OCA Tll[)ll 3
270'
275'
:lll!'
37' 0 2!!' 0 2"
6111 24 It
1t
it ICE C!l!fftl'a!:~
1: C!JIHAl~MEUT
23
22 21
1!!11' !Rm
I!' llltfl
Zll
IS
19
10
suo,1e:10I q:>1!MS am1eJadwa1 pue OHi JOJ .1.z~-9 aIqe1 aas
pue4 al!soddo ~ l!Un
UMOl!S i!: l!Un
1&2
REV •
•
Ca
taw
ba
Nu
clea
r S
tati
on
U
FS
AR
Fig
ure
6-1
76
(P
ag
e 1
of
1)
(24
OC
T 2
00
4)
Fig
ure
6-1
76
. B
lock
Dia
gra
m:
Ice
Co
nd
ense
r T
emp
eratu
re M
on
itori
ng S
yst
em
ICE CONDENSER REGION
48 SCANNER/ 48 FT RTD ICE BED RTD'S MULTIPLEXER RECORDER UNIT
6 TEMPERATURE }--0 6 SWITCHES CINITIATE AT 25°F)
ANNUNCIATOR ANNUNCIATOR <INDICATION & ALARM) <INDICATION & ALARM>
DUKE POWER CIM'ANY CATAWBA NUCLEAR STATION
BLOCK DIAGRAM 1
ICE CONDENSER TEMPERATURE
MONITORING SYSTEM APPENDIX 6 - CHAPTER 6 TABLES & FIGURES
I lll!I.EMEDFllta4Fllttl'DAIEl!RICl',ll-2H4 voe -.. CLI ""' RGl/ .. ACF CPS RCF 1EBUlliRlll..Jll,illATE..u;;;,a;;u.J_. .. .._ 1M41 YP 111...MN MTE.ll:11::::U!tat, .. .._
I _.,._.RRalF'l!ll1fllFl\1Ea:FCl'.DMt»f2-II DECKED!E!c!!II W.TE.ll:IZ:::l.ll!FPll.!tl!i!!!!m .. 1Elli1i!:!l.
NO. REVISIONS ll'lN DATE CH<D DATE .... CJVD. R.IIC. ICH, DATE
INSPECTED DWO. NO. CN-FSM-FIG.6-176 I ir·
Catawba Nuclear Station UFSAR Figure 6-177 (Page 1 of 1)
(22 OCT 2001)
Figure 6-177. Door Monitoring Zones
TYPICAL ZONE:
q DOORS OR 8 DOOR PANELS WITH 2 SWITCHES PER PANEL (SWITCHES DESIGNATED "X" & ••y ti)
ORIENTATION SHOWN FOR UNIT I
ACCESS DOORS
p 9' ,p
"'f\:_ EQUIPMEoT ACCESS DOOR_
Catawba Nuclear Station UFSAR Figure 6-178 (Page 1 of 1)
(22 OCT 2001)
Figure 6-178. Wiring Diagram: "Y" Switch
--·--,,, ··- -~ -..... '>...,,
11111' -l'-H
~ 11111'
- illllllli •- -· ~ 11111' • ...... -.... ~ --,_,
' 11111'
-..... ' ' - Iii:-
-•-~Ila -· __ .,.. __ '111111111~•'¥"11111'1:H
.=J----__ ,_ ___ ,H
... REWJ• IINI - 121--. .. 1111 I":"
Catawba Nuclear Station UFSAR Figure 6-179 (Page 1 of 1)
(22 OCT 2001)
Figure 6-179. Wiring Diagram: "X" Switches Lower Inlet Doors
--·--11-M
a-H
• .... -H-1
....
.... It+<
-...
-:I. 'IWM.ll'lllllllmfllll• .. I.NI'--. ., __ ,...., ____ _ -.--~-··-----Tll!-Ml!IULT .....
--•---•---
aw,-.t • naa:11111:11 .....
--••-.aa UIIIIIIIIUT-
..... - latfWll-fa.1-111 -I
Catawba Nuclear Station UFSAR Figure 6-180 (Page 1 of 1)
(22 OCT 2001)
Figure 6-180. Deleted Per 2001 Update
Catawba Nuclear Station UFSAR Figure 6-181 (Page 1 of 1)
(22 OCT 2001)
Figure 6-181. Model of Horizontal Lattice Frame Structure
TIE MEMBERS CONNECTING LATTICE FRAMES
OUTER CRANE WAcL
CAIHILEVER ELOE!HS REPRESENTING GROUPS OF SIX INTERCONNECTED LATTICE FRol.MES
MASSES ASSOCIAfED WITH ICE BASKEl-LATTIC[ FRAME ASSEMBLY
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
82
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-182
. Gro
up
of S
ix In
tercon
nected
Lattice F
ram
es
CONNECTING POINTS OF ADJACENT FRAME
r STIFFNESS OF OTHER . LATTICE FRAME GROUPS
WALL PANEL S"T I FF NESS
TYPICAL LATTICE FRAME
CRANE WALL
STIFFNESS OF OTHER LATTICE FRA~E GROUPS
Catawba Nuclear Station UFSAR Figure 6-183 (Page 1 of 1)
(22 OCT 2001)
Figure 6-183. Lattice Frame Ice Basket Gap
GAP (EXAGGERATED)
TOP VIEW
ICE BASKET
CONNECT, '':"G:..---H==-,r-----r COLLAR-
SIDE VIEW
GAP (EXAGGERATED)
Catawba Nuclear Station UFSAR Figure 6-184 (Page 1 of 1)
(22 OCT 2001)
Figure 6-184. Typical Displacement Time History for 12 Foot Basket with End Supports - Pluck
Test
,{:---/ - -...,~ ' ........ ---. "
" 0.. ..... >
,, __ Jc. .....
------✓ I ✓ -------
----- --------- ---
--. -------- ----- --. --
Catawba Nuclear Station UFSAR Figure 6-185 (Page 1 of 1)
(22 OCT 2001)
Figure 6-185. Non Linear Dynamic Model
LOCAL IMPACT Elh!ENT
I CE BASKET MASS ----~-~-. ....
LOCAL iMPACT llhlElff
LATTICE FRAME M4SS -------~
LATTICE FKAME -W:1LL Pi\NE.L l::LEIIENT
t INPUT
COUPLED
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
86
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-186
. 3 M
ass T
an
gen
tial Ice B
ask
et Mod
el
i:HNE WALL MOTION
.. •
WALL PANEL
.....
LOCAL IMPACT ELEMENT
l LATTICE FRAME
I I I I 1(VVV
I CE BASK E~S T
I I I I ~o
Catawba Nuclear Station UFSAR Figure 6-187 (Page 1 of 1)
(22 OCT 2001)
Figure 6-187. 9 Mass Radial Ice Basket Model
ICE------~ BAS1<ETS
LOCAL IMPACT EL~ENT
i CRANE WALL t«>TION
WALL PMIEL
LATTICE FRAME
Catawba Nuclear Station UFSAR Figure 6-188 (Page 1 of 1)
(22 OCT 2001)
Figure 6-188. 48 Foot Beam Model
LATTICE FRAME WALL PANEL ELEMENT
ICE BASKETS
LOCAL lti!PACT ELEMENT
LOWER SUPPORT
Ca
taw
ba
Nu
clear S
tatio
n
UF
SA
R F
igu
re 6-1
89
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 6
-189
. Ph
asin
g M
ass M
od
el of A
dja
cent L
attice F
ram
e Bays
l
a ~--------- I
LATTICE FRAMEWALL PANEL
0
I
• PHASING LINK
LCOUPLED
I
---DO.OTES RIGID LI Nk
ICE BASKETS
LOCAL IMPACT ELEMENT
I
Catawba Nuclear Station UFSAR Figure 6-190 (Page 1 of 1)
(22 OCT 2001)
Figure 6-190. Phasing Study Model, 1 Level Lattice Frame 300 Degrees Non-Linear Model
PHASING CONNECTOR GAP (TYPICAL)
CANTILEVER ELEMENTS REPRESENTING GROUPS OF SIX INTERCONNECTED LATTICE FRAMES
--~--- LATTICE FRAME END TIE
~ PHASING CONNECTOR, TENSION
-0- PHASING CONNECTOR, COMPRESSION
PHASING CONNECTOR GAP (TYPICAL)
Catawba Nuclear Station UFSAR Figure 6-191 (Page 1 of 1)
(22 OCT 2001)
Figure 6-191. Typical Crane Wall Displacement
2.50
2.00
I. 50
1.00 --Cl')
w .50 5 z -
~ 0 as
i:fj c.,
::5 D.. -.50 ct.I
Q
-1.00
-I .SO
All. ~ r '\ ' •v1
\ \ ' /\ I \) ~r1 '--~ ' V
\i .
~ 1
-2.00
{ -2.50
a 2.0 ~.0 6.0 8.0 10.0 12.0 llL0 16.0 18.0 20.0 TIME (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-192 (Page 1 of 1)
(22 OCT 2001)
Figure 6-192. Typical Ice Basket Displacement Response
2.50
2.00
I .SO
1.00
-u:i IJ.J
.50 ::i::: (.) z: -I-
0 z: UJ
ai 0 -< _,J
0.. -.50 (/) -0
-1.00
-1. 50
-2.00
' ~
Yl ' 1
~ ' l r~ ~ n ... I ~ -, - '¥\ N~ I\ -' I
I n ~
- I I I
' I I ~ i-+-- ' A. I I
I'~ ,'\J \, I +- 1 -- t-I I '
I\ \J u n I i -2. 50
0 I .0 2.0 3.0 l+.0 s.o 6.0 7.0 8.0 9.0 10.0
TIME {SECONDS)
Catawba Nuclear Station UFSAR Figure 6-193 (Page 1 of 1)
(22 OCT 2001)
Figure 6-193. Typical Ice Basket Impact Force Response
20000
15000
- 10000 u:i
t:i :w: Co?
5000 ,ci: a::I
LL.I (.)
,._ 0 N
I.I.. 0
....I
r ' r, I r ' rr ' -cc
6 -5000 I--v., l:ICI ....I -10000 . w ,._, a::: 0
~-15000 ~ 0.. ::E
-20000
-25000
-30000 0 1.0 2.0 3.0 4-.0 5.0 6.0 7.0 8.0 9.0 10.0
TIME (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-194 (Page 1 of 1)
(22 OCT 2001)
Figure 6-194. Typical Crane Wall Panel Load Response
1!+000
12000
10000
8000
6000 -Cl.) m ..l
- 4000 w (.) er 0 1,1,..
2000
0
-2000
-IWOO
-6000 0
.
.-:·-IN ·-~t! ~ y ~ij,~~q ~R •
1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 TIME (SECONDS)
Catawba Nuclear Station UFSAR Figure 6-195 (Page 1 of 1)
(22 OCT 2001)
Figure 6-195. Wall Panel Design Load Distribution Obtained Using the 48-Foot Beam Model
Tangential Case
13
12
I I
10 TANGENTIAL
~ LOAD DISTRIBUTION ~
:..c: 9 DESIGN ENVELOPE .. 0 ,.: 0 ....I
8 ....I LU z • a. ....I 7 ..J
i ....I
6 < I-ffi <!J z 5 • t-
~ LOAD DlSTRIBUTIOH 4- DUKE DBE EAST-WEST
>< EARTHQUAKE HO. q i 3
2
0 ...._ _ _.__...,.. __ _.__ ..... ____ __._ _ ____. ___ _.
LFH I Lf #2 LFH3 Lf#ij LF.#5 LF#6 LF#7 Lff/8 LOWER SUPPORT
LATTICE FRAME LOCATION STRUCTIJRE
Catawba Nuclear Station UFSAR Figure 6-196 (Page 1 of 1)
(22 OCT 2001)
Figure 6-196. Wall Panel Design Load Distribution Obtained Using the 48-Foot Beam Model Radial
Case
"' 0..
!Ill:
~
0 < 0 ..J
..J LLJ z < 0..
...J
...J
~ -' < C < 0::
:::E
i X < :::E
14
13
12 RADIAL LOAD DIITIIBUTIO~ DESIGN ENVELOPE
11
10
9
8
7 LOAD DISTRIBUTION DU~E DBE EAST-WEST ~ARTHQUAKE NO, I+
6
5
ij
3
2
0 LF/1 I LF1ii2 LF#3 Lf#IJ LF#5 LF#6 Lffl?
LATTICE FRAME LOCAl lvN
LF#8 LOWER SUPPORT STRUCTURE
Catawba Nuclear Station UFSAR Figure 6-197 (Page 1 of 1)
(22 OCT 2001)
Figure 6-197. Ice Basket Swivel Bracket Assembly
ICE BASKET PLATE
SWIVEL BRACKET
LOWER- · SUPPORT STRUCTURE LUG
CAP SCREWS
COTTER
Catawba Nuclear Station UFSAR Figure 6-198 (Page 1 of 1)
(22 OCT 2001)
Figure 6-198. Block Ice Minimum Restriction Basket Assembly
Top Clamp Aucmbly
Top Plate Assembly
Cable Assembly
RJvited Stiffei,er Ring
layc,ut Dye LQ<::ation for Cru<:ifonn lmemblie.s
Rivitec! Coupling Ring
layout Dy.i Location for Cn.Jcifonn A11mibli~11
Base Plate Assembly
Clasp Assembly
--Swivd Bracket
-· Clevis Pin, Washers (2), And Retair1ing Clip
Catawba Nuclear Station UFSAR Figure 6-199 (Page 1 of 1)
(18 APR 2009)
Figure 6-199. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses
0.00E+00
2.00E+07
4.00E+07
6.00E+07
8.00E+07
1.00E+08
1.20E+08
1.40E+08
1.60E+08
1.80E+08
2.00E+08
0 5 10 15 20 25 30
TIME (SECONDS)
TO
TA
L I
NT
EG
RA
TE
D B
RE
AK
VA
PO
R E
NE
RG
Y
(BT
U)
Hot Leg Break
Cold Leg Pump Discharge Break
Catawba Nuclear Station UFSAR Figure 6-200 (Page 1 of 1)
(18 APR 2009)
Figure 6-200. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses
0.00E+00
2.00E+08
4.00E+08
6.00E+08
8.00E+08
1.00E+09
1.20E+09
0 3000 6000 9000 12000 15000
TIME (SECONDS)
TO
TA
L I
NT
EG
RA
TE
D B
RE
AK
VA
PO
R E
NE
RG
Y
(BT
U)
Hot Leg Break
Cold Leg Pump Discharge Break
Catawba Nuclear Station UFSAR Figure 6-201 (Page 1 of 1)
(18 APR 2009)
Figure 6-201. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses
0.00E+00
2.00E+04
4.00E+04
6.00E+04
8.00E+04
1.00E+05
1.20E+05
1.40E+05
0 5 10 15 20 25 30
TIME (SECONDS)
TO
TA
L I
NT
EG
RA
TE
D B
RE
AK
VA
PO
R M
AS
S
(LB
M)
Hot Leg Break
Cold Leg Pump Discharge Break
Catawba Nuclear Station UFSAR Figure 6-202 (Page 1 of 1)
(18 APR 2009)
Figure 6-202. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses
0.00E+00
1.00E+05
2.00E+05
3.00E+05
4.00E+05
5.00E+05
6.00E+05
7.00E+05
8.00E+05
9.00E+05
1.00E+06
0 3000 6000 9000 12000 15000
TIME (SECONDS)
TO
TA
L I
NT
EG
RA
TE
D B
RE
AK
VA
PO
R M
AS
S
(LB
M)
Hot Leg Break
Cold Leg Pump Discharge Break
Catawba Nuclear Station UFSAR Figure 6-203 (Page 1 of 1)
(22 OCT 2001)
Figure 6-203. Deleted Per 2000 Update.
Catawba Nuclear Station UFSAR Figure 6-204 (Page 1 of 1)
(27 MAR 2003)
Figure 6-204. Upper and Lower Compartment Pressure, Min. Pressure Analysis
6
U)
0.... 4 ...__.,
LLl
a:::: => 3 U)
U)
LLl
a:::: 0.... 2
MCGU I RE 1 AND 2. CA TAWBA 1 AND 2 M I N CONTA I NMENT PRESSURE FOR BELOCA ANALYSIS
UPPER COMPARTMENT PR ESSURE LOWER COM PA RTME NT PRESS UR E
=~ f- I
,-
:\ f-
f-
I-
f-
·:,\ f-
f-
f-
f- : A-~ f-
f-I /
~ I / I/
f- -------f- r----_ I-
f-
I I 1 I ) 1
0 50 100 I I I I I I I I I I I
200 1 50 T I M E ( S E C )
I
250 I I I I I I I I
300 350
Catawba Nuclear Station UFSAR Figure 6-205 (Page 1 of 1)
(27 MAR 2003)
Figure 6-205. Upper Compartment Heat Removal Rate, Min. Pressure Analysis
..---... u LL.J (/)
---------=::> f-
m -.._..,
LL.J
f-<J:: 0::::
_J
<J:: > 0 ~ LL.J
0::::
f-
<J:: LL.J
:::r::
MCGUIRE 1 AND 2. CATAWBA 1 AND 2 M I N CONTAINME NT PRESSURE FOR BE LOCA ANALYSIS
UP PER COMP ARTMEN T HEA T REMOVAL RATE
4000 -
3000
20 00
100 0
,-
\ -
\ -,-
I-
1-
\ -I-
I-
0
I-
I\ -I-
-- ~ -
~ -- r---
- 1000 I I I I 1 I I I I I I I I I I I I '
0 50 100 150 200 250 300 TI ME ( S E C )
350
Catawba Nuclear Station UFSAR Figure 6-206 (Page 1 of 1)
(27 MAR 2003)
Figure 6-206. Lower Compartment Heat Removal Rate, Min. Pressure Analysis
7 --- 1 0 (_)
l.J..J (/)
---------=::, 1--en
6 1 0
l.J..J
1--<I: 0:::
__j
<I: > 5
0 1 0 2 l.J..J
0:::
1--
<I: l.J..J
:r: 4 1 0
MCGUIRE 1 AND 2. CATAWBA 1 AND 2 M IN CONTAINMENT PRESSURE FOR BELOCA ANALYSIS
LOW ER COMPAR TMENT HEAT REMOVA L RATE
-----
-
-
=
~ - r --
I I I I I
0 50
-------~ I I I I I I
1 00 150
T IM E
' I I I
200 250
(SEC)
I I I ' I
300 350
Catawba Nuclear Station UFSAR Figure 6-207 (Page 1 of 1)
(27 MAR 2003)
Figure 6-207. Upper and Lower Compartment Temperature, Min. Pressure Analysis
250
---------LL
(/)
Lu
Lu 200 0::::: 0 Lu
0 ..__...
150 Lu
0::::: ~
I--<(
n::: 100 Lu o_
2 Lu
I--
50
MCGUIRE 1 AND 2, CATAWBA 1 AND 2 MIN CON TAIN ME NT PR ESSURE FOR BELOCA ANALYS I S
UPPER CO MPARTM ENT TEMPER AT UR E LOW ER COMPARTM ENT TEMP ERAT URE
-:.... r "'\ - \
- I - - - -- - - - - - I-- - - - - - - - - - - - - -\ - -'\ --
-f-
f-
~ f- ~
---.......
~ r---f-
f-
I I I I I I I I I I I I I I I I I I I I I I I I I
0 50 100 150 200 25 0 300 350 T I M E ( S E C )
Catawba Nuclear Station UFSAR Figure 6-208 (Page 1 of 1)
(27 MAR 2003)
Figure 6-208. Ice Bed Heat Removal Rate, Min. Pressure Analysis
8
MCGUIRE t ANO .2, CATAWBA 1 AND 2 MtN CONTAINMENT PRESSURE FOR BELOCA ANALYSIS
ICE BED ff[AT REMOVAL RATE
.-.... 1 O· ·-=-----.---.......... ....------.------------.----.----------. c..;> w U')
---......:- 7 ::, t 0 I-,-.
CD
6 w 10 1--,--
<C e::::
..:...J ~ <C10,=-~,i----;:;;::::::==t======:--t----:--,--,--,--"'.'--'-'-1 -> 0 :::::iE L.LJ .4
.<0::: 1 o. "'E"---t---r----t--'--:"""'""""--t"'~-~----t===::;::;::==:j 1--,-
<C L.LJ
·· :c · ref 0 50 too 150 2no 2so '. 300 350
· Tl ME '(SEC)
Catawba Nuclear Station UFSAR Figure 6-209 (Page 1 of 1)
(27 MAR 2003)
Figure 6-209. Heat Removal Rate by Lower Compartment Drain, Min. Pressure Analysis
MCGUIRE 1 AND 2, CATAWBA 1 AND 2 MI N CON TAINM ENT PRESSURE FOR BE LOCA ANAL YSIS
HEAT REMOVAL RA TE BY LC DR AIN
..--... 3-00000 I-
u I-
LiJ I-
c.n ... -........._ 250000 :::> -I-- I-
m ... -..___, 200000
I-
... LiJ -I-- -<r: -O:::'. 150000 -_J I-
<r: -> 100000 0
-
-2 I-
LiJ -O:::'. I-
50000 I--
<r: LiJ :::r:: 0
- ( Ir---I-
----------- i---_
I I I I I I ' I I I I I I I I I I I I
0 50 10 0 150 200 250 300 T I M E ( S E C )
350
Ctawba Nuclear Station UFSAR Figure 6-210 (Page 1 of 1)
(27 MAR 2003)
Figure 6-210. Heat Removal Rate by Sump and Spray, Min. Pressure Analysis
..---... u u..J (./)
------::::J
I--CD
....__...
LLJ
I--
<t: Ct:::
__J
<t: > 0 ~ LLJ
Ct:::
I--<t: LLJ
:::r::
MCG UIR E 1 AND 2. CA TAWBA 1 AND 2 MI N CONTAINM EN T PRESSU RE FOR BELOCA ANA LYS IS
HEAT REMOVAL RAT E BY SUMP HEAT REMOVAL RATE BY SPRAY
100000 t-
~ \ ~ \
80000 I
\ ~
\ ~ \
- r,..
60000 \
\ - \
\ -\
- \
40000 ' ' - \
- \ '\
- '\
20000 I '\
- ' - --.....
0
-
----------------- ..... ,\ --- -- -
I I v; I I I I I ' I I I ' ' t I I I ' ,- ,- ,- - , -, o T
0 50 100 150 200 250 300 350 TIME (S EC)