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Catawba Nuclear Station UFSAR Appendix 6B. Figures Appendix 6B. Figures

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Page 1: Appendix 6B. Figures › docs › ML1830 › ML18305A300.pdf · 2 days ago · 0 5 10 15 25 30 35 40 45 50 55 60 65 75 85 90 95 100 Time (Minutes) Catawba ... ,1J OF REACTOR COOLANT

Catawba Nuclear Station UFSAR Appendix 6B. Figures

Appendix 6B. Figures

Page 2: Appendix 6B. Figures › docs › ML1830 › ML18305A300.pdf · 2 days ago · 0 5 10 15 25 30 35 40 45 50 55 60 65 75 85 90 95 100 Time (Minutes) Catawba ... ,1J OF REACTOR COOLANT

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ure

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0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100

Time (Minutes)

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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}

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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

Page 5: Appendix 6B. Figures › docs › ML1830 › ML18305A300.pdf · 2 days ago · 0 5 10 15 25 30 35 40 45 50 55 60 65 75 85 90 95 100 Time (Minutes) Catawba ... ,1J OF REACTOR COOLANT

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

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Ca

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clear S

tatio

n

U

FS

AR

Fig

ure 6

-5 (P

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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

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Ca

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AR

Fig

ure 6

-6 (P

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Fig

ure 6

-6. P

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Co

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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

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Ca

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n

U

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AR

Fig

ure 6

-7 (P

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f 1)

(17

AP

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01

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Fig

ure 6

-7. P

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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

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Ca

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Fig

ure 6

-8 (P

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Fig

ure 6

-8. P

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men

t Tem

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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

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Ca

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Fig

ure 6

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ure 6

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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

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Ca

taw

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tatio

n

U

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AR

Fig

ure 6

-10

(Pa

ge 1

of 1

)

(17

AP

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01

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Fig

ure 6

-10. P

eak

Co

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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

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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 -

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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

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Catawba Nuclear Station UFSAR Figure 6-13 (Page 1 of 1)

(22 OCT 2001)

Figure 6-13. Drain Piping Arrangement Refueling Canal

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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

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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

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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)

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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

~

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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

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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

'"' UJ

~ 20 UJ -I I.U Cc: ,.. (!) a:: u.J z: I.U 0

...

...

FULL-SCALE SECTION TESTS

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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

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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

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Catawba Nuclear Station UFSAR Figure 6-22 (Page 1 of 1)

(22 OCT 2001)

Figure 6-22. Deleted Per 1997 Update

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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

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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

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Catawba Nuclear Station UFSAR Figure 6-25 (Page 1 of 1)

(22 OCT 2001)

Figure 6-25. Plan at Equipment Rooms Elevation

A

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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

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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

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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

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Catawba Nuclear Station UFSAR Figure 6-29 (Page 1 of 1)

(22 OCT 2001)

Figure 6-29. TMD Code Network

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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

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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)

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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)

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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)

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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)

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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

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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

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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 -- - -_.,. ... _ .. --- __ .,_ ... _ ..

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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

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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

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Catawba Nuclear Station UFSAR Figure 6-40 (Page 1 of 1)

(22 OCT 2001)

Figure 6-40. Flowpath Connections for the Reactor Cavity Analysis

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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

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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

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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}

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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)

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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}

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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}

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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)

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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)

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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}

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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)

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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)

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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)

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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)

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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)

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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)

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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}

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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)

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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)

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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)

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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)

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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)

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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

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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)

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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)

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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)

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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

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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)

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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

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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

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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

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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

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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)

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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

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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 !

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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

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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)

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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::

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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

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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

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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

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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

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Catawba Nuclear Station UFSAR Figure 6-108 (Page 1 of 1)

(22 OCT 2001)

Figure 6-108. Areas of Potential Hydrogen Pockets

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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

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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

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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!

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Catawba Nuclear Station UFSAR Figure 6-112 (Page 1 of 1)

(22 OCT 2001)

Figure 6-112. Containment Piping Penetration Valve Arrangements

.. ---..

. -••

·---IIL

...

... -·--

- -

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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':"'

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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':""

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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

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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

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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

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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

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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)

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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

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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

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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

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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 •

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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

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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

:::~-=~

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Catawba Nuclear Station UFSAR Figure 6-131 (Page 1 of 1)

(17 APR 2012)

Figure 6-131. Flow Diagram of Safety Injection System

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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

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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)

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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

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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)

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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

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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 ...

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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

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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.

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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

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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

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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

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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 -- , __ ___.., ·-, ~-----~

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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.

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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

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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

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Catawba Nuclear Station UFSAR Figure 6-144 (Page 1 of 1)

(22 OCT 2001)

Figure 6-144. Lattice Frame Analysis Model

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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

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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

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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

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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

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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

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Ca

taw

ba

Nu

clear S

tatio

n

UF

SA

R F

igu

re 6-1

50

(Pa

ge 1

of 1

)

(22

OC

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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

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Ca

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ure 6

-15

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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

!

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r

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Catawba Nuclear Station UFSAR Figure 6-152 (Page 1 of 1)

(22 OCT 2001)

Figure 6-152. Air Handling Unit Support Structure

• < • .. i

I

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Catawba Nuclear Station UFSAR Figure 6-153 (Page 1 of 1)

(21 OCT 2010)

Figure 6-153. Deleted Per 2010 Update

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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

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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

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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

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I u,

<[

N­O

·::;:, +I c:c: I'- :::r::: ::t 1--

.ci;

c:') a:i

z: 0

,. ij B U)

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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

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Ca

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ure 6

-15

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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

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l+ •! hl I 1tr

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RESTFl"'""NG STRAP RESTRAINING PIPE

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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

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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

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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

~

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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

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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

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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

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Ca

taw

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Fig

ure

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ure

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LF

Sp

ectr

a H

ot

Leg

Bre

ak

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e T

ran

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t

2.0

I. 5

-LL. ...J 0 -Cl<: 0 I-c..> < LL.

0 1.0 < 0 ...J

u

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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

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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

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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

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Ca

taw

ba

Nu

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AR

Fig

ure 6

-16

8 (P

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(22

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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

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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

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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

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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,

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N (.,J

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m

I I I I I I

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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

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a

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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;;...

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J

i t

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r I

L ~

I j I

l 1 r-

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12

140HTHS

i6 2i.

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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

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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

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Ca

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ure

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270'

275'

:lll!'

37' 0 2!!' 0 2"

6111 24 It

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1: C!JIHAl~MEUT

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suo,1e:10I q:>1!MS am1eJadwa1 pue OHi JOJ .1.z~-9 aIqe1 aas

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1&2

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Ca

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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·

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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_

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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":"

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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

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Catawba Nuclear Station UFSAR Figure 6-180 (Page 1 of 1)

(22 OCT 2001)

Figure 6-180. Deleted Per 2001 Update

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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

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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

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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)

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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 ✓ -------

----- --------- ---

--. -------- ----- --. --

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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

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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

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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

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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

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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

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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)

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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)

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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)

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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)

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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)

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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

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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

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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

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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

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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

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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

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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

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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

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Catawba Nuclear Station UFSAR Figure 6-203 (Page 1 of 1)

(22 OCT 2001)

Figure 6-203. Deleted Per 2000 Update.

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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

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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

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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

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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 )

Page 201: Appendix 6B. Figures › docs › ML1830 › ML18305A300.pdf · 2 days ago · 0 5 10 15 25 30 35 40 45 50 55 60 65 75 85 90 95 100 Time (Minutes) Catawba ... ,1J OF REACTOR COOLANT

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)

Page 202: Appendix 6B. Figures › docs › ML1830 › ML18305A300.pdf · 2 days ago · 0 5 10 15 25 30 35 40 45 50 55 60 65 75 85 90 95 100 Time (Minutes) Catawba ... ,1J OF REACTOR COOLANT

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

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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 '\

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0

-

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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)