ML21229A016

From kanterella
Jump to navigation Jump to search
1 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3B, Figures - NRC (Redacted
ML21229A016
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 10/22/2001
From:
Duke Energy Carolinas
To:
Division of Operating Reactor Licensing
Stone Z
Shared Package
ML21228A237 List:
References
Download: ML21229A016 (124)


Text

Catawba Nuclear Station UFSAR Appendix 3B. Figures Appendix 3B. Figures

Catawba Nuclear Station UFSAR Figure 3-1 (Page 1 of 1)

(22 OCT 2001)

Figure 3-1. Wind Pressure Distribution On The Reactor Building EL JIZ.+3

[L.fi'la*_Y _

~.t;93+!_

~L.li89+1i

[L. 591

  • 6 EL.59'.h_6 EL 58!1+1i EL 553*6._

El. 54~

  • Ii 1.35 l

IIS

/10 n:

y li

w.
n:

I:

OI

.,o 8

+ J,o

-0 7 P*llTS rnz w.m AEII

-0 ~

-0 4

<J.4 l Cpe * - 6 *.3 cos I+.929 cos 21

  • 411 cos 31 -.Oi COS 48
  • 01~ cas 51
  • Q;l cos 6a -

008 CDS lt -

If, cos Ila

-I

\\

11/'\\

_1__

)./

-O'l " -08

-II

\\/

-I*),(_

    • U

-12 _f PART 1X J4

  • 4

.::; 8

~ART.X OB

-0 7 1:111' * -

1fl6 -

337 cos t + 179 cos 2* -

Ol cos Ja Cpl Di -

1121 COS I + 221 CDS 2t + 111 en Jt

-.IDB cas 4a *.005 CDS 5t -.038 cos 6a OO'J ***5"-

013co*6a

  • 011.., 1,

-.004 CDS 79 -

013 CDS Ila 008 cos Be I

L_J

~I:,

. ~\\\\\\

LJ

... ~----------.....

/

_,/

r

/

~I lo

/

/,,.

/

I I

1/

I

\\

L.J

_J r'Afl; XI PAllT :xJI Cpe * -115 QJe = -1 15

, r:~

e' 'l '<.UPc C(,[F1 IUEMT

Catawba Nuclear Station UFSAR Figure 3-2 (Page 1 of 1)

(22 OCT 2001)

Figure 3-2. Wind Pressure Distribution For Rectangular Structures

,...,~o WINO@

I I I I


~ l J

I /- ~

L/-/~-

@)

1 ~~

---+---

~

L :'._J PLAN VIEW STRUCTURE WINO

..... ~..,-

AUXILIARY N-S BUILDING E-W DOGHOUSE STR.

N-S a NEW FUEL BLDG.

E-W SPENT FUEL N-S POOL BUILDING E-W p * (Cpe)fvl

  • ( Cpe I (.002558)19:5)1 s 23.09(Cpe)

COEFFICIENT (Cpe) 0 @

0.9 l-0.:5 -0.4 ~...

0.9 -0.3 i-0.4 -0.4 0.9 0.5 i-0.7 t-0.7 0.9 -0.5 0.6 -0.6 0.9 -0.5 -0.7 -0.7 0.9 -0.5 '-0.6 0.6 f*.002558 (p.1150, Ref. I) ya 95 mph p* psf

~.8 *O.B k).3 0.8 0.8 -0.3 0.6 ~o.6 0.:5

-0.7 0.7 -0.:5

-0.6 -0.6 f-0.5 0.7 -0.7 -0.5 0.3

-0.3

-0.5

-0.:1

-0.5

-0.5

Catawba Nuclear Station UFSAR Figure 3-3 (Page 1 of 1)

(22 OCT 2001)

Figure 3-3. Turbine Building Tornado Velocity Distribution

~

,S1.t*1, N

,u*,r

~

  • a,,

~!..

I-

,g:n

. ~"Cl 110001

,H tll

,9.Lffl

  • c,

,u*111

,S.ntl

Catawba Nuclear Station UFSAR Figure 3-4 (Page 1 of 1)

(22 OCT 2001)

Figure 3-4. Tornado Wind Loads - Design Velocity Vs. Radius From Center Of Tornado 360mph

~

~

~

~

70m LINEAR 1501 Radius in F<<JI VR I.S =C

Catawba Nuclear Station UFSAR Figure 3-5 (Page 1 of 1)

(22 OCT 2001)

Figure 3-5. Turbine Missile Ejection Zones

(

TURBINE l>'ISSILE EJECTION ZONES CATAWBA J\\l.JCLEAR STATION Figure 3.5.1-l

Catawba Nuclear Station UFSAR Figure 3-6 (Page 1 of 1)

(22 OCT 2001)

Figure 3-6. Loss Of Reactor Coolant Accident Boundary Limits CASE I CASE D CASE m CASE II CASE I:

OUTGOING LINES WITH MORMALLY CLOSED VALVE

/

REACTOR COO..AN T P I PI NG I

)

OUTGOING LINES 1111TH '-ORt~AlLY OPEN VALVES F41 L CLOSED OR tAIL-AS*IS ULVES RESTRJI.INT

_J_*

I I BOUNDARY INCOMING L1NES NORMALLY WlTH FLOW NO.

NO. 2

...i.

BOUNDARY NOTE:

PRESSURIZER SAFETY VALVE)

ARE INCLUDED UNDER THIS CASE.

NOH:

THE REACTOR COOLANT PUMP NO. l SEAL IS ASSUt1EO TO BE EQUl~ALENT ;Q FIRST I/AL'¥£ TEST CONNECTI.ON INC0~1NG LlHES ~ORMALLY WITHOUT FLOW

_L BOUNDARY TEST CONNECTION (MEANS OF 1/ERIFYING THAT CHECK VALVE IS CLOSED)

ALL INSTRUMENTATION TUBING AND INSTRUMENTS CONNECTED DIRECTLY TO THE REACTOR COOLANT SYSTEM 1s*coNSIOERED AS A BOUNDARY.

HOWEVER. A BREAk WITHIN THI s *aouNDAAY RESULTS IN A RELATl'HLY SMALL FLOW WHICH CAN NORMALLY BE MADE UP. WITH THE CHARGING SYSTEM,

Catawba Nuclear Station UFSAR Figure 3-7 (Page 1 of 1)

(22 OCT 2001)

Figure 3-7. Location Of Postulated Breaks In Main Reactor Coolant Loop REACTOR PRESSURE VESSEL

(__

STEAM GENERATOR 9 DENOfES BREAK LOCATION REACTOR PllESSURE VESSEL

Catawba Nuclear Station UFSAR Figure 3-8 (Page 1 of 1)

(22 OCT 2001)

Figure 3-8. Deleted Per 2001 Update

Catawba Nuclear Station UFSAR Figure 3-9 (Page 1 of 1)

(22 OCT 2001)

Figure 3-9. Reactor Coolant Loop Model 189 IOI L,...

RESTRAINT COLD LEG IESTRAIIH ROT LEG RESTRAINT STEAM GENERATOI 139 STEAM GENEIATOII UPPEI SIJPPOIIT (SGUS)

~

CROSSOYEI LEG IIESTUINT (XLVII) j CflOSSOVER LEG RESTRAINT (llLSG) 179 UACTOlt tOOLlNT PUMP

\\

!:C~l' CIOSSOVER LEG RESTUIIIT

( NLRCP)

Catawba Nuclear Station UFSAR Figure 3-10 (Page 1 of 1)

(22 OCT 2001)

Figure 3-10. Time-History Dynamic Solution For Loca Loading Time-History Dynamic Solution for LOCA Loading Reactor Coolant Equipment LOCA Forcing Loop Support Structure Functions 1

Loop Geometry Support Structure and Model Stiffness Matrices I

t Define Initial Oefl ect ion of the System 1-a---1'

.... ~

t Natural Frequencies and Normal Modes Dynamic Displacement Response at Mass Points t

Compute Time-History Forces, Stresses and Displacements t

I Piping Stress Evaluation! !support Member Evaluation I

Catawba Nuclear Station UFSAR Figure 3-11 (Page 1 of 1)

(22 OCT 2001)

Figure 3-11. Typical Cold Penetration PROCESS PIPE RESTRAINT RING

~6

~

3"-o' REACTOR BLDG.

WALL

~.

h...

  • i-

~ -

'b._ -_.... -

  • . ~.

.:.* ti,;'*_

  • 'b

~. -~.

. t>.

... '. h o,.*.* :"'..

h b

D.

  • b _

(;,.

/, -

~

. A* t..*

.A.:-~.1,..*._

.* ~. ;,.*

-~-

6*-o*

(NOMINAL)

PIPE CAP TEST CONNECTION FLAT HEAD

~----0s

-~,i-,Lll-_..:,p

~~

TYPICAL COLD PENETRATION

~-;;;.§iiF*'

CONTAINMENT VESSEL

Catawba Nuclear Station UFSAR Figure 3-12 (Page 1 of 1)

(22 OCT 2001)

Figure 3-12. Typical Main Steam And Feedwater Penetration I

11 11 13-0 Ii, I

,t 6 - 0 n.,..,, nai

....-ANCHOR RING 1

BELLOWS GUARD SHROUD l,\\s II S\\ \\\\ ii \\\\ \\I I\\ 'I II §\\\\II I' §\\:h:s'rri,l

/

l

-CONTAINMENT VESSEL

-FLUED HEAD GUARD PIPE

!M"-'\\.~11" " 11 u ss S1 11 11 11 11 n,, 11 tus 11 11 11 ss ss 11 "

ss 11 "

15 n ss 1s II ss 15 ss

§

" << ss u " "

" >>,. 11 Ii 11 1,s § + ---PROCESS PIPE 1-,===:,c2=:DVlJUlflf w,, u*u 1

REACTOR BLDG

.. *,:: WALL TYPICAL MAIN STEAM AND FEEDWATER P[NETr~ATION

Catawba Nuclear Station UFSAR Figure 3-13 (Page 1 of 1)

(22 OCT 2001)

Figure 3-13. Typical Hot Penetration FLUED HEAD 1--

~- o* __ _ 't

~- ---\\"--f:I

'_* R:A~TOR ~ B,L;DG _~:.*

~., WALL,

_ D

t,. ; *. :.6 d_.., : '.. :

' ; t:.

  • !i.. ' 6:

\\

t,;1>=-.*

!\\

.b:*

    • I b

. : "4. '

.., *' t,..*

,l>-

\\"

j

~.-

. ~*,,'... *.. _(>,

.,'\\.'

.'ti.' -. **.

t,.'"*.

.d

---\\V-.. -~~ - -

12'-o"_

6'-d' TEST CONNECTION BELLOWS JOINT ~\\,

\\

{V\\_

ANCHOO RING TYPICAL HOT PENETRATION i

GUARD PIPE

_/,../ PROCESS PIP CONTAINMENT VESSEL

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 1 of 12)

(22 OCT 2001)

Figure 3-14. Deleted Per 1990 Update Figure 3-15. Deleted Per 1990 Update Figure 3-16. Deleted Per 1990 Update Figure 3-17. Deleted Per 1990 Update Figure 3-18. Deleted Per 1990 Update Figure 3-19. Deleted Per 1990 Update Figure 3-20. Deleted Per 1990 Update Figure 3-21. Deleted Per 1990 Update Figure 3-22. Deleted Per 1990 Update Figure 3-23. Deleted Per 1990 Update Figure 3-24. Deleted Per 1990 Update Figure 3-25. Deleted Per 1990 Update Figure 3-26. Deleted Per 1990 Update Figure 3-27. Deleted Per 1990 Update Figure 3-28. Deleted Per 1990 Update Figure 3-29. Deleted Per 1990 Update Figure 3-30. Deleted Per 1990 Update Figure 3-31. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 2 of 12)

(22 OCT 2001)

Figure 3-32. Deleted Per 1990 Update Figure 3-33. Deleted Per 1990 Update Figure 3-34. Deleted Per 1990 Update Figure 3-35. Deleted Per 1990 Update Figure 3-36. Deleted Per 1990 Update Figure 3-37. Deleted Per 1990 Update Figure 3-38. Deleted Per 1990 Update Figure 3-39. Deleted Per 1990 Update Figure 3-40. Deleted Per 1990 Update Figure 3-41. Deleted Per 1990 Update Figure 3-42. Deleted Per 1990 Update Figure 3-43. Deleted Per 1990 Update Figure 3-44. Deleted Per 1990 Update Figure 3-45. Deleted Per 1990 Update Figure 3-46. Deleted Per 1990 Update Figure 3-47. Deleted Per 1990 Update Figure 3-48. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 3 of 12)

(22 OCT 2001)

Figure 3-49. Deleted Per 1990 Update Figure 3-50. Deleted Per 1990 Update Figure 3-51. Deleted Per 1990 Update Figure 3-52. Deleted Per 1990 Update Figure 3-53. Deleted Per 1990 Update Figure 3-54. Deleted Per 1990 Update Figure 3-55. Deleted Per 1990 Update Figure 3-56. Deleted Per 1990 Update Figure 3-57. Deleted Per 1990 Update Figure 3-58. Deleted Per 1990 Update Figure 3-59. Deleted Per 1990 Update Figure 3-60. Deleted Per 1990 Update Figure 3-61. Deleted Per 1990 Update Figure 3-62. Deleted Per 1990 Update Figure 3-63. Deleted Per 1990 Update Figure 3-64. Deleted Per 1990 Update Figure 3-65. Deleted Per 1990 Update Figure 3-66. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 4 of 12)

(22 OCT 2001)

Figure 3-67. Deleted Per 1990 Update Figure 3-68. Deleted Per 1990 Update Figure 3-69. Deleted Per 1990 Update Figure 3-70. Deleted Per 1990 Update Figure 3-71. Deleted Per 1990 Update Figure 3-72. Deleted Per 1990 Update Figure 3-73. Deleted Per 1990 Update Figure 3-74. Deleted Per 1990 Update Figure 3-75. Deleted Per 1990 Update Figure 3-76. Deleted Per 1990 Update Figure 3-77. Deleted Per 1990 Update Figure 3-78. Deleted Per 1990 Update Figure 3-79. Deleted Per 1990 Update Figure 3-80. Deleted Per 1990 Update Figure 3-81. Deleted Per 1990 Update Figure 3-82. Deleted Per 1990 Update Figure 3-83. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 5 of 12)

(22 OCT 2001)

Figure 3-84. Deleted Per 1990 Update Figure 3-85. Deleted Per 1990 Update Figure 3-86. Deleted Per 1990 Update Figure 3-87. Deleted Per 1990 Update Figure 3-88. Deleted Per 1990 Update Figure 3-89. Deleted Per 1990 Update Figure 3-90. Deleted Per 1990 Update Figure 3-91. Deleted Per 1990 Update Figure 3-92. Deleted Per 1990 Update Figure 3-93. Deleted Per 1990 Update Figure 3-94. Deleted Per 1990 Update Figure 3-95. Deleted Per 1990 Update Figure 3-96. Deleted Per 1990 Update Figure 3-97. Deleted Per 1990 Update Figure 3-98. Deleted Per 1990 Update Figure 3-99. Deleted Per 1990 Update Figure 3-100. Deleted Per 1990 Update Figure 3-101. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 6 of 12)

(22 OCT 2001)

Figure 3-102. Deleted Per 1990 Update Figure 3-103. Deleted Per 1990 Update Figure 3-104. Deleted Per 1990 Update Figure 3-105. Deleted Per 1990 Update Figure 3-106. Deleted Per 1990 Update Figure 3-107. Deleted Per 1990 Update Figure 3-108. Deleted Per 1990 Update Figure 3-109. Deleted Per 1990 Update Figure 3-110. Deleted Per 1990 Update Figure 3-111. Deleted Per 1990 Update Figure 3-112. Deleted Per 1990 Update Figure 3-113. Deleted Per 1990 Update Figure 3-114. Deleted Per 1990 Update Figure 3-115. Deleted Per 1990 Update Figure 3-116. Deleted Per 1990 Update Figure 3-117. Deleted Per 1990 Update Figure 3-118. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 7 of 12)

(22 OCT 2001)

Figure 3-119. Deleted Per 1990 Update Figure 3-120. Deleted Per 1990 Update Figure 3-121. Deleted Per 1990 Update Figure 3-122. Deleted Per 1990 Update Figure 3-123. Deleted Per 1990 Update Figure 3-124. Deleted Per 1990 Update Figure 3-125. Deleted Per 1990 Update Figure 3-126. Deleted Per 1990 Update Figure 3-127. Deleted Per 1990 Update Figure 3-128. Deleted Per 1990 Update Figure 3-129. Deleted Per 1990 Update Figure 3-130. Deleted Per 1990 Update Figure 3-131. Deleted Per 1990 Update Figure 3-132. Deleted Per 1990 Update Figure 3-133. Deleted Per 1990 Update Figure 3-134. Deleted Per 1990 Update Figure 3-135. Deleted Per 1990 Update Figure 3-136. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 8 of 12)

(22 OCT 2001)

Figure 3-137. Deleted Per 1990 Update Figure 3-138. Deleted Per 1990 Update Figure 3-139. Deleted Per 1990 Update Figure 3-140. Deleted Per 1990 Update Figure 3-141. Deleted Per 1990 Update Figure 3-142. Deleted Per 1990 Update Figure 3-143. Deleted Per 1990 Update Figure 3-144. Deleted Per 1990 Update Figure 3-145. Deleted Per 1990 Update Figure 3-146. Deleted Per 1990 Update Figure 3-147. Deleted Per 1990 Update Figure 3-148. Deleted Per 1990 Update Figure 3-149. Deleted Per 1990 Update Figure 3-150. Deleted Per 1990 Update Figure 3-151. Deleted Per 1990 Update Figure 3-152. Deleted Per 1990 Update Figure 3-153. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 9 of 12)

(22 OCT 2001)

Figure 3-154. Deleted Per 1990 Update Figure 3-155. Deleted Per 1990 Update Figure 3-156. Deleted Per 1990 Update Figure 3-157. Deleted Per 1990 Update Figure 3-158. Deleted Per 1990 Update Figure 3-159. Deleted Per 1990 Update Figure 3-160. Deleted Per 1990 Update Figure 3-161. Deleted Per 1990 Update Figure 3-162. Deleted Per 1990 Update Figure 3-163. Deleted Per 1990 Update Figure 3-164. Deleted Per 1990 Update Figure 3-165. Deleted Per 1990 Update Figure 3-166. Deleted Per 1990 Update Figure 3-167. Deleted Per 1990 Update Figure 3-168. Deleted Per 1990 Update Figure 3-169. Deleted Per 1990 Update Figure 3-170. Deleted Per 1990 Update Figure 3-171. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 10 of 12)

(22 OCT 2001)

Figure 3-172. Deleted Per 1990 Update Figure 3-173. Deleted Per 1990 Update Figure 3-174. Deleted Per 1990 Update Figure 3-175. Deleted Per 1990 Update Figure 3-176. Deleted Per 1990 Update Figure 3-177. Deleted Per 1990 Update Figure 3-178. Deleted Per 1990 Update Figure 3-179. Deleted Per 1990 Update Figure 3-180. Deleted Per 1990 Update Figure 3-181. Deleted Per 1990 Update Figure 3-182. Deleted Per 1990 Update Figure 3-183. Deleted Per 1990 Update Figure 3-184. Deleted Per 1990 Update Figure 3-185. Deleted Per 1990 Update Figure 3-186. Deleted Per 1990 Update Figure 3-187. Deleted Per 1990 Update Figure 3-188. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 11 of 12)

(22 OCT 2001)

Figure 3-189. Deleted Per 1990 Update Figure 3-190. Deleted Per 1990 Update Figure 3-191. Deleted Per 1990 Update Figure 3-192. Deleted Per 1990 Update Figure 3-193. Deleted Per 1990 Update Figure 3-194. Deleted Per 1990 Update Figure 3-195. Deleted Per 1990 Update Figure 3-196. Deleted Per 1990 Update Figure 3-197. Deleted Per 1990 Update Figure 3-198. Deleted Per 1990 Update Figure 3-199. Deleted Per 1990 Update Figure 3-200. Deleted Per 1990 Update Figure 3-201. Deleted Per 1990 Update Figure 3-202. Deleted Per 1990 Update Figure 3-203. Deleted Per 1990 Update Figure 3-204. Deleted Per 1990 Update Figure 3-205. Deleted Per 1990 Update Figure 3-206. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3 Figure 212 (Page 12 of 12)

(22 OCT 2001)

Figure 3-207. Deleted Per 1990 Update Figure 3-208. Deleted Per 1990 Update Figure 3-209. Deleted Per 1990 Update Figure 3-210. Deleted Per 1990 Update Figure 3-211. Deleted Per 1990 Update Figure 3-212. Deleted Per 1990 Update

Catawba Nuclear Station UFSAR Figure 3-213 (Page 1 of 1)

(22 OCT 2001)

Figure 3-213. Design Response Spectrum,.15g Undamped Period (sec.)

LEGEND 0.lign Spectra


Spectra per Regulatory Guide I. 60

Catawba Nuclear Station UFSAR Figure 3-214 (Page 1 of 1)

(22 OCT 2001)

Figure 3-214. Response Acceleration Spectra GI 0

0 0

0 t-d 0.0!5 l

I J

I 0.10 A

!~ fiJ tll'\\ Iv I

",~

t 0.20


R£$UL S FROM /TIME l TEPS IN I

-- RESUL: S FROM rTIME l TEPS INI I

\\

~

I J V

~ ~'\\

\\_ r----. ---I'-r---

0.!50 1.00 2.00

!5.00 10.00 PERIOD IN SECONDS

Catawba Nuclear Station UFSAR Figure 3-215 (Page 1 of 1)

(22 OCT 2001)

Figure 3-215. Response Acceleration Spectra

.c cc:

VJ C

ci t

.,.-/

'iJ. 05 I

J i

J I~

~~l \\

~

v I

~

vv I

I I

I

o. 10

~ESUL TS FRCPI T 111£ STI PS II I

~£SUI TS FRO~ T IME ST PS II Ill I

I I

I I

J I

i i

' \\,

~

V V l\\

I i

\\._ ----r---~

a.so l.00

2. a*

5.0*

10.Ca PERI~O IN SEC~N05

Catawba Nuclear Station UFSAR Figure 3-216 (Page 1 of 1)

(22 OCT 2001)

Figure 3-216. Damping Valve For Seismic Analysis Of Piping (Applicable To Both OBE and SSE, Independent Of Pipe Diameter) 4

_,I

~

3 u.....

I-.....

0::

u o,-.'l. -

2

(.!)

z:

c..

~

c:(.

0 0

0 10 20 30 Frequency (Hz.)

Catawba Nuclear Station UFSAR Figure 3-217 (Page 1 of 1)

(22 OCT 2001)

Figure 3-217. Containment Interior Structure Lumped Mass Model Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-218 (Page 1 of 1)

(22 OCT 2001)

Figure 3-218. Auxiliary Building Elevation Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-219 (Page 1 of 1)

(22 OCT 2001)

Figure 3-219. Exterior Doghouse And UHI Elevation Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-220 (Page 1 of 1)

(22 OCT 2001)

Figure 3-220. Diesel Generator Building Elevation Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-221 (Page 1 of 1)

(22 OCT 2001)

Figure 3-221. Nuclear Service Water Pump Structure Elevation WT 9 El.BiMo G)

WT 8 Q).

WT7 G)

WT 6

(]

. WT 5 El.600.00 l I G)

WT 4 G)

Q)l WT 3

. WT 2 0

LUMPED MASS MODEL M!Mel I UNmi

~

(FT.). ', (FT:2}

1-6 10.33 1$3 EL. 545.83 r I I.. 7~8 10.00 771 MOSS HUCLEAB S~Bm wme el)Me SIB~Ulll; El.milllR I wss

~

P(lNT$.

WT*t WT-2 3847 548.33 WT-3 am 558:00 wr-.4 3271 BOO wt-5 2142 579i38 wt-6 2141 500.~

WT-7 2775 a:noo wr-s*

13EKJ 610.00

.WT-9 1531 EW.00 N

w

  • 7*

E s

STR.clUW.PFO&(hES,

. :x-AXIS

~

-6J=EA I OJ X;(1o)

. {Fl'.~..... (Ff.i,..

tl?f.

346 563

m Y-A>aS SJEllfl.*

.. MA.

.* -I OJx_ (.1.o)

(FT.~..

o=r.,

8l!

364 a>t 434 2-AXIS (l,)x(1o)

(Fti,"

1364 742

Catawba Nuclear Station UFSAR Figure 3-222 (Page 1 of 1)

(22 OCT 2001)

Figure 3-222. Reactor Building First And Second Horizontal Mode Shapes I

EL 549~6 rs-1 HORIZONAL MODE 5.3 r~s 2~ HORIZONTAL MODE

(;, - IS. I CPS

Catawba Nuclear Station UFSAR Figure 3-223 (Page 1 of 1)

(22 OCT 2001)

Figure 3-223. Reactor Building First And Second Vertical Mode Shapes I

II EL. 549+6 1~1 VERTICAL MODE f1 =-l3.29 CPS I

EL,. 549+6 2ND VERTICAL MODE

~2== 19. 4 7 CPS

Catawba Nuclear Station UFSAR Figure 3-224 (Page 1 of 1)

(22 OCT 2001)

Figure 3-224. Reactor Building Shear Force, Q (lb/in), Due To SSE 0

327.48 c::._ ___

Catawba Nuclear Station UFSAR Figure 3-225 (Page 1 of 1)

(22 OCT 2001)

Figure 3-225. Reactor Building Meridional Force, N (lb/in), Due To SSE 465.0 4 59. 06

Catawba Nuclear Station UFSAR Figure 3-226 (Page 1 of 1)

(22 OCT 2001)

Figure 3-226. Reactor Building Meridional Moment, M (in-lb/in.), Due To SSE 2103.5

~

9321.6 28880.4

Catawba Nuclear Station UFSAR Figure 3-227 (Page 1 of 1)

(22 OCT 2001)

Figure 3-227. Reactor Building Membrane Shear N (lb/in) Due To SSE

.01 831.3 tO 121 ~..----¥ 3241.Q..

Catawba Nuclear Station UFSAR Figure 3-228 (Page 1 of 1)

(22 OCT 2001)

Figure 3-228. Reactor Building Hoop Force No (lb/in) Due To SSE 1402.8 291 t.I 1498. 2

Catawba Nuclear Station UFSAR Figure 3-229 (Page 1 of 1)

(22 OCT 2001)

Figure 3-229. Reactor Building Hoop Moment MO (in-lb/in) Due To SSE IOZ9*3 15~a-.a.

2050. P

Catawba Nuclear Station UFSAR Figure 3-230 (Page 1 of 1)

(22 OCT 2001)

Figure 3-230. Containment Interior Structure First Four Horizontal Mode Shapes North-South Direction MODE I MODE 2 MODF 4>

MODE 4

f, -6_74 *:":.PS r2 ° 20.76 :Ps 43 34.33 -.PS r4 =49.6 7 PS

Catawba Nuclear Station UFSAR Figure 3-231 (Page 1 of 1)

(22 OCT 2001)

Figure 3-231. Containment Interior Structure First Four Horizontal Mode Shapes East-West Direction

Catawba Nuclear Station UFSAR Figure 3-232 (Page 1 of 1)

(22 OCT 2001)

Figure 3-232. Containment Interior Structure First Tow Vertical Mode Shapes Vertical Direction I

MODE I

MODE 2 f'1 = 19.10 CPS 42 =- 50.56 CP5

Catawba Nuclear Station UFSAR Figure 3-233 (Page 1 of 1)

(22 OCT 2001)

Figure 3-233. Reactor Building Interior Structure Response Loads North-South, SSE

(

(

r I,

Accft&RAT)0,,1 (i='T/~,'1)

!Uf.i!TIAL fl.l(@i:

(lo:.,.... '5)

Di~pL..A,c:,.e.MF,.,;Jf (Fe;e.T,.ID"~)

REACTOO: BUILDING INTERIOR STRUCTURE RESPONSE LOADS NORTH-SOUTH, SSE CATAWBA ffJCLEAA STATION Figure 3.7.2-17

Catawba Nuclear Station UFSAR Figure 3-234 (Page 1 of 1)

(22 OCT 2001)

Figure 3-234. Reactor Building Interior Structure Response Loads East-West, SSE

(

('

\\

REACTOR BUILDING INTERIOR STRUCTURE RESPONSE LOADS EAST -WEST, SSE CATAWBA NUCLEAR STATION Figure 3.7.2-18

Catawba Nuclear Station UFSAR Figure 3-235 (Page 1 of 1)

(22 OCT 2001)

Figure 3-235. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 556+8, (OBE) t:J Ul a

0 0

a:

en

~

Cl.

...,o cr:

a::

w.,,

...J_

w.

uo u a:

w V]O z-oo a..

If')

w a::

a Cl a

D.

CATRWBR NUCLEAR STATI~N RESPONSE RCCELERRTION SPECTRA, DAMPING= 0.050 REACTOR INTERI *R, N-5 DIAECTIDN. EL. 556+8 I-7 I

I I

(\\ {\\

I r-.

I I,

I V I

I~

~ 1\\

/

V"'

J V

\\ ' \\

I f\\ '

/

I\\

\\

I 1/

\\/' '.

I I

~

V

\\\\

I

/ )

\\

I

\\\\

I I v

~

~

~

'-I\\'-

\\.:

9:J. 05

o. 10 0.20 0.50 1.00 2.00 PERIOD IN SECONDS I'-

i" r--..::s.

S.00 10,00

Catawba Nuclear Station UFSAR Figure 3-236 (Page 1 of 1)

(22 OCT 2001)

Figure 3-236. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 592+2, (OBE)

CRTRWBR NUCLEAR STATION AESP*NSE ACCELERATI~N SPECTRR, DAMPING~ 0.050 DRERCT*R INTERIOR. N-5 OJRECTICJN.

EL, 592-t-2

,7 0

C C

_o a:

en

  • o z"'

0.....,o

..-a:

a:

w

__Jo w""

uo

(.J a:

w

(!)O z"'

Oo IL

(!)

w a::

0 0

0 0

k;:.

"b.os L/ /

I I

I I

I I

I I

I J l/ _.. ~

D. 10

~\\

\\' \\

\\

\\

\\

\\

~

- (\\ ~"

V

~

~

V I\\~,

~,,

rs r--..c::::; ~

~

0.20 D. 50 1.00 2.00 PERI~* IN SEC~NDS I'-- --

~t::

r--.

5.00 10.00

Catawba Nuclear Station UFSAR Figure 3-237 (Page 1 of 1)

(22 OCT 2001)

Figure 3-237. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 609+10, (OBE) a:

(J')

0

~

C "'

C N

C C

C CATAWBA NUCLEAR STRTIDN RESP* NSE ACCELEART!ClN SPECTRA, DAMPING= 0.050 R E A C T D A 1 N T E R 1 Cl A, N *** 5 D I R E C T ICl N, E L. 6 0 9 -t I 0 I

I I I

) \\ \\

I \\ \\

I

\\

I I I \\ \\

I I

1/

\\ \\

I(\\

V

"'\\ ~

rv K

. l.J I/

I'----

i---' v I'....

I...:=: I--

r-,...

l.:::r-I'.

['\\

I---

I'---.

)-.. -.

r---.. r-- --

I'-

°tJ. OS

0. I 0 0.20 0, 50 I.DO 2.00 PER(OO IN SECONDS

~- -

~

5.00 10.00

Catawba Nuclear Station UFSAR Figure 3-238 (Page 1 of 1)

(22 OCT 2001)

Figure 3-238. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 643+6, (OBE)

C>...

C>

Zc

..... 0 u.J enc ZID Oo a..

[/)

L.U a:

0 :::,

C 0

0 CATAWBA NUCLEAR STATION RESPONSE RCCELERRT]ON SPECTRA, ORMPINC= 0.050 AEACTCJR INTERIC'IR, N-S DIAECTIDN. EL. 643-t-6 r 7

! I

// \\\\

1// \\

1*

\\

I iv

\\ \\ ~'

__. [:;~

'--='- ~

~.... re. -

I--

~

I-- t-- -._

f-.-

I'--.._

r-....r--__

  • 1------L---

9J. 05 0.10 0.20 0.50 I.00 2,00 PERIOD JN S[C~N05 5.00 l 0. 00

Catawba Nuclear Station UFSAR Figure 3-239 (Page 1 of 1)

(22 OCT 2001)

Figure 3-239. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 668+10, (OBE)

CRTRWBR NUCLEAR STATION RESPONSE RCCELERRTIDN SPECTRA. DAMPING= 0.050 0 RERCT~R INTERIOR, N-S DIRECTICJN, EL, 668+)0 0:,

N 0

I' N
i~

O*

1-a:

a:

w

..... ~

w.

u-u Ir a a "t.05

~

r'-7 I

I I

I

! I I

I I

I J --

l ii I

I

\\

// \\I lV

~

1_,... L; 1,-'

0. 10 0.20

- - '\\,; r-Z --

f---

I'--+----r-- -.___

r---_

..... ----- ~

0,50

1. 00 2.00 F(Hl~O IN S£C~N05

--f-5.00 10.00

Catawba Nuclear Station UFSAR Figure 3-240 (Page 1 of 1)

(22 OCT 2001)

Figure 3-240. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 609+10, (OBE) 0 N

C)

~o 0

zo oa>

-0 I-

<[

11::

l.iJ

....Jo l.iJ"'

Oo u

<[

l.iJ Cl) 0 z~

~o Cl) w 0::

0 N

0 0

0

~

0 0.05 I

/

v I--'

~

I I

I I

I \\ \\

I I

\\

I I

I I

I

\\ \\

I \\

I "vAdj I

I I

I

//

' I

~\\~

V

~

ll Colculat l'Jd S1 ectrum

  • 0,10 0.20

~sted Spe truin

-tr ~ i\\ '

r-,, '-,_

~

r---. -

I'---

,r-=:.: r=:-:: ::::--- ----,.

0.50 1.00 2.00 5.00 10.00 PERIOD IN SECONDS

Catawba Nuclear Station UFSAR Figure 3-241 (Page 1 of 1)

(22 OCT 2001)

Figure 3-241. Soil Pressure Diagram For Substructure Walls Of Auxiliary Building t.t3KY 79.70 K/FT.

3.156 KS' STATIC EAllTH PRE'5SUR!

  • LAT£11AL 51JSMIC PR[SSUR[

- US[D,o" DESIGN 79.70 K/f'T.

3.156 KSf' STATIC EARTH PRlSSURE

+ LAT[RAL EARTH P'RC55U RE rROM MONONOB[-OKAIIC COEFFICIENT ANALYSIS

Catawba Nuclear Station UFSAR Figure 3-242 (Page 1 of 1)

(22 OCT 2001)

Figure 3-242. Multi-Degree Of Freedom System

Catawba Nuclear Station UFSAR Figure 3-243 (Page 1 of 1)

(22 OCT 2001)

Figure 3-243. Reactor Building And Containment Structural Outline SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-244 (Page 1 of 1)

(22 OCT 2001)

Figure 3-244. Reactor Building Bottom Radial Bars

,,********j' N

'11

\\I,,

I\\

'\\

I I

\\

_j_J___

,,/

--~

',.c.-_;.,*:.;:-..::'-_;.\\*.:,. ***'"\\,,.,:*

~

~

Catawba Nuclear Station UFSAR Figure 3-245 (Page 1 of 1)

(22 OCT 2001)

Figure 3-245. Reactor Building Top Radial Bars t

I

-~-l j!

-_ -*~ --

!L.~-----

Catawba Nuclear Station UFSAR Figure 3-246 (Page 1 of 1)

(22 OCT 2001)

Figure 3-246. Reactor Building Circular Bars

Catawba Nuclear Station UFSAR Figure 3-247 (Page 1 of 1)

(22 OCT 2001)

Figure 3-247. Containment Vessel And Equipment Anchorage Details

(

~

~-~

~§..'I.L=.IT-*

CONTAINMENT VESSEL AND EQUIPMENT ANCHORAGE DETAILS CATAWBA 'UCLEAR STATION rigure 3.8.1-5

Catawba Nuclear Station UFSAR Figure 3-248 (Page 1 of 1)

(22 OCT 2001)

Figure 3-248. Reactor Building Shell Wall Developed Elevation Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-249 (Page 1 of 1)

(22 OCT 2001)

Figure 3-249. Reactor Building Shell Wall Developed Elevation Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-250 (Page 1 of 1)

(22 OCT 2001)

Figure 3-250. Reactor Building Shell Wall Developed Elevation Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-251 (Page 1 of 1)

(22 OCT 2001)

Figure 3-251. Reactor Building Equipment Hatch Reinforcing Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-252 (Page 1 of 1)

(22 OCT 2001)

Figure 3-252. Dome And Ring Girder Reinforcing Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-253 (Page 1 of 1)

(22 OCT 2001)

Figure 3-253. Dome And Ring Girder Reinforcing Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-254 (Page 1 of 1)

(22 OCT 2001)

Figure 3-254. Dome And Ring Girder Reinforcing

(

(

(

IXl1£ ANO RJN REINFORCING G GIRDER CATAWBA NUC LEAR STATION Figure 3.B.1-12

Catawba Nuclear Station UFSAR Figure 3-255 (Page 1 of 1)

(22 OCT 2001)

Figure 3-255. Equipment Hatch Model

(

(

RE.ACTOR BUILOINC SHELL EQUIPMENT HATCH M)O[L CATAWBA MJCLEAR ST,.TION Figure 3.8.1-13

Catawba Nuclear Station UFSAR Figure 3-256 (Page 1 of 1)

(22 OCT 2001)

Figure 3-256. K-Shell Model For Reactor Building Analysis Segrnen+ in Main

'95311----.-+~

Fb~*

fur+m 185311 --'-1,..r/

l7S1 11 _.....,,.__---f-1731' H,80 11 --I-+-+--

571.o" 528

480 11 4811 011 Par+ Y t of R. S. Wo.ll Part.I[

Pa.rtm

--+-H--

Part Il Par+ I A K - She.I I cannot be a clos.ed shell. Therefore a 2°Siegmen+

was left out. When this model Is rotated 3"'0'° there is a

73. 851 11 diameter hole ln the dome. The edge of this hole.

hQ-S. r.l s.prin.9 support <111 around to oppr-oiimote the segment of the dome omitted.


"'- El. (.39+3 t af Dorne l?odiu.s t of Reactor Bi;ilding ~ C.en+er of Rel/olution of K-Shell Mode.I

Catawba Nuclear Station UFSAR Figure 3-257 (Page 1 of 1)

(22 OCT 2001)

Figure 3-257. Axis Orientation For Reactor Building Analysis 1¢ e

Qe

Catawba Nuclear Station UFSAR Figure 3-258 (Page 1 of 1)

(22 OCT 2001)

Figure 3-258. Reactor Building Shell And Crane Wall (Reinforcement Details)

SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-259 (Page 1 of 1)

(22 OCT 2001)

Figure 3-259. Containment Geometry 0 "'

\\0

.. ~

~ -

=g

-<J N

~

I.I")

~

  • ~
  • ~

. '3

~

"<l

(',I "rl\\

0 *i

  • II)

OJ I")

"-t' rt)

EL. 7~1 J

1380"


4-...:..=-:=--=-------.....

0.25TH 1K

--L 2s2 J VERTICAL CYLINDER I

EL.564+5 I.OfH'K EL sso**o" FLAT LINER PLATE EL.ca 1 '.. 4 78"

Catawba Nuclear Station UFSAR Figure 3-260 (Page 1 of 1)

(22 OCT 2001)

Figure 3-260. Containment Personnel And Equipment Hatch Typical Details Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-261 (Page 1 of 1)

(22 OCT 2001)

Figure 3-261. Containment Mechanical And Electrical Penetrations Typical Details TYPlc..-.t.. C.'.1...)

,£',iETRATION

(

(

'"'-~'

,,,J:,,:~"'-'

T.l~.w,;;_t; 11 '.*

~I.-., t,,_i.

gj:'c'*

<<<:,JI-"'),

c.....s.ro, "dHt...:,

TV?IO.L -OW JO<:-;,,i;.

PU>-,f, C..:.ll"<rl)y l

INSTRlJM!;,NTA1a.. Pl::"-fTR.<.Tl:ll;i C<M"""41'N"T-_f WJ L __ _.;__L,u_

--+---+-

I

,.T.,

CONTAINMENT MECHANICAL AND ELECTRICAL PENETRATIONS TYPICAL DETAILS CATAWBA NUCLEAR STATION Figure 3.8.2-3

Catawba Nuclear Station UFSAR Figure 3-262 (Page 1 of 1)

(22 OCT 2001)

Figure 3-262. Containment Vessel And Cylinder Plate Layout And Penetration Location Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-263 (Page 1 of 1)

(22 OCT 2001)

Figure 3-263. Containment Vessel And Cylinder Plate Layout And Penetration Location Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-264 (Page 1 of 1)

(24 OCT 2004)

Figure 3-264. Containment Vessel Penetration Details SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-265 (Page 1 of 1)

(22 OCT 2001)

Figure 3-265. Containment Vessel Base Linear Plate Embedded Items Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-266 (Page 1 of 1)

(22 OCT 2001)

Figure 3-266. Containment Vessel Base Linear Plate Test Channel Layout Security-Related,Withhold under 10 CFR 2.390

Catawba Nuclear Station UFSAR Figure 3-267 (Page 1 of 1)

(22 OCT 2001)

Figure 3-267. Containment Vessel Model For KSHEL Analysis

~I I

'l*"t t--

\\'t i i I

i L

R CATAWBA CONTAINMENT 11 KSHEL II MODEL

@)

G) n.0 l-0

    • t Z COORC.

--140~"'

-12115 11

~--11,;9*

--1049"

~-929'

-- 909"

-~6'SI"

,M--ft-383" Iv~- 2e1*

~1--149" 0./'

157' o*

ELEV, 6M',I" 64'9'*5*

639\\~"

629',5" 619*... ~*

COil',tl" ffl'*:!!ilil

!9!1*t,*

58t+ll 11

$7:3'.-!5...

~:s::g:

!5!5-41tlO*

i!52 1tO..

Catawba Nuclear Station UFSAR Figure 3-268 (Page 1 of 1)

(22 OCT 2001)

Figure 3-268. Containment Vessel Model For Stardyne Localized Analysis

~

X

'(

Catawba Nuclear Station UFSAR Figure 3-269 (Page 1 of 1)

(22 OCT 2001)

Figure 3-269. Containment Vessel Model For Wilson-Ghosh Analysis 16 spcs. E 5°:1:.

R= 690" r.,,, of Symmetry R=690" r

CATAWBA CONTAINMENT VESSEL WILSON - GHOSH MODEL i!-COORD.

ELEV.

'\\c." t (in) 1405 669+1 34"1\\i_

1285 659+1 1169 649-1-5 1049 639+5 929 629+5 809 619 +5 689 609+5 569 599+5 497 593+5 383 583-+-II 257 573+5 i~

137 563 +5

~

34 554...-10 0

552+0

Catawba Nuclear Station UFSAR Figure 3-270 (Page 1 of 1)

(22 OCT 2001)

Figure 3-270. TMD Compartment Pressure Transients - Ice Condenser Region 8 "'

(D 0.,. -

N N "

ci 0

~

COMPRRTMENT 40

( ICE CotffNSER LCMER PLBrn f{G!ON)

HOT LEG BREi'IKS L 2 N ID 3

',ESTINGHlJJSE 1979 DATA l!l HL I 6 HL 2

+ HL 3

'-+------,--------,-----,-----r---~~----,-----r----~---~

  • .ODO 0.276 0.556 0.633
1. 111 1.389 I. 667 l.914 2.222 2.500 TI ME (SEC)

Catawba Nuclear Station UFSAR Figure 3-271 (Page 1 of 1)

(22 OCT 2001)

Figure 3-271. TMD Compartment Pressure Transients - Ice Condenser Region N

c-.

0 CClMPRRTMENT 40 t ICE COIWlSER LO/ER PLENIJ', REGION)

HOT LEG B~ '4, 5 /\\Nil 6

\\IESTlNGHOUSE 1979 MTA x lil 4

~ HL 5

'I' KL 6

,_,___ __ -~----------,------.----.......-------,-----,------,

0.000 0.2/B

o. 556 0.833 Lill 1.389 I. 667 1.941 2.222 2.500 TIME (~ED

Catawba Nuclear Station UFSAR Figure 3-272 (Page 1 of 1)

(22 OCT 2001)

Figure 3-272. TMD Compartment Pressure Transients - Ice Condenser Region

ll C...

ca ui CClMPRRTMENT 40 (ICE cctIDENSrn LO,JER PLENlJ'1 P.ECIONl C(l.] l.EG BIIIIKS 1, 2 Nil 3

\\/ESTINGHWSE 1979 DAT,~

ii
CL I z CL 2 y

CL 3

-*...-----,-----,------.----------.----~------~--~

0.000 0.278 0.556 a.833 I. Ill 1.389 1.667 1.944 2.222

2. 500 TI ME <s::.o

Catawba Nuclear Station UFSAR Figure 3-273 (Page 1 of 1)

(22 OCT 2001)

Figure 3-273. TMD Compartment Pressure Transients - Ice Condenser Region

!{:

w~

O::m

=:J en en"'

w~

0::...:

Q_

m N

N 0

0 C

Ill COMPARTMENT 40 (ICE CONDErt;ER L.a:H PWIIJi REG l CW CQD IIG Br.EAKS 4, 5 AND 5 irnrnGnJSE 1979 Il!\\TA

. CL i 111 CL 5 x Cl 6

'+----.--------,--------~-----,-----.-----.------,r-----.------,

0.000 0.276 0.556 D.833 Lill 1.389 1.667 1.94*

2.222 2.500 TIME (SEO

Catawba Nuclear Station UFSAR Figure 3-274 (Page 1 of 1)

(22 OCT 2001)

Figure 3-274. Fourier Series Representation Of Transient Pressures L.t\\

V, 0..

0

~

LU er::

)

Vl v,-

1.1.J IX 0--

I.I\\

0 0

0 0.00 L.t\\

0

~

V, Q. -

\\.LJ c:::

i V,

Vl L.t\\

\\.LJ er::

0..

\\

0 0.

0 0.00

<I')

Q.

' \\

w er::

=>

\\

Vl

\\

U1 1.1.J I.I'\\

0:::

0..

0 0

0 0.00 45.00 90.00 90.00

+ COMPARTMENT PRESSURE

  • FOURIER REPRESENTATION LEVEL 2 TIMEa::0,1 SEC

.00 180.00 225,00 AZIMUTH(DEGREES}

LEVEL2 TIME=0,2 SEC 135.00 180.00 225.00 AZIMUTH(DEGREES)

LEVEL2 TIME=O. 4 SEC

/

/

I 135,00 180,00 225.00 AZIMUTH(DEGREES)

I I

360.00 270.00 3 5.00 360.00

/

/

I '

270.00 315.00 360.00

Catawba Nuclear Station UFSAR Figure 3-275 (Page 1 of 1)

(22 OCT 2001)

Figure 3-275. Containment Vessel Model For BOSOR4 Stability Analysis CATAWBA CONTAINMENT BOSOR 4 MODEL EL 611'*1"

---~-iSEG 8 5.ll22*

  • I 4

'~ *AXIi QF STMMETRT "M'ICAL P

MENT-----,

DISCl!i:TE:

RING DETAIL I RING STIFFENER z

SEG 7

,.,gf--

EL. 639'*~*

SEG 6

  • -~T~s I

,- SEE DETAIL I SEG !5

/ -./

17 PTS

/

\\

EL. 619"*;*

I

\\ -:::~ ~IPME:!!_T -~TCH Z*72\\' l I

SEG 4 22 P1'S I

l* 497"__,

SEG 3 +

SEG 2 13 PTS SEG I 21PTS

' I El. !599'*!,*

EL.~,**~"

EL ~83'*_11"_

EL. 5n',5" EL. !!54"* 10"

[_L. !!1521-1-0*

J.f.

Catawba Nuclear Station UFSAR Figure 3-276 (Page 1 of 1)

(22 OCT 2001)

Figure 3-276. Localized Nastran Model For Stability Analysis

\\u.

I

,1~ *'i

Catawba Nuclear Station UFSAR Figure 3-277 (Page 1 of 1)

(22 OCT 2001)

Figure 3-277. Containment Vessel Model For Marc Ultimate Capacity Analysis f--

\\'t

~MIi OF S'tMlilCT""

CATAWBA CONTAINMENT AXISYMMETRIC MODEL Ill 16 IT,.~

20 17

~

~,

21.

1B ii

@ *~

~.. "

~t ---@

.. ~

  • o 44 31
    • ~-

~~. :~~

l!l!o 41:

e,

@).. :~

61 q

-~.

(.,) !I :;~

6

@)

'"~

Z!.,..

77 60 (M) '" ~

66

~

1g a l?i 12

@)

~

11 911,J 101 78 (e,)

10~

106, IQ'
  • O 84 II 8~

(19)

"6@

l*ri "'~

111 91

Catawba Nuclear Station UFSAR Figure 3-278 (Page 1 of 1)

(21 OCT 2010)

Figure 3-278. Reactor Building Pressure Seals And Gaskets PJ?F:SSI.Rt'. DooR

~

~~al']E 2-RE*'D

,~t t*"'

-~

DWO.t<IO.CN-FSAR-FIG.3-278 4

Catawba Nuclear Station UFSAR Figure 3-279 (Page 1 of 1)

(15 NOV 2007)

Figure 3-279. Reactor Building Pressure Seals And Gaskets I-<,*

r~

I.

i I

I

__J 5°s's"(r;.t,. A l'E 2.1<1r(c...t..a) 1;

  • ~

1i ll

  • ~

1~g sr

~:

I H

i.

!ii~

it~ ~~

t ct JI,

,~r~

~

i ii ! /

\\~

Ii 1f II

_P I

Catawba Nuclear Station UFSAR Figure 3-280 (Page 1 of 1)

(22 OCT 2001)

Figure 3-280. Catawba Operating Floor Elastic Model

\\

I ii

  • I
  • ii * * * !

I I

I *

  • I ii

~

~

i!i

~

  • I I

M

  • I

~

I

~

~

~

11

~

Ii ii Ii ii I

I a

  • a a

a I

~ *

  • I i

I I

I a

iii

~

Ii ii

~

M I

K G

E I *

~

B

~

I I

I I

I

(

~

~

ij

~ g

(

Catawba Nuclear Station UFSAR Figure 3-281 (Page 1 of 1)

(22 OCT 2001)

Figure 3-281. Catawba Operating Floor Element Model

(

(

CATAWBA OPERATING FLOOR ELEMENT Jll)DEL CATAWBA. NJOLEAA STATION Figure 3.8.3-6

Catawba Nuclear Station UFSAR Figure 3-282 (Page 1 of 1)

(22 OCT 2001)

Figure 3-282. Fixed End Supports CA~E':

Fi,ctp E.t.Jc:, ~uPpclt r!>

~~£.LJDL. t 4~1~tJ 2>*.5 J/J -

E.t...A.r:- : ~£GT A.-A

~

,/

~

-+-

ID *

'+

'Y. "'

D I'

_\\/

~

7.

uJ *UJ I

<J

£ -U>.

- 311)

I I

I I

0.0 0.2

0. 4
0. 6 0.8
1. 0 (FRACTION OF SPAN)

DUKE POWER COMPANY CATAWBA NUCL EAR STAT[ON F I XED ENO SUPPORTS CHAPTER 3 TABLES & FIGURES OESI QNEA~

llJllE 11~; *~IIN~.

OOJCi, Aat;N;(D F"!'.R 2011 f~ ~T~ UTtCU)a.Tt tt*l2*1!

IRIMl~

OATE 11-1&-IJ,.!_ JN"..F'.

QttUf(lCt lllllY 0AT£J.1:J.!::f.J.IIPPA. ""' 8ARIIE11 OM£~

ERN!

V1 NO.

REV ISIONS OATE CHKD OATE APPR OATE CJll!l """ ""* DWO. NO.

CN-FSAR-FIO. 3 - 282 I r::~-

INSP ECTED

Catawba Nuclear Station UFSAR Figure 3-283 (Page 1 of 1)

(22 OCT 2001)

Figure 3-283. Pinned End Supports

~

~

4-

~D 4-ID y,

'-.J t-()

I *ID

~

2 -~

-,o

().()

ERN: CN00 w

C.A~~! PuJN6.D E'JJo -SuPPc,SZ.'1'"-5

--- ~-r~u PL-: ~e:c..-,o,....".3.. 3 e: L.A-6 : '6et:-'T"ll>N A-A

,-------~-..,,..,,,.?

o.i D.4 IJ.CJ, 1).1, ORIO. h tLlAElnA 2m1 rw *re fFff.tT.C1111t 1e-u *1 l,D (FRACTION OF SPAN)

DUKE POI/ER CCM'ANY CATAWBA NUCLEAR STATION PINNED ENO SUPPORTS CHAPTER 3 TABLES & FIGURES

<<'Sl~OllrE.!.!:.lrni'II? *.

CR~O'TE!.l:Jl:f.Ll/11?, _

NO.

RE":VISIONS wc~m~~fE:J.1:JZ:IJ.IIHIII.~

ORN lnAra;ln<<*l*11ri::IAWAl0Ari.:JctYi~ I Mc. I,<e1e.j OWG, NO, CN-FSAR-F[G. 3-283 ttl'!.Pl:Crt:O

~,

""'T".il::tll AE:'I, 0

Catawba Nuclear Station UFSAR Figure 3-284 (Page 1 of 1)

(22 OCT 2001)

Figure 3-284. Fixed End Supports r

tl

~

~

(\\)

Q.

~

'J

~~

\\fl

('-I a

~

'I 2

I ltl I

I 0

I Id

/Ill)

)(

ll

- I -

U\\

I

.,g I

t

\\)

,;\\-

('-I

() -

'ill

~

'¢ C'IJ J

~

t\\

9 C

q

\\

( +t/+J-~) 1N31r4Q~

Catawba Nuclear Station UFSAR Figure 3-285 (Page 1 of 1)

(22 OCT 2001)

Figure 3-285. Pinned End Supports

~

6 N

\\

~

t"

~

/

I tl)

/

\\J)

C\\I,

/

2t0

/

0

/

<l

/

J

--:i

/

~S)

/

<)

fi \\flt N

ul

'2

\\Jl

")

    • \\()

~

_J Q a*

":l '(\\

\\>>

~1

~

ill

Catawba Nuclear Station UFSAR Figure 3-286 (Page 1 of 1)

(17 APR 2012)

Figure 3-286. Calculation Of Safety-Related Masonry Walls I

I a

!..--,,--:::::c~~.:.Tt0ucru*L I

I

~c )SZSc'"""'"""""

1,,,s1anrn CALCULATEHORIZONALFLEXURALSTRENGTH fo

  • Ulllo
  • 1.41Ul* l* 11"1I Cllllh T*ll 11 c:c****Hn IIICI ~-,....... c'"'"*

ITOIIITH Cl'.,,,*1. il* -* 11~1. *-LY Tl* *LICO ITIILf Hllil ~

  • II,11cC1S,ol* III ASSMEANA O\\IAAFSIRFSS*5000PSJ(EOBIENSJONI

+* 1-'-f'* 1

.".Ta l.!176,n2,!ollH0 P5H

~

HQRJlQNTAI MQMfNT(APA[jTYQF BIOCKWAII

  • ~EA ]NIBS Ge C I eif SPOCIMO PF YfBUCA 516 SifF MfMRFRS FROM REEPENSE SPECTRO l'ILE CN-1139.01*231. n+: OCCELEROTJONS AS FOLJ.OWS. SH!i..L BE USEO.

uo mo,.m moa,u* * *,fu,,, * *'"'

WALLS BETVEEN EL. 56~'& 517"* 1f11.u, *.Blg WALL5BETVEE*EL. 177'll.. "*f"*llol* l.~g WALL5BETVEE*EL. * <'l Ill"* f".111

  • 1.15~

tfilill :~~N!T~:~;~~ ~~:E:N~*:;:;.~INENT~~N~~~T~~~IO*

tJ= THE VOLL VllJLO NOT OCCUR[ OT n+: TIME OF MOXJMLJ<

~CELERIHmN. HOWEVER. >OR SIMPLICITY. WESH/i..LUTILIZE THEr-llX"OCCELEROTION5ABIJVE.U1t_ESSRESULTSBECOME MOSS OF BL.aCK.

VT "'.BLOC>'.

  • <115~ LB/FT~<B/lZKB/12].

~~II X ~CC~LUUI*I, -~ l*-lC. ~*ct

!ICLH*

  • THI W"-L
  • 111 ~Ill X 10*1ca~L IFWEO!l!lJI-EBLOCKWIUffiPINM::00TIHE5lRL.CIUFIALSTEEL MEMBERS, MO~IMLJ< Mi1<ENT Will. IIE DEl'EUlPEO.

-*-1}-1 I OW!l,MD, CN-FSA~FIG.3-2BS 1~;**

STRUCTURAL STEEL MEMBER DESIGN TABLEC LOADS ON VERTICAL STEEL F[JSFLEXUF!E *ESIDN,ASSUMEPINNEaEN*SATTHEFL*[Ja!N* CEILIN*.

r-llX.SPANF[Ja5TEELMEMBER51519"--ll.UNCllHR*LCOMPLEXAF!EAI

,-f-T*9.sw MAX.SPACING *FVERT.MEMBERS*153"*12'9"F*RMOMENTOESIGN

' 12 *,,msa.VE ms THESPANATEACHELEVATl*N* 5EETABLEB SIZE THE VERTICN.STEELMEMBERSF[Ja THE ABD\\IE LOOIJS WITHC~SmEMTION INTHE *EPTH *FTfEMEMBERSS* THATTHEBL*C<SWILLF!ESTSECUF!ELY BETWEENTHEFLArt;E5.SEETAIII..ECF*RLOA*5ATEOCHELEVATION.

MAX.SPANIHORIZONTAUFORBLOCKWALLS l"'*""'"""°"""'alM' I

M-IX.5PANBET\\IEEN560'l5/7'*lll'-ll M-IX.SPO*BET\\IEENF.f17'l094"*8"-rn*

.,. seo, "'"" ""' Sll'a a"'

CHECK THECi.,PllESSI\\IE STF!ESSOEVELOPEOIN THEC~CRETE ]FH+:

STEEL RE~HES 51l~II! PSI STRESS LE'IEL*

~'.~.;:*:*I 1111,n XI**

,* II* lJII...W.

.-.r-c-.;,.b,.d*l3B0L05 SOLVE FOR lo*~

  • ~,!,I'll I<. 1325.,.15]

312 PSIISFIIR BELllll lfE N.LO\\MBLE COMPRESSIVE STRESS

  • F BL* CK UNITS THEREF*RE *.K.

2 RELH!ED FDR 1~\\2 FSIIR LFll\\TE EFFECT.DATE 1-8-\\1 loMC 1:;I>

POii 7 18 WEH 7 19 -W-

-II-

-\\I-IIU<EENERGY CATAWBA NUCLEAR STATION CALCULATION OF SAFETY-RELATE* MAS*NRYi/ALLS CHAPTER 3 TABLES ~ FIGURES 1

!ELH5EDFDR1111l9F611RlFll\\TEEFFECT. *ATE4-l8-!9 VOCI~.*'

TLC:..= GN(li<.**

W II-

\\I-rr,am1..

O,JEll-!Ht[N!P.

ll>TE ORIGREL£!5ED FDR 1111ll FSIIR LFll\\TE EFFECT. *ATE l!-11-~

i=~:~==~::;=

111N *ATE CHK* DATE '1'1'11 ll\\TEJNffi,eo70WG. NO.

CN FSAR F!G.3 286 I ROV.

Catawba Nuclear Station UFSAR Figure 3-287 (Page 1 of 1)

(22 OCT 2001)

Figure 3-287. Reactor Coolant Loop Supports System Dynamic Structural Model RESTRAINT DUE TO PRIMARY RESTRAINT DUF TO PRIMARY SHIELD WALL XG YG ZG RESTRAINT RCL GLOBAL COORDINATE SYSTEM STEAM GENERATOR LOWER SUPPORT STEAM GENERATOR UPPER SUPPORT CROSSO~ER LEG RESTRAINT REACTOR COOLANT PUMP REACTOR COOLANT PUMP SUPPORT

Catawba Nuclear Station UFSAR Figure 3-288 (Page 1 of 1)

(22 OCT 2001)

Figure 3-288. Through-Wall Thermal Gradients X

~

TA(~

AT2I ( t)

G._

I

~

~.t.T 1 (t)

ACTUAL 7

PIPE WALL TH I CKNESS

_j_

T

Catawba Nuclear Station UFSAR Figure 3-289 (Page 1 of 1)

(22 OCT 2001)

Figure 3-289. Reactor Internals Mathematical Model For DARI Variables SIMPLIFIED RP\\I AND LOOf>

SUPPORT REPRESENTA-TION CROM UPPER CORE PLATE0 14 0

CGOF LOWER HEAD NOTE: NOOE 1 IS COUPLED TO NODE 2 IN WO&TAS t,J\\/'-.J\\- e t--'\\,/\\/-10 IJV'-,,

GUIDI: TUIIE AND3HU FUEL ELfMSllil

Catawba Nuclear Station UFSAR Figure 3-290 (Page 1 of 1)

(22 OCT 2001)

Figure 3-290. Reactor Internals Mathematical Model For WOSTAS Variables SUPPORT NOTE: NOOE 2 IS THE REACTOR VESSEL SUPPORT NODE WHICH IS COUPLED TO NODE 1 IN DARl-2 25

@ r 10 se---------0---------( g

+ TWO-WAY SPRING-OAMPE~

.¢,.

ONE-WAY SPRING*SIIIUBBER I

t-.- PRELOAD ONE-WAY SPRING ONE-WAY SPRING-SNUBBER WITH INITIAL GAP 4

SLIDING ELEMENTn 9

ELEMENT NUMBERED n NODE m WITH MASS REPRESENTING INTEANAL COMPONENT NOOE m WITHOUT MASS ELEMENT WITHOUT STIFFNESS

Catawba Nuclear Station UFSAR Figure 3-291 (Page 1 of 1)

(22 OCT 2001)

Figure 3-291. Pre And Post Hot Functional Examination Points For Internals And Integrity

  • / I I

Catawba Nuclear Station UFSAR Figure 3-292 (Page 1 of 1)

(22 OCT 2001)

Figure 3-292. Auxiliary Building Auxiliary Feedwater System

(

(

(

Catawba Nuclear Station UFSAR Figure 3-293 (Page 1 of 1)

(22 OCT 2001)

Figure 3-293. Full Length Control Rod Drive Mechanism 1.'"";:,

~.:."I\\

I

~.-*

ROD TRAVEL HOUSING ---..J.

OPERATING COIL STACK ASSEMBLY

,--..~

PRESSURE HOUSING i

i DISCONNECT ROD --.

Catawba Nuclear Station UFSAR Figure 3-294 (Page 1 of 1)

(22 OCT 2001)

Figure 3-294. Full Length Control Rod Drive Mechanism Schematic

~r DR I VE ROD ASSEMBLY

___ ROD TRAVEL HOUSING LATCH HOUSING 0 RING FLUX RI NG LOCK WI RE COIL STACK ASSEMBlV LIFT POLE LIFT COIL (C)

SHIM LIFT RETURN SPRING FLUX RING LOCK WIRE MOVABLE GRIPPER POLE

_MG COIL (8)

SH IM

_MO~ABLE GRIPPER SPRING LOCK PLUNGER MOVABLE LATCH

~Hil:Jl.-t+-\\-H~~ LATCH Pl N LATCH ARM LINK PIN LATCH L 1 Nk LINK PIM LOCK WIRE SUPPORT TUBE MO~ABLE LATCH


.STATIONARY GRIPPER POLE fLU X Rl NG GUIDE TUBE SHIM

-SG COIL (A)

---.....__,__ STAT I OMARY GRt PPER SPRING

---... PLUNGER HALF FLUX RING LOCK WIRE SHIM

~~LIFT RETURN SPRING

,~~SPRING RETAI MER

~ LATCH PIH

'\\.'-.-LOCK PLUNGER STATIONARY LATCH LINK PIN LATCH LINK

"'"' LIIIK PIN

"'"' SUPPORT TUBE ST AT IONARY LATCH

~

LATCH STOP

Catawba Nuclear Station UFSAR Figure 3-295 (Page 1 of 1)

(22 OCT 2001)

Figure 3-295. Nominal Latch Clearance At Minimum And Maximum Temperature B

t,.

~

BEFORE LOAD TRANSFER SG LI Fr COIL OFF LI FT COIL ON LI FT COi L OFF LI FT COIL OH A

15.61+0 16.265 A

15.725 16.375 AT 70° B

© 15.625 0.015 16.250 o.o,s AT 650° B

G)

15. 679 0.0116 16.387 0.068 B

A AFTER LOAD TRANSFER LIFT COIL OF-F LI FT COIL ON L I FT CO I L OFF LI FT COIL OH A

15.625 16.258 A

15.679 16.387 AT 70° B

15. 578 6.203 AT 650° B

J s.. 61+/

J6.Wf

© 0.0117 0.01+7 CD 0.038 0.016

Catawba Nuclear Station UFSAR Figure 3-296 (Page 1 of 1)

(22 OCT 2001)

Figure 3-296. Control Rod Drive Mechanism Latch Clearance Thermal Effect 0.080 Cl) 0.070 w

z::

u z:: -

0.060 UJ 0

0 a::: 0.050 c::,

w a:::: 0,0q.O 0

C.

z

<r

(/') 0.030 UJ

c u I-

_J 0.020 UJ u

z:

<(

0::: 0.010

<(

UJ

_J c.:,

0.000 0

LIFT COIL OFF}

/

MG CLEARANCE AFTER

/

LIFT COIL OM LOAD TRANSFER

/

/

//

/

/

/

/ --

/

~--~LI FT COIL ON

}

SG CLEARANCE BEFORE 0

LOAD TRANSFER LI FT COIL M

100 200 300 400 TEMPERATURE (°F) 500

/

600 700

Catawba Nuclear Station UFSAR Figure 3-297 (Page 1 of 1)

(22 OCT 2001)

Figure 3-297. Lower Core Support Assembly (Core Barrel Assembly)

FLANGE --.I IJPPER CORE PUrE 6U I DE PIN CORE BARREL FUEL ASSEMBLY GUIDE Pill E

UTRON SHIELD PANEL UPPER CORE BARREL LOWER CORE BARREL THE O.D. AND I.D. ARE CONTINUOUS BETWEEN UPPER MID LOWER BARREL.

TIIERE IS NO GIRTH WELD REDUCTION ENERGY ABSORBER ASSEMBLY OFF-SET I NSTRIMNTA T 11>>1 COLIMI SECONDARY CORE SUPPORT BUTT TYPE COLIMI I HSTRUMENTA TI ON 6111 DE COLIN!

(CRUCIFORM)

UPPER TIE Pl.ATE RADIAL SUP~T

Catawba Nuclear Station UFSAR Figure 3-298 (Page 1 of 1)

(22 OCT 2001)

Figure 3-298. Upper Core Support Structure

Catawba Nuclear Station UFSAR Figure 3-299 (Page 1 of 1)

(22 OCT 2001)

Figure 3-299. Plan View Of Upper Core Support Structure SUPPORT COLUMNS HEAD AHO 'JESSEL ALIGNMENT Pl N LOCATION GUIDE TUBE ASS£MBLV LOCATIOHS

Catawba Nuclear Station UFSAR Figure 3-300 (Page 1 of 1)

(22 OCT 2001)

Figure 3-300. Direct Generation Interactive Scheme Flow Chart Compuce *Cw) from&(~)

Using Equation. (10)

Compute a(~)1 from *(~)

Using Equation (7)

OK i<~) is consistent with R(w)

NO

Catawba Nuclear Station UFSAR Figure 3-301 (Page 1 of 1)

(22 OCT 2001)

Figure 3-301. Reactor Coolant Loop Model for Steam Generator Replacement r

131 1e f

11 I

LO I

I e

7j I

6 I

L_____;o_

r l

!tt A

A u

~

0:1 E

D C

lil:IIEHAL ARIRII\\Nlii:H[NT

"'I la 1..

11 z

,5

~

Catawba Nuclear Station UFSAR Figure 3-302 (Page 1 of 1)

(22 OCT 2001)

Figure 3-302. Reactor Coolant Loop Model for Steam Generator Replacement l:

I.]

iiii im iiii N..

Catawba Nuclear Station UFSAR Figure 3-303 (Page 1 of 1)

(22 OCT 2001)

Figure 3-303. Reactor Coolant Loop Model for Steam Generator Replacement m

D..

t.:I L.

0 w

Ill u

Catawba Nuclear Station UFSAR Figure 3-304 (Page 1 of 1)

(22 OCT 2001)

Figure 3-304. Reactor Coolant Loop Model for Steam Generator Replacement

Catawba Nuclear Station UFSAR Figure 3-305 (Page 1 of 1)

(22 OCT 2001)

Figure 3-305. Loop Layout and Global Coordinates REACTOR COOLANT

?UMP

~EAC"~

COOL:.r1

~UII?

Catawba Nuclear Station UFSAR Figure 3-306 (Page 1 of 1)

(22 OCT 2001)

Figure 3-306. RPV Shell Submodel 25 TVPtCAL SUPPORTE!I NOZZLE (4>

17

~PPER HEAD C.G.

INTERNALS SUPPORT LEDG£ TYPICALLY UNS~PPORTED NOULE (4)

[ K]

STIFFlltSS MATRIX 19

-H-fLf-+I'-

LINEAi! IMPACT I

l()lj[R RADTAL

-- su,,oa1 LOWER 001'1£ C.G.

Catawba Nuclear Station UFSAR Figure 3-307 (Page 1 of 1)

(22 OCT 2001)

Figure 3-307. Core Barrel Submodel a

OENQTES NOOU ON RPY sKm SUBMODEL Typical raprasentallon of the oonowm: impact elemrlnls between the fuel auembly grlcll am:! the core bal"T

-#-1Ci,,.t,t-CONCENT!IJC IMPACT

.....-+-I~ I-#- L lNEAR IMPACT

_cou SARtm Fl.ANGE RPV NOZZLE

  • CEtlTERLIIIE UPPER CORE PLATE CORE C,G.

LOIIER CORE

-PLATE LIIIIER RADIAL SUPPORT.

Catawba Nuclear Station UFSAR Figure 3-308 (Page 1 of 1)

(22 OCT 2001)

Figure 3-308. Reactor Internals Submodel

,-, DENOTES HODES ON L.1 RPV SHELL SUl!HODEL 0 DENOTES NOD£S OM CORE BARREL SUIIIIODEL IS UPP!:R SUPPORT PLATE SUPPORT COLUMNS 1 ANO GUIDE TUBES

  • tfihliff-Ll~EAR IMPACT 11 L

9 \\ IIOTTflfll FIJEL L

NOZZLE

[!ll)-f1'-918 UPPER CORE

-Pvm CORt

-c.G.

LOWER CORE PLATE

Catawba Nuclear Station UFSAR Figure 3-309 (Page 1 of 1)

(22 OCT 2001)

Figure 3-309. Hydrodynamic Masses in Vessel/Barrel Downcomer Annulus 0 -,N:M* r,ium-be-r"

'LJ

-H)'<>r<>V)l>larnioMonl:lem"'11

Catawba Nuclear Station UFSAR Figure 3-310 (Page 1 of 1)

(22 OCT 2001)

Figure 3-310. Response Acceleration Spectra d) 00 RESPONSE ACCELERATION, SA, !NG o.oe 0.1s o.2q 0.32 o qo o,qa z

U) 0,,.

0 0

0 N

0 rTJ n_

GI zo 00 U)

N 0

0

<.n 0

0 0

0 0

\\

/,

)

I I

I If

~

....... ---~

~-a

_...,"'"::::J

~ ---~

l:t-

-=---* -

I~

-~-

~

£:::

--->7

~

I?

I I

I I

I I

rn.

en Cl>

C C:

r-r-

en Cl>

~

~

x
x

-t

-i

x i

en en

-t

-t rn JI.

z z

0 S6

.. *