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
22-179
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 Q LOADING SEQUENCE 5 XHE-17A-D I 35 50 85 J JW NORMAL INJECTION 4 PLACES ROh1 DIESEL GENERATOR SIGNAL ESF B IPX4476A-HR-SW - 3/4" 'A' COOLER 2 9000 50 'l5 NORMAL LOADING SEClUENCE 8' A l----+.!.7.!270!!!04-...:5e,0'----jf-':13c:0"-f--rP-';O-;::ST:::::;A:;C~CI_D1 ~ 8 PLACES 4 PLACES ~

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

5 r' LO,...... ro u Cl l ~

150 'l5 3/4' /R0,-22

~ ROp-4'1 / 311'lA-SW @ I HVAC CHILLER 3104A-SW 3131A-SW w 68 02

'APPROX. C CONTROL 8' 20'

<GAi OWG B-208-10'1 B SHT VU03 & VU041 B I I 20' IPX445511-HR-8'rlrril XPS-I 46A-SW !FT 4460-LR-SW ~ 20' ZS /PX\\ ROb-1 1 2b CD

~ ~ ~ 3138A-SW co 3/4

• 1*x3/4* !~~. I,;;::,.._ ~"'Nh.:,.-l;::5=-,---1:1 NC 20 3/4'x1/2~TSC 3I24A-SW 3' RNg-14,,- nM~ ::!:<r >----.::-y~~~~~~, *~

• 3I22A-SW J;- ~1~~ 3 SW ~ ~ 152N FE VENT :,, 151X 4460 XVV13I43A-SW IN)..~--,-----T.,,\\-,_I~ -"~, ECR-50567 C H C COMPONET COOLING 1-'.-'-':::-ic- - A ~ ~ VENT HEAT EXCHANGER 'A' 01 "xp"'s:-_-:-=10"'37A-...,s"'w,...._ ---

J-3 30' 24' 24' LOOP 'A' -221 I' SW 2' YoRAIN

D D

ROH-17 I3I38-SW

ROhl 3146B-SW E IPX4546B-HR-SW E HVAC CHILLER ROhl CGAI DWG B-20 B CONTROL

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 16' 6'

"' RNn-55

.....I 3I26B-SW 0 STATION DRAINAGE 6' u E-911-I06 I-LDC G-8 z

)

G (!) I' G z

,_, LOOP 'B' 3.....I ¢ Y RAIN

- (J) 0 J-'l

"'* 0 -221 L Jl "' ' "' u o-,_,

0: M 0.. SW I ~~l!fN-~ 20'r-6-J a:

Cl ID REQ'Dl 8' 0 3 0 8' l-a:

1-w.,.... !£ lL H <J: '-' ' '.. UJ H 3

X (!)

ID

- z STATION DRAINAGE

-,_, E-911-I06 1--------< 151X 152N RN,-'l !FT z.....I

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

!!l 0 3I46D-SW u ROH-17 2" NOTES: !. ALL PIPING TO BE LINE SPEC 152N. 13I39-SW 2.CHECK VALVE W/CONTROLLABLE DASH POTS. EXCEPT AS NOTED.

3.TEMP CORRESPONDING TO PERTINENT HEAT EXCHANGER OUTLET. X IIRIWING Cl.ASS LEGIBILl!Y I

4. CEP-CONTROL ROOM EVACUATION PANEL. LJ -

5.ALL STATUS LIGHT INDICATE BOTH OPEN DR !£l NUCLEAR SAFETY RELATED THIS IS A AND CLOSED POSITIONS. DOCUM£HT. NO DEVIATION SH"'- OE J

6.

• DENOTES MISSION DUO CHECK OR EOUAL. NllATEO OR PERFORMED WITHOUT PRIOR HYDROSTATIC TEST TEMP. 60" 2 7. ** INOICA TES SWITCHES, ALARMS ANO INDICATING DOCI.Jt,IENTATION #ID WRITJEN APPROV/ll

!FT 4492-LR-SW RETURN TD X R0,-14 LIGHTS ARE LOCATED ON THE HVAC CONTROL BOARD Ill S.W. POND " """' - 3136B-SW (XCP-62I0-AH) IN THE MAIN CONTROL ROOM. FSAR FIGURE 9.2-2 12 120 95 188 214 <I3/4 235 ccs !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 XPS-147A-SW RDq-11 ROq-11 I0.FOR VENTS AND DRAINS ON XAA-IA,IB,-2A 8 16 95 20 214 (!Y. 25 ccs 3I37A-SW 3I37B-SW & 2B-AH. SEE DETAIL 'A' ON OWG. 0-302-221. VIRGIL C, 51JNMER NUCLEAR STATION 7 16 124 20 13111 25 WTW LRC I 11* j?g~0 fi\\,f tefBA iilJN"bO.Jif~'if Ptfc \\DflflT'if'MTED~~9~fN1!_0N PIP!NG SYSTEM FLOW PEN.* PEN.' DIAGRAM 6 65 124 65 130 82 TW LRC NN 16" 3/4" 1su 5 65 95 65 95 82 ccs NOTE 3 MRF-22144 MRF-22I44 I55X 2" 4031}--'-'-'-rc-2,::-,-f'r--:2:::,:-r, ---i REFERENCE NCN5063 OISP. *4. tr:c~[:-D,c~,c~e7.~cc= 52 4/271115 RHM REVISED PER ECR-50064 RHM BCB,tlr-~:c~c.cwc,=-= -! -,,,~,=~~~°'~~~~~ ~J~~.;~,,,;~ec~~g.. ~"~;.~d= -=-=-f T~;~.;~.. ~ 7~ '~"'~"~'= -rl---__ -: _z _s --:--_ - -T 2:_SE~R~V~IC~E;~W~A;TE~R;;C~O~O;Ll~NG;======1 K 4 120 95 188 214 <IY. 235 ccs NOTE 3 Jl32-SW 3141-SW cs, 58 9118/08 RHM REVISED PER ECR-71211 MGR GK C:, DESIGN ENGINEERING K 2' ROp-15 ROp-15 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_11R;t:JHMM18sacss7,,.,::"'...,.. v. c....... NUCLEAR STATION JEN<..... LLE ** c.

2 16liJ 95 185 95 <lY. 235 ccs 2" I3135-SW 2" 13137-SW r-56 t/28/08 RHM REVISED PER ECR-50567 RHM BCB...,. CHEOOD LE,.PROV"-

PSIG F PSIG F DURATION HYDR BY CHO REMARK *..:~ ~11-::-:-. -b.,,~ 2' R0p-15 UPSET R0p-1e

" MRF-22I44,,- 2'

• I3134-SW DETAIL 8 13136-SW DETAIL A DR 53 5126/05 RHM REVISED PER ECR-50605 RHM CCB DESIGN DATA 3133-SW DETAIL C OR LE NO. DATE BY "'.,., D-302-222 REVISION CKD. BY OVAL DRAWING Nt.>>eER 58 SHT. NUIIIK1II REV 5' 15' 20'