ML22194A269

2 to Updated Final Safety Analysis Report, Figure 9.2-2, Service Water Cooling

ML22194A269
Person / Time
Site:	Summer
Issue date:	06/27/2022
From:	Dominion Energy South Carolina
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22194A236	List: ML22194A109 ML22194A110 ML22194A111 ML22194A112 ML22194A113 ML22194A114 ML22194A115 ML22194A116 ML22194A117 ML22194A118 ML22194A119 ML22194A120 ML22194A121 ML22194A122 ML22194A123 ML22194A124 ML22194A125 ML22194A126 ML22194A127 ML22194A128 ML22194A129 ML22194A130 ML22194A131 ML22194A132 ML22194A133 ML22194A134 ML22194A135 ML22194A136 ML22194A137 ML22194A138 ML22194A140 ML22194A141 ML22194A142 ML22194A143 ML22194A144 ML22194A145 ML22194A146 ML22194A147 ML22194A148 ML22194A149 ML22194A150 ML22194A151 ML22194A152 ML22194A153 ML22194A154 ML22194A155 ML22194A156 ML22194A157 ML22194A158 ML22194A159 ... further results
References
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Download: ML22194A269 (1)

Text

14 13 12 11 10 9 8 7 6 5 4 3 2 1 ROh-1 SYSTEM DATA ESF A S _66 1 IPX447 GPM PS!G * 'F BY REMARKS SAFETY INJECTION Q

4 PLACES LOADING SEQUENCE ROh1 5 XHE-17A-D DIESEL GENERATOR I 35 50 85 J JW NORMAL SIGNAL 'A' COOLER 3/4"

~

ESF B IPX4476A-HR-SW -

2 9000 50 'l5 NORMAL A l----+.!.7.!270!!!04-...:5e,0'----jf-':13c:0"-f--rP-';O-;::ST:::::;A:;C~CI_D1

~ 8 PLACES 4 PLACES LOADING SEClUENCE 8' 3 1000 50 'l5 NORMAL HVAC CHILLER 820 50 116 POST ACCID A CONTROL 4 1000 to 45 > 65 NORMAL (GAi DWG B-208-109 600 45 > 65 POST ACCID SHT VUIIJ!l

....r' -

~I LO ,......

5 Cl rol u 150 'l5 HVAC CHILLER C CONTROL 8'

~ ROp-4'1 3104A-SW 3131A-SW

/

w 3/4' /R0,-22 311'lA-SW @ 68 02

'APPROX. <GAi OWG B-208-10'1 20' SHT VU03 & VU041 B I I 20' !FT 4460-LR-SW ~ B IPX445511-HR-8'rlrril XPS-I 46A-SW

/PX\ 20'

~ ~ ZS

~

ROb-1 3138A-SW 1

3/4* 1*x3/4*

2b co CD

!~~. I ,;;::,.._ ~"'Nh.:,.-l;::5=-,---1:1 NC 20 3/4'x1/2~TSC 3I24A-SW 3' RNg-14 ,,-

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>----.::-y~~~~~~, * ::!:<r *~

3I22A-SW J;- ~1~~ SW 3 ~~

VENT  :,, 152N 151X FE 4460 XVV13I43A-SW IN)..~--,-----T.,,\-,_I~ - " ~ , ECR-50567 C H C COMPONET COOLING 1-'.-'-':::-ic- -

01 A ~ ~ "xp"'s:-_-:-=10"'3 A-...,s"'w,...._ - - -

7 VENT HEAT EXCHANGER 'A' J-3 24' 30' 24' LOOP 'A' -221 I' SW 2' YoRAIN D D ROH-17 I3I38-SW 3146B-SW ROhl E IPX4546B-HR-SW E HVAC CHILLER ROhl B CONTROL CGAI DWG B-20 109 SHT VU DG 'A' HI LUBE OIL/HI WATER JACKET TEMPERATURE LOGIC SEE GAi DWG 0-802-014, SHT 5 ORC*' !RC F F DG '8' HI LUBE OIL/HI WATER JACKET TEMPERATURE LOGIC ZS SEE GAi DWG 0-802-014, SHT 5 6' 16'

"' RNn-55 3I26B-SW

.....I 0 STATION DRAINAGE 6' u E-911-I06 I- LDC G-8 z

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YRAIN 3

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LOOP 'B' J-'l ¢

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.....I STATION DRAINAGE E-911-I06 1--------< 151X 152N RN,-'l

(\J 0 LOC. G-11 !FT 4498-LR-SW

!!l 0 3I46D-SW u ROH-17 2"

NOTES:

!. ALL PIPING TO BE LINE SPEC 152N. 13I39-SW EXCEPT AS NOTED.

2.CHECK VALVE W/CONTROLLABLE DASH POTS.

3.TEMP CORRESPONDING TO PERTINENT HEAT IIRIWING Cl.ASS EXCHANGER OUTLET.

4. CEP-CONTROL ROOM EVACUATION PANEL.

5.ALL STATUS LIGHT INDICATE BOTH OPEN LJ DR X

!£l LEGIBILl!Y I THIS IS A NUCLEAR SAFETY RELATED J AND CLOSED POSITIONS. DOCUM£HT. NO DEVIATION SH"'- OE NllATEO OR PERFORMED WITHOUT PRIOR 2 6.

• DENOTES MISSION DUO CHECK OR EOUAL. DOCI.Jt,IENTATION #ID WRITJEN APPROV/ll HYDROSTATIC TEST TEMP. 60" 7. ** INOICA TES SWITCHES, ALARMS ANO INDICATING

!FT 4492-LR-SW RETURN TD X R0,-14 LIGHTS ARE LOCATED ON THE HVAC CONTROL BOARD 12 120 95 188 214 <I3/4 235 ccs S.W. POND " """' I ll 3136B-SW (XCP-62I0-AH) IN THE MAIN CONTROL ROOM. FSAR FIGURE 9.2-2

!FT44'l2-HR-SW 9.RECORDER SHARED WITH REACTOR BLOG SPRAY PUMP 10 125 '15 165 95 <IY. 21111 RJS FLOW INSTRUMENTATION. SOUTH CAROLINA ELECTRIC & GAS COIIPANY

'l 16 150 20 150 25 ccs RDq-11 I0.FOR VENTS AND DRAINS ON XAA-IA,IB,-2A

(];(

XPS-147A-SW ROq-11

& 2B-AH. SEE DETAIL 'A' ON OWG. 0-302-221. VIRGIL C, 51JNMER NUCLEAR STATION 8 16 95 20 214 (!Y. 25 ccs 3I37A-SW 3I37B-SW RN 08-026 7 16 124 20 13111 25 WTW LRC PEN.*

I PEN.'

11* j?g~ fi\,f tefBA iilJN"bO.Jif~'ifPtfc \DflflT'if'MTED~~9~fN1!_0N 0

November 2008 PIP!NG SYSTEM FLOW DIAGRAM RHMcwc,=-= -,,,~,=~~~°'~~~~~

-! REVISED ~J~~.;~ ..~

NN 16" 3/4" 1su 6

5 65 65 124 95 65 65 130 95 82 82 ccs TW LRC NOTE 3 MRF-22144 MRF-22I44 I55X 2" 4031}--'-'-'-rc-2,::-,-f'r--:2:::,:-r,- - - i REFERENCE NCN5063 OISP. *4. tr:c52~[:-D,c4/271115 58 9118/08

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C:, DESIGN ENGINEERING K 4 120 95 188 214 <IY. 235 ccs NOTE 3 Jl32-SW 3141-SW cs, K sacss , ,.,::"'...,..

2 16liJ 95 PSIG F PSIG 185 95 <lY.

F DURATION 235 ccs HYDR BY CHO REMARK 2'

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2' 2" ROp-15 I3135-SW 2" ROp-15 13137-SW 1 g,s1f--!!¥,'28/08~l-HR~H~M;t--;:R:;:Etv1;;'s;;:ED~P~E~R-;E;;:c;;;R;::-s~o~s~6';1_

r- 56 t/28/08 RHM REVISED PER ECR-50567 11R;t:JHMM RHM18 BCB 7 ...,.

v. c....... NUCLEAR STATION JEN<.....LLE ** c.

CHEOOD LE ,.PROV"-

UPSET R0p-1e R0p-15

" MRF-22I44,,- 2'

• I3134-SW DETAIL 8 OR 13136-SW DETAIL A 53 5126/05 RHM REVISED PER ECR-50605 RHM CCB

"' .,., D-302-222 58 DESIGN DATA 3133-SW DETAIL C DR NO. DATE BY REVISION CKD. BY LE OVAL DRAWING Nt.>>eER SHT. NUIIIK1II REV 5' 15' 20'