Latest revision as of 18:21, 18 January 2022

Text

1 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3B, Figures - NRC (Redacted
	ML21229A016
Person / Time
Site:	Catawba
Issue date:	10/22/2001
From:	; Duke Energy Carolinas
To:	; Division of Operating Reactor Licensing
	Stone Z
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Catawba Nuclear Station UFSAR Appendix 3B. Figures Appendix 3B. Figures

Figure 3-1. Wind Pressure Distribution On The Reactor Building Catawba Nuclear Station

-0 7 IIS -0 ~

/10 -0 4

.,o

OI 8 <J.4

+ J,o l 1.35 EL JIZ.+3 P*llTS rnz w.m AEII Cpe * - 6 * .3 cos I+ .929 cos 21

411 cos 31 -.Oi COS 48

01~ cas 51

[L.fi'la*_Y _

Q;l cos 6a - 008 CDS lt - If, cos Ila

~.t;93+!_ -II

~L.li89+1i n: -I 11/'\ '._ __1__

\ - . -O'l

\/

)./ " -08

-I*),(_

y

- U

-12

_f J4

4 .::; 8 OB

-0 7 PART 1X ~ART .X 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,

[L. 591

6 - .004 CDS 79 - 013 CDS Ila - 008 cos Be EL.59'.h_6 EL 58!1+1i l li

w. --- --.._ ~I:, /

_,/

/

...~----------..... '-..._

'* r

~lo I

EL 553*6._

n:

I

. ~\\\ 1/

I I

/ /,,. /

El. 54~

Ii I:

L_J LJ L.J I

_J

\

r'Afl; XI PAllT :xJI Cpe * -115 QJe = -1 15 UFSAR Figure 3-1 (Page 1 of 1)

, r:~ e' 'l '<.UPc C(,[F1 IUEMT (22 OCT 2001)

Figure 3-2. Wind Pressure Distribution For Rectangular Structures Catawba Nuclear Station COEFFICIENT (Cpe)

..... . ,- 0 WINO STRUCTURE

~

I I % AUXILIARY N-S 0.9 l-0.:5 -0.4 ~ ... ~.8 *O.B k).3 0.3 I BUILDING E-W 0.9 -0.3 i-0.4 -0.4 0.8 0.8 -0.3 -0.3 I

DOGHOUSE STR. N-S 0.9 0.5 i-0.7 t-0.7 0.6 ~o.6 0.:5 -0.5

,...,~o -----~ l J a NEW FUEL BLDG.

SPENT FUEL E-W N-S 0.9 -0.5 0.6 -0.6 0.9 -0.5 -0.7 -0.7

-0.7 0.7 -0.:5 -0.:1

-0.6 -0.6 f-0.5 -0.5

~ L/- /~- POOL BUILDING E-W 0.9 -0.5 '-0.6 0.6 0.7 -0.7 -0.5 -0.5 I /-

@)

p * (Cpe)fvl f*.002558

~~

( Cpe I (.002558)19:5) 1 (p.1150, Ref. I)

WINO@ ---+---

1 ~

s 23.09(Cpe) ya 95 mph p* psf L :'._J UFSAR Figure 3-2 (Page 1 of 1)

PLAN VIEW (22 OCT 2001)

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

Figure 3-3. Turbine Building Tornado Velocity Distribution

,S1.t*1,

~

,u*,r

.~.

....I-N

a,,

~!

,g:n

.~"Cl 110001

,H tll

,9.Lffl

.., *c,

,u*111

,S.ntl (22 OCT 2001)

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

Figure 3-4. Tornado Wind Loads - Design Velocity Vs. Radius From Center Of Tornado VR I.S =C Radius in F<<JI 1501 LINEAR 360mph 70m

~

- ~ ~

~

(22 OCT 2001)

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

Figure 3-5. Turbine Missile Ejection Zones

(

TURBINE l>'ISSILE EJECTION ZONES CATAWBA J\l.JCLEAR STATION Figure 3.5.1-l (22 OCT 2001)

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

Figure 3-6. Loss Of Reactor Coolant Accident Boundary Limits CASE I OUTGOING LINES WITH MORMALLY CLOSED VALVE

/ REACTOR COO..AN T P I PI NG I

)

NOTE: PRESSURIZER SAFETY VALVE)

ARE INCLUDED UNDER THIS CASE.

CASE D OUTGOING LINES 1111TH '-ORt~AlLY OPEN VALVES NOH: THE REACTOR COOLANT PUMP NO. l SEAL IS ASSUt1EO TO BE EQUl~ALENT ;Q FIRST F41 L CLOSED OR I/AL'¥£ tAIL-AS*IS ULVES _J_*

I I BOUNDARY RESTRJI.INT CASE m INCOMING L1NES NORMALLY WlTH FLOW NO.

NO. 2

...i.

BOUNDARY TEST CONNECTI.ON CASE II INC0~1NG LlHES ~ORMALLY WITHOUT FLOW

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

CASE I: 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, (22 OCT 2001)

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

Figure 3-7. Location Of Postulated Breaks In Main Reactor Coolant Loop REACTOR PRESSURE VESSEL 9 DENOfES BREAK LOCATION STEAM GENERATOR REACTOR PllESSURE VESSEL

(__

(22 OCT 2001)

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

Figure 3-8. Deleted Per 2001 Update (22 OCT 2001)

Figure 3-9. Reactor Coolant Loop Model Catawba Nuclear Station STEAM GENERATOI COLD LEG IESTRAIIH 139 189 STEAM GENEIATOII UPPEI SIJPPOIIT (SGUS)

IOI 179 L, . .RESTRAINT UACTOlt tOOLlNT PUMP

~ \ !:C~l' ROT LEG CROSSOYEI LEG IIESTUINT RESTRAINT (XLVII)

CIOSSOVER LEG RESTUIIIT

( NLRCP) j UFSAR Figure 3-9 (Page 1 of 1)

CflOSSOVER LEG RESTRAINT (llLSG)

(22 OCT 2001)

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

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 and Model - Support Structure 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 ,' .'

IPiping Stress Evaluation! !support Member Evaluation I (22 OCT 2001)

Figure 3-11. Typical Cold Penetration Catawba Nuclear Station 3"-o' 6*-o*

(NOMINAL)

REACTOR BLDG.

WALL PIPE CAP h ...

~ .

TEST CONNECTION

i- *. ~ - 'b._ -_ .... - * . ~.

.: .* ti,;'*_ *'b -. . "'

PROCESS PIPE

~. -~ . . t>.

... '. h

~-;;;.§iiF*'

o,.* .* :"'.. h b D .

b _ , . . A* t. .*

/,

RESTRAINT RING (;,.

~

FLAT HEAD

~----0s

~

~6 .A.:-~ .1,. . * ._ . .__ .* ~. ;,.*

-~-

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

~~ CONTAINMENT VESSEL TYPICAL COLD PENETRA TION UFSAR Figure 3-11 (Page 1 of 1)

(22 OCT 2001)

Figure 3-12. Typical Main Steam And Feedwater Penetration Catawba Nuclear Station I 11 11 13-0 l

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

-CONTAINMENT

....-ANCHOR RING VESSEL

__....- 1 BELLOWS GUARD SHROUD l,\s II S\ \\ ii \\ \I I\ 'I II §\\II I' §\:h:s'rri,l /

-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 UFSAR Figure 3-12 (Page 1 of 1)

REACTOR BLDG

.. *,:: WALL (22 OCT 2001)

TYPICAL MAIN STEAM AND FEEDWATER P[NETr~ATION

Figure 3-13. Typical Hot Penetration Catawba Nuclear Station 12'-o"_

1-- ..,, .;.. ~- o*__ _ 6'-d'

't i

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

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

~ . , WALL , _ D TEST CONNECTION BELLOWS JOINT ~\,

t, . ; * . : .6 . ' d_ .. , : '.. : \ GUARD PIPE

' ; t:. * !i. . ' 6: {V\_

_/,../ PROCESS PIP FLUED HEAD

. *, "' . \

t,;1>=-.* !\ .b:*

** I b . ': "4. '

.. ' .. , *' t,. \".*

,l>- ,,*. j ANCHOO RING -..___ CONTAINMENT VESSEL

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

.'ti.' - . **. t,.'"*. ,._ .*

.d *,. ... "".

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

TYPICAL HOT PENETRATION UFSAR Figure 3-13 (Page 1 of 1)

(22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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

LEGEND

- 0.lign Spectra

- - - - Spectra per Regulatory Guide I. 60 (22 OCT 2001)

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

Figure 3-214. Response Acceleration Spectra

- -- --- R£$UL S FROM /TIME l TEPS IN I A - - RESUL: S FROM rTIME l TEPS INI I

!~ fiJ tll'\ Iv I

",~

l t

~

\ I J GI 0

0 t-

..,,I J

I V

~

~'\

\_

r----.

0 d

0 0.0!5 0.10 0.20 0.!50 PERIOD IN SECONDS 1.00 2.00

--- I'- r---

!5.00 10.00 (22 OCT 2001)

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

Figure 3-215. Response Acceleration Spectra

.c !

cc:

VJ ------- ~ESUL TS FRCPI T 111£ STI PS II I I

J I

-- ~£SUI TS FRO~ T IME ST PS II Ill I I

I J

I~ ~ ~~l \

i I v Ii

~

vv '

I I :I

\, V

~

V C

ci .,.-/

t J '

i l\ \._

'iJ. 05 i

o. 10 I

I I

a.so l.00 2. a*

r--- ~

5.0

10.Ca PERI~O IN SEC~N05 (22 OCT 2001)

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

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

_,I

~

u

..... 3 I-0::

u

-o,-.'l.

(.!)

z:

2 c..

~

c:(.

0 0

0 10 20 30 Frequency (Hz.)

(22 OCT 2001)

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

Figure 3-217. Containment Interior Structure Lumped Mass Model Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-218. Auxiliary Building Elevation Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-219. Exterior Doghouse And UHI Elevation Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-220. Diesel Generator Building Elevation Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

WT 8 N Q).

WT7 G)

WT 6

(]

. WT 5 w

7*

., E El.600.00 l I G)

WT 4 G)

Q)l WT 3

. WT 2 0 s LUMPED MASS MODEL STR.clUW.PFO&(hES,

. :x-AXIS Y-A>aS 2-AXIS M!Mel I UNmi ~

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

~ -6J=EA I

.{Fl'.~ . . . .

OJ X;(1o)

(Ff.i, .

SJEllfl.*

.. M* A (FT.~ . .

. *. -I OJx_ (.1.o) o=r.,

(l,)x(1o)

(Fti,"

1-6 10.33 1$3 tl?f. 563 8l! a>t 1364 EL. 545.83 r I I .. 7~8 10.00 771 346 :m 364 434 742 UFSAR Figure 3-221 (Page 1 of 1)

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 (22 OCT 2001) wt-6 2141 500.~

WT-7 2775 a:noo wr-s* 13EKJ 610.00

.WT-9 1531 EW.00

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

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

EL 549~6 rs-1 HORIZONAL MODE 2~ HORIZONTAL MODE 5.3 r~s (;, - IS. I CPS (22 OCT 2001)

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

Figure 3-223. Reactor Building First And Second Vertical Mode Shapes I II EL. 549+6 EL,. 549+6 I '

1~1 VERTICAL MODE 2ND VERTICAL MODE f1 =-l3.29 CPS ~2 == 19. 4 7 CPS (22 OCT 2001)

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

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

327.48 c::.__ _ __

(22 OCT 2001)

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

Figure 3-225. Reactor Building Meridional Force, N (lb/in), Due To SSE 465.0 4 59. 06 (22 OCT 2001)

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

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

~

9321.6 28880.4 (22 OCT 2001)

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

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

.01 831.3 tO 121 ~ . . - - - - ¥ 3241.Q ..

(22 OCT 2001)

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

Figure 3-228. Reactor Building Hoop Force N o (lb/in) Due To SSE 1402.8 291 t .I 1498. 2 (22 OCT 2001)

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

Figure 3-229. Reactor Building Hoop Moment M O (in-lb/in) Due To SSE IOZ9* 3 2050. P 15~a- .a.

(22 OCT 2001)

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

Figure 3-230. Containment Interior Structure First Four Horizontal Mode Shapes North-South Direction f,

-6_74 MODE I

":.PS MODE 2 r2 ° 20.76 :Ps 43 MODF 34.33 -.PS 4>

r4 =49.6 7 MODE 4

PS (22 OCT 2001)

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

Figure 3-231. Containment Interior Structure First Four Horizontal Mode Shapes East-West Direction (22 OCT 2001)

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

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

I f'1 = 19.10 CPS MODE 2 42 =- 50 .56 CP5 (22 OCT 2001)

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

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

(

Accft&RAT)0,,1 !Uf.i!TIAL fl.l(@i: Di~pL..A,c:,.e.MF,.,;Jf (i='T/~,'1) (lo:., .... '5) (Fe;e.T,.ID"~)

r REACTOO: BUILDING INTERIOR I, STRUCTURE RESPONSE LOADS

NORTH-SOUTH, SSE CATAWBA ffJCLEAA STATION Figure 3.7.2-17 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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

CATRWBR NUCLEAR STATI~N RESPONSE RCCELERRTION SPECTRA, DAMPING= 0.050 Ul REACTOR INTERI

R, N-5 DIAECTIDN. EL. 556+8

"'a I- - - - ,_ - '-- - 7 I I 0

,I (\ {\

I 0 I I,

r-.

I I~ V~ 1\

t:J I

/ V"'

J a:

en V

\ \

~

Cl .

...,o

....cr: I I

/

1/

I f\ I\

\

\/' '.

I V a::

w.,,

...J_

w. /

I ~

)

\\ \

\\-

uo I u I a:

w ~

I v V]O z-oo a..

~ " ....

If')

~I\'-

w a::

a '-

\.:

Cl a

D I'- r--..::s.

i" 9:J. 05 o. 10 0.20 0.50 1.00 2.00 S.00 10,00 PERIOD IN SECONDS (22 OCT 2001)

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

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

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

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

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

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

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

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

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

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

Figure 3-241. Soil Pressure Diagram For Substructure Walls Of Auxiliary Building t.t3KY 79.70 79.70 K/FT. K/f'T.

3.156 KS' 3.156 KSf' STATIC EAllTH PRE'5SUR! STATIC EARTH PRlSSURE

LAT£11AL 51JSMIC PR[SSUR[ + LAT[RAL EARTH P'RC55U RE

- US[D ,o" DESIGN rROM MONONOB[-OKAIIC COEFFICIENT ANALYSIS (22 OCT 2001)

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

Figure 3-242. Multi-Degree Of Freedom System (22 OCT 2001)

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

Figure 3-243. Reactor Building And Containment Structural Outline SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-244. Reactor Building Bottom Radial Bars

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

Figure 3-245. Reactor Building Top Radial Bars t

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(22 OCT 2001)

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

Figure 3-246. Reactor Building Circular Bars (22 OCT 2001)

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

Figure 3-247. Containment Vessel And Equipment Anchorage Details

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

Figure 3-248. Reactor Building Shell Wall Developed Elevation Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-249. Reactor Building Shell Wall Developed Elevation Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-250. Reactor Building Shell Wall Developed Elevation Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-251. Reactor Building Equipment Hatch Reinforcing Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-252. Dome And Ring Girder Reinforcing Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-253. Dome And Ring Girder Reinforcing Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-254. Dome And Ring Girder Reinforcing

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

Figure 3-255. Equipment Hatch Model

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RE.ACTOR BUILOINC SHELL

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EQUIPMENT HATCH M)O[L CATAWBA MJCLEAR ST,.TION Figure 3.8.1-13 (22 OCT 2001)

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

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

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Part.I[ t of Reactor Bi;ilding ~ C.en+er Pa.rtm of Rel/olution of K- Shell Mode.I 480 11 --+-H--

Part Il 4811 011 Par+ I (22 OCT 2001)

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

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

Qe (22 OCT 2001)

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

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

SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 (22 OCT 2001)

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

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

Figure 3-260. Containment Personnel And Equipment Hatch Typical Details Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-261. Containment Mechanical And Electrical Penetrations Typical Details

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CATAWBA NUCLEAR STATION Figure 3.8.2-3 (22 OCT 2001)

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

Figure 3-262. Containment Vessel And Cylinder Plate Layout And Penetration Location Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-263. Containment Vessel And Cylinder Plate Layout And Penetration Location Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-264. Containment Vessel Penetration Details SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 (24 OCT 2004)

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

Figure 3-265. Containment Vessel Base Linear Plate Embedded Items Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-266. Containment Vessel Base Linear Plate Test Channel Layout Security-Related,Withhold under 10 CFR 2.390 (22 OCT 2001)

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

Figure 3-267. Containment Vessel Model For KSHEL Analysis

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

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

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(22 OCT 2001)

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

Figure 3-269. Containment Vessel Model For Wilson-Ghosh Analysis CATAWBA CONTAINMENT VESSEL WILSON - GHOSH MODEL 16 spcs. E 5°:1:. i!-COORD. ELEV.

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257 137 34 573+5 563 +5 554...-10 r 0 552+0 (22 OCT 2001)

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

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

"" COMPRRTMENT 40

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(22 OCT 2001)

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

Figure 3-271. TMD Compartment Pressure Transients - Ice Condenser Region CClMPRRTMENT 40 t ICE COIWlSER LO/ER PLENIJ', REGION) x lil 4 HOT LEG B~ '4, 5 /\Nil 6 ~ HL 5

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

Figure 3-272. TMD Compartment Pressure Transients - Ice Condenser Region CClMPRRTMENT 40 (ICE cctIDENSrn LO,JER PLENlJ'1 P.ECIONl C(l.] l.EG BIIIIKS 1, 2 Nil 3 ;ii: CL I

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

Figure 3-273. TMD Compartment Pressure Transients - Ice Condenser Region COMPARTMENT 40 (ICE CONDErt;ER L.a:H PWIIJi REG lCW CQD IIG Br.EAKS 4, 5 AND 5 :. CL i irnrnGnJSE 1979 Il!\TA 111 CL 5 x Cl 6

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

Figure 3-274. Fourier Series Representation Of Transient Pressures

+ COMPARTMENT PRESSURE

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(22 OCT 2001)

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

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

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(22 OCT 2001)

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

Figure 3-276. Localized Nastran Model For Stability Analysis

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

Figure 3-277. Containment Vessel Model For Marc Ultimate Capacity Analysis CATAWBA CONTAINMENT AXISYMMETRIC MODEL 16 @ IT ,.~

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

Figure 3-278. Reactor Building Pressure Seals And Gaskets DWO.t<IO.CN-FSAR-FIG.3-278 4

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

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

Figure 3-280. Catawba Operating Floor Elastic Model

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

Figure 3-281. Catawba Operating Floor Element Model

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( CATAWBA OPERATING FLOOR ELEMENT Jll)DEL

CATAWBA. NJOLEAA STATION Figure 3.8.3-6 (22 OCT 2001)

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

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

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

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AS FOLJ.OWS. SH!i..L BE USEO.

I TABLEC I

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

! ..--,,--:::::c~~.:.Tt0ucru*L WALLS BETVEEN EL. 56~'& 517"* 1f11.u, * .Blg WALL5BETVEE*EL. 177'll.."*f"*llol* l.~g LOADS ON VERTICAL STEEL I WALL5BETVEE*EL. * <'l Ill"* f".111

1.15~

I 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 F[JSFLEXUF!E *ESIDN,ASSUMEPINNEaEN* SATTHEFL* [Ja!N* CEILIN *.

r-llX.SPANF[Ja5TEELMEMBER51519"--ll.UNCllHR*LCOMPLEXAF!EAI MOSS OF BL.aCK. VT "'.BLOC>'. * <115~ LB/FT~<B/lZKB/12].

~c )SZSc'"""'""""" 1,,,s1anrn

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

!ICLH *

THI W"-L

111 ~Ill X 10*1ca~L

~*ct

,-f-T*9.sw CALCULATEHORIZONALFLEXURALSTRENGTH IFWEO!l!lJI-EBLOCKWIUffiPINM::00TIHE5lRL.CIUFIALSTEEL MEMBERS, MO~IMLJ< Mi1<ENT Will. IIE DEl'EUlPEO. '

-*-1}-1 fo

Ulllo

1.41Ul* l* 11"1I Cllllh T*ll 11 c:c****Hn ITOIIITH Cl'.,,,

IIICI ~-, . . . . . . . c'"'"*

1. il* -* 11~1. * -LY Tl*

LICO ITIILf Hllil ~

II ,11cC1S,ol

III MAX.SPACING *FVERT.MEMBERS*153"*12'9"F *RMOMENTOESIGN SIZE THE VERTICN.STEELMEMBERSF[Ja THE ABD\IE LOOIJS WITHC~SmEMTION INTHE

EPTH

FTfEMEMBERSS* THATTHEBL* C<SWILLF!ESTSECUF!ELY ASSMEANA O\IAAFSIRFSS*5000PSJ(EOBIENSJONI ' 12 * ,,msa.VE ms THESPANATEACHELEVATl* N* 5EETABLEB BETWEENTHEFLArt;E5.SEETAIII..ECF* RLOA*5ATEOCHELEVATION.

MAX.SPANIHORIZONTAUFORBLOCKWALLS l"'*""'"""°"""'alM' M-IX.5PANBET\IEEN560'l5/7'*lll'-ll I

+* 1-'-f'* 1 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 l o * ~

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

~

~,!,I'll I<. 1325.,.15]

IIU<EENERGY CATAWBA NUCLEAR STATION HQRJlQNTAI MQMfNT(APA[jTYQF BIOCKWAII * ~EA ]NIBS 312 PSIISFIIR BELllll lfE N.LO\MBLE COMPRESSIVE STRESS CALCULATION OF

F BL* CK UNITS THEREF* RE * .K.

SAFETY-RELATE MAS NRYi/ALLS*

CHAPTER 3 TABLES ~ FIGURES 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-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.

(17 APR 2012)

Figure 3-287. Reactor Coolant Loop Supports System Dynamic Structural Model Catawba Nuclear Station RESTRAINT DUE TO PRIMARY STEAM GENERATOR STEAM GENERATOR UPPER SUPPORT REACTOR COOLANT PUMP REACTOR COOLANT RESTRAINT DUF TO YG PUMP PRIMARY SHIELD WALL SUPPORT XG ZG RESTRAINT LOWER SUPPORT RCL GLOBAL COORDINATE SYSTEM CROSSO~ER LEG RESTRAINT UFSAR Figure 3-287 (Page 1 of 1)

(22 OCT 2001)

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

Figure 3-288. Through-Wall Thermal Gradients PIPE WALL TH I CKNESS 7 _j_ T ACTUAL

- G._

~.t.T 1 (t)

I

~

TA(~

AT2I ( t)

~

X (22 OCT 2001)

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

Figure 3-289. Reactor Internals Mathematical Model For DARI Variables CROM NOTE: NOOE 1 IS COUPLED TO NODE 2 IN WO&TAS SIMPLIFIED RP\I AND LOOf>

SUPPORT REPRESENTA-TION t,J\/'-.J\- e UPPER CORE PLATE 014 t--'\,/\/-1 0 IJV'- ,,

0 GUIDI: TUIIE AND3HU FUEL ELfMSllil CGOF LOWER HEAD (22 OCT 2001)

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

Figure 3-290. Reactor Internals Mathematical Model For WOSTAS Variables 25 r

SUPPORT NOTE: NOOE 2 IS THE REACTOR VESSEL SUPPORT NODE WHICH IS COUPLED TO NODE 1 IN DARl-2 10 se----- ----0-- ------- ( g 9

+ TWO-WAY SPRING-OAMPE~ ELEMENT NUMBERED n

.¢,. ONE-WAY SPRING*SIIIUBBER NODE m WITH MASS REPRESENTING INTEANAL COMPONENT I

t-.- PRELOAD ONE-WAY SPRING NOOE m WITHOUT MASS ELEMENT WITHOUT STIFFNESS ONE-WAY SPRING-SNUBBER WITH INITIAL GAP 4 SLIDING ELEMENTn (22 OCT 2001)

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

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

I* /

(22 OCT 2001)

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

Figure 3-292. Auxiliary Building Auxiliary Feedwater System

(

(22 OCT 2001)

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

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

~.:."I\ I

~ .-*

ROD TRAVEL HOUSING ---..J.

i i

OPERATING COIL STACK ASSEMBLY ,--..~

PRESSURE HOUSING DISCONNECT ROD - - .

(22 OCT 2001)

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

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

~r LINK PIN LATCH L1Nk 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

~ ~ L I F T RETURN SPRING

,~~SPRING RETAI MER

~ LATCH PIH

"-"- "-

LATCH ARM

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

" ' " ' LIIIK PIN

" ' " ' SUPPORT TUBE ST AT IONARY LATCH

~ LATCH STOP (22 OCT 2001)

Figure 3-295. Nominal Latch Clearance At Minimum And Maximum Temperature Catawba Nuclear Station BEFORE LOAD TRANSFER AFTER LOAD TRANSFER AT 70° AT 70° A B

A AT 650° AT 650° A B G) A B CD LI FT COi L OFF 15.725 15. 679 0.0116 L I FT CO I L OFF 15.679 J s.. 61+/ 0.038 LI FT COIL OH 16.375 16.387 0.068 LI FT COIL OH 16.387 J6.Wf 0.016 UFSAR Figure 3-295 (Page 1 of 1)

~

SG (22 OCT 2001)

Figure 3-296. Control Rod Drive Mechanism Latch Clearance Thermal Effect Catawba Nuclear Station 0.080 C l) w

z::

u 0.070 .,,.,,,,,,.

z:: /

- 0.060 UJ LIFT COIL OFF} MG CLEARANCE AFTER / /

0 LIFT COIL OM LOAD TRANSFER / /

0 a:::

0.050 c::,

//

w

> /

a::::

0 0,0q.O C.

z

<r

(/')

UJ 0.030 /

c /

u I-

/

_J

/

0.020 UJ u ~ - - ~ L I FT COIL ON } SG CLEARANCE BEFORE z:

<(

LOAD TRANSFER 0:::

<( 0.010 LI FT COIL 0M UJ

_J c.:,

0.000 0 100 200 300 400 500 600 700 UFSAR Figure 3-296 (Page 1 of 1)

TEMPERATURE (°F)

(22 OCT 2001)

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

Catawba Nuclear Station IJPPER CORE FUEL ASSEMBLY PUrE 6U I DE PIN GUIDE Pill CORE BARREL ENERGY ABSORBER ASSEMBLY OFF-SET INSTRIMNTA T 11>>1 COLIMI SECONDARY CORE SUPPORT BUTT TYPE COLIMI I HSTRUMENTA TI ON 6111 DE COLIN!

(CRUCIFORM)

E UPPER TIE Pl.ATE UTRON SHIELD PANEL FLANGE --.I UPPER CORE BARREL LOWER CORE BARREL RADIAL SUP~T

THE O.D. AND I.D. ARE CONTINUOUS BETWEEN UPPER MID LOWER BARREL.

TIIERE IS NO GIRTH WELD REDUCTION UFSAR Figure 3-297 (Page 1 of 1)

(22 OCT 2001)

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

Figure 3-298. Upper Core Support Structure (22 OCT 2001)

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

Figure 3-299. Plan View Of Upper Core Support Structure HEAD AHO 'JESSEL ALIGNMENT Pl N LOCATION SUPPORT COLUMNS GUIDE TUBE ASS£MBLV LOCATIOHS (22 OCT 2001)

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

Figure 3-300. Direct Generation Interactive Scheme Flow Chart Compuce

Cw) from&(~)

Using Equation. (10)

Compute a(~) 1 from

(~)

Using Equation (7)

NO OK i<~) is consistent with R(w)

(22 OCT 2001)

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

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

!tt ~ E D C L_____;o_

.::! A ~

I l

6 ,5 I

7j lil:IIEHAL ARIRII\Nlii:H[NT z

e I

I LO I

r A 11 11 f

1e 1 ..

131 r u ; 0:1 "'I la (22 OCT 2001)

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

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

... l: I.] ... .

N iiii im iiii (22 OCT 2001)

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

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

... t.:I L. w Ill m

D 0 u (22 OCT 2001)

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

Figure 3-304. Reactor Coolant Loop Model for Steam Generator Replacement (22 OCT 2001)

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

Figure 3-305. Loop Layout and Global Coordinates

~EAC"~

COOL:.r1

~UII?

REACTOR COOLANT

?UMP (22 OCT 2001)

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

Figure 3-306. RPV Shell Submodel

_ ~PPER HEAD C.G.

_ INTERNALS SUPPORT LEDG£ 25 TYPICALLY UNS~PPORTED NOULE (4)

TVPtCAL SUPPORTE!I NOZZLE (4>

17

[ K] STIFFlltSS MATRIX 19 -H-fLf -+I'- LINEAi! IMPACT

l()lj[R RADTAL

- - su,,oa1

_ LOWER 001'1£ I C.G.

(22 OCT 2001)

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

Figure 3-307. Core Barrel Submodel a OENQTES NOOU ON RPY sKm SUBMODEL -#-1Ci,,.t,t- CONCENT!IJC IMPACT

.....-+-I~ I-#- LlNEAR IMPACT

_co u SARtm Fl.ANGE

_ RPV NOZZLE

CEtlTERLIIIE

_ UPPER CORE PLATE Typical raprasentallon of the oonowm: impact elemrlnls between the fuel auembly grlcll am:! the core bal"T _ CORE C,G.

LOIIER CORE

-PLA TE LIIIIER RADIAL

- SUPPORT.

(22 OCT 2001)

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

Figure 3-308. Reactor Internals Submodel

,-, DENOTES HODES ON L.1 RPV SHELL SUl!HODEL 0 DENOTES NOD£S OM CORE BARREL SUIIIIODEL UPP!:R SUPPORT IS - PLATE SUPPORT COLUMNS ANO GUIDE TUBES 1 *tfihliff- Ll~EAR IMPACT UPPER CORE 11 -Pvm L

CORt

-c.G.

9 \ IIOTTflfll FIJEL L NOZZLE LOWER CORE

[!ll)-f1'-918 - PLATE (22 OCT 2001)

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

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 (22 OCT 2001)

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

Figure 3-310. Response Acceleration Spectra RESPONSE ACCELERATION, SA, !NG d) 00. o.oe 0.1s o.2q 0.32 o qo o,qa 0 S6 .

0

\

' ~ .*

0 0

---~

~-

a 0

N 0

~ ---~

_...,"'"::::J l:t-

-=---*

-~-

I~

~ . .

z £:::

--->7 U) rTJ ~

n_ <*

GI zo 00 U)

I? I,.,

I I

I N /, '"

en C

r-rn.

Cl>

C:

r- *.

0 0 ... ...

en Cl>

) ~

x

-t

x

~

x

-i i

I '"en

-t en

-t rn

<.n I "'- JI- .

z z 0

0 I -- -

If 0

0 0

(22 OCT 2001)

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