ML21209A377

1 to Updated Final Safety Analysis Report, Chapter 9, Figure 9.2-2, Revision 58, Piping System Flow Diagram Service Water Cooling

ML21209A377
Person / Time
Site:	Summer
Issue date:	04/30/2021
From:	Dominion Energy South Carolina
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21209A581	List: ML21209A111 ML21209A112 ML21209A113 ML21209A114 ML21209A115 ML21209A116 ML21209A117 ML21209A118 ML21209A119 ML21209A120 ML21209A121 ML21209A122 ML21209A123 ML21209A124 ML21209A125 ML21209A126 ML21209A127 ML21209A128 ML21209A129 ML21209A130 ML21209A131 ML21209A132 ML21209A133 ML21209A134 ML21209A135 ML21209A136 ML21209A137 ML21209A138 ML21209A139 ML21209A140 ML21209A141 ML21209A142 ML21209A144 ML21209A145 ML21209A146 ML21209A147 ML21209A148 ML21209A149 ML21209A150 ML21209A151 ML21209A152 ML21209A153 ML21209A155 ML21209A156 ML21209A157 ML21209A158 ML21209A159 ML21209A160 ML21209A161 ML21209A162 ... further results
References
21-167
Download: ML21209A377 (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 600 45 > 65 NORMAL (GAi DWG B-208-109 SHT VUIIJ!l 45 > 65 POST ACCID 5

150 'l5

~ ROp-4'1 / 3/4' /R0,-22 311'lA-SW HVAC CHILLER 3104A-SW 3131A-SW C CONTROL 8' w

'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*

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!~~. 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 I3138-SW E E HVAC CHILLER ROhl B CONTROL CGAI DWG B-20 10'l SHT VU OG '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 D-802-014, SHT 5 16' 6'

"' RNn-55 3126B-SW

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

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3

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LOOP 'B' J-'l ¢ YDRAIN

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

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

!!l 0 3146D-SW u ROH-17 2"

NOTES:

!. ALL PIPING TO BE LINE SPEC 152N. 13139-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 OUO CHECK OR EOUAL, DOCI.Jt,IENTATION #ID WRITJEN APPROV/ll HYDROSTATIC TEST TEMP. 60" 7. ** INDI CA TES SWITCHES, ALARMS AND INDICATING RETURN TO X R0,-14 LIGHTS ARE LOCATED ON THE HVAC CONTROL BOARD

!FT 4492-LR-SW 12 120 95 188 214 <13/4 235 ccs S.W. POND " """' I ll 3I36B-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 'l5 (13/4 210 RJS FLOW INSTRUMENTATION. SOUTH CAROLINA ELECTRIC & GAS COIIPANY ROq-11 I0.FOR VENTS AND DRAINS ON XAA-IA,IB,-2A

'l 16 150 20 150 (];( 25 ccs XPS-147A-SW ROq-11

& 2B-AH. SEE DETAIL 'A' ON OWG. D-302-221. VIRGIL C, 51JNMER NUCLEAR STATION 8 16 95 20 214 (!3/4 25 ccs 3137A-SW 3I37B-SW RN 08-026 7 16 124 20 130 25 WTW LRC PEN.*

I PEN.'

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November 2008 PIP<NG SYSTEM FLOW DIAGRAM ISP. cwc,=-=-,,,~,=~~~°'~~~~~

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16" 3/4" 1su 6

5 65 65 124 95 65 65 130 95 82 82 TW LRC ccs NOTE 3 MRF-22I44 MRF-22I44 NN 155X 2" 4031}--'-'-'-rc-2,::-,-f'r--:2:::,:-r,- - - i REFERENCE NCN5063 *4. tr:c52~[:-D,c4/271115 58 9118/08

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2 160 95 185 95 (13/4 235 ccs 2' 2' 2" ROp-15 2"

ROp-15 r 56 t/28/08 RHM REVISED PER ECR-50567 11R;t:JHMM sacss , ,.,::"'...,..

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

PSIG F PSIG F DURATION HYOR BY CHO REMARK UPSET

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R0p-1e I3135-SW ROp-15 13137-SW CHECl(E!) LE ,.PROV"-

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• I3I34-SW DETAIL 8 13136-SW DETAIL A 53 5126/05 RHM REVISED PER ECR-50605 RHM CCB

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