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

I 2

14 SYSTEM DATA GPM PS!G *

'F BY REMARKS 35 50 85 J JW NORMAL 9000 50

'l5 NORMAL 13 SAFETY INJECTION SIGNAL 12 A l----+.!.7.!270!!!04-...:5e,0'----jf-':13c:0"-f--rP-';O-;::ST:::::;A:;C~CI_D1 1000 50

'l5 NORMAL 3

~

8 PLACES HVAC CHILLER B

C D

E F

G H

820 50 116 POST ACCID 4 1000 to 45

> 65 NORMAL 600 45

> 65 POST ACCID 5

150

'l5

'APPROX.

HYDROSTATIC TEST TEMP. 60" 12 120 95 188 214

<I3/4 10 125

'15 165 95

<IY.

'l 16 150 20 150

(];(

8 16 95 20 214

(!Y.

7 16 124 20 13111 6

65 124 65 130 5

65 95 65 95 3

(J)

Jl "'

o-0: M 235 ccs 21111 RJS 25 ccs 25 ccs 25 WTW LRC 82 TW LRC 82 ccs A CONTROL (GAi DWG B-208-109 SHT VUIIJ!l HVAC CHILLER C CONTROL 8'

<GAi OWG B-208-10'1 SHT VU03 & VU041 I

I

~ ~

J-3 LOOP 'A' -221 SW 30' HVAC CHILLER 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 DG '8' HI LUBE OIL/HI WATER JACKET TEMPERATURE LOGIC SEE GAi DWG 0-802-014, SHT 5 X -

ID -

z

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z

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0 u 0..

a:

Cl 0 l-a:

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z

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0 u NOTE 3 STATION DRAINAGE E-911-I06 LDC G-8 LOOP 'B' J-'l

-221 SW ID REQ'Dl 8'

24' 24' 2'

8'

.,.... !£ lL

.. UJ K 4 120 95 95 188 214

<IY.

<lY.

235 ccs 235 ccs NOTE 3 2

16liJ PSIG F

185 PSIG 95 F

DURATION HYDR BY CHO REMARK UPSET DESIGN DATA Q

4 PLACES 11 ESF A LOADING SEQUENCE 10 9

ROh1

~

ESF B LOADING SEClUENCE IPX4476A-HR-SW -

3/4" 16' 4 PLACES 20'

~

ROp-4'1

/

3104A-SW 3131A-SW ZS 20 20'

/PX\

~

RNg-14 3I22A-SW 6'

6' RNn-55 3I26B-SW I ~~l!fN-~

COMPONET COOLING HEAT EXCHANGER 'A' ZS

¢ w

3/4'

/R0,-22 311'lA-SW IPX445511-HR-8'rlrril ROb-1 1

2b 3138A-SW 3/4*

1*x3/4*

0 3 L

20'r-6-J STATION DRAINAGE E-911-I06 1--------<

LOC. G-11 NN MRF-22144 MRF-22I44 I55X Jl32-SW 3141-SW

• ..:~ ~11-::-:-. -b.,,~ 2' MRF-22I44,,-

2' 3133-SW 2'

5' 15' 20' 8'

DETAIL C 8

ROh-1 S _661 IPX447 5

XHE-17A-D DIESEL GENERATOR

'A' COOLER XPS-I 46A-SW

!~~.

7 6

!FT 4460-LR-SW

~

CD 20' co I

~"'Nh.:,.-l;::5=-,---1:1 NC 3'

3/4'x1/2~TSC 3I24A-SW nM~

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1-'.-'-':::-ic- -

A 01 H

FE 4460 XPS-147A-SW J;-~1~~3 SW

~ ~

VENT IN)..~--,-----T.,,\-,_I~ -"~,

~ ~

"xp"'s:-_-:-=10"'37A-...,s"'w,...._ ---

!FT 4492-LR-SW

!FT44'l2-HR-SW I

RETURN TD S.W. POND PEN.*

R0p-1e 2"

I3134-SW DETAIL 8 2"

RDq-11 3I37A-SW 16" ROp-15 I3135-SW OR 5

2 X -

Ill -

PEN.'

ORC* !RC R0,-14 3136B-SW ROq-11 3I37B-SW 3/4" 4031}--'-'-'-rc-2,::-,-f'r--:2:::,:-r, ---i 1su cs, ROp-15 2"

13137-SW R0p-15 13136-SW DETAIL A DR 4

ROhl 3

2 r' LO ro u Cl l

~

I 68 02 3146B-SW ROhl IPX4546B-HR-SW 151X 152N RN,-'l

!FT 4498-LR-SW 3I46D-SW NOTES:

!. ALL PIPING TO BE LINE SPEC 152N.

EXCEPT AS NOTED.

2.CHECK VALVE W/CONTROLLABLE DASH POTS.

3.TEMP CORRESPONDING TO PERTINENT HEAT EXCHANGER OUTLET.

4. CEP-CONTROL ROOM EVACUATION PANEL.

5.ALL STATUS LIGHT INDICATE BOTH OPEN AND CLOSED POSITIONS.

6.

• DENOTES MISSION DUO CHECK OR EOUAL.

ROH-17 13I39-SW

7. ** INOICA TES SWITCHES, ALARMS ANO INDICATING LIGHTS ARE LOCATED ON THE HVAC CONTROL BOARD (XCP-62I0-AH) IN THE MAIN CONTROL ROOM.

9.RECORDER SHARED WITH REACTOR BLOG SPRAY PUMP FLOW INSTRUMENTATION.

I0.FOR VENTS AND DRAINS ON XAA-IA,IB,-2A 2"

LJ DR X -

!£l 1

152N ROH-17 I3I38-SW 151X XVV13I43A-SW ECR-50567 VENT I'

YoRAIN I'

YRAIN IIRIWING Cl.ASS LEGIBILl!Y I THIS IS A NUCLEAR SAFETY RELATED DOCUM£HT. NO DEVIATION SH"'- OE NllATEO OR PERFORMED WITHOUT PRIOR DOCI.Jt,IENTATION #ID WRITJEN APPROV/ll FSAR FIGURE 9.2-2 SOUTH CAROLINA ELECTRIC & GAS COIIPANY

& 2B-AH. SEE DETAIL 'A' ON OWG. 0-302-221.

VIRGIL C, 51JNMER NUCLEAR STATION 11* j?g~0fi\,f tefBA iilJN"bO.Jif~'if Ptfc \DflflT'if'MTED~~9~fN1!_0N PIP!NG SYSTEM FLOW REFERENCE NCN5063 OISP. *4.

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-rl---__ -: _z _s --:--_ --T 2:_SE~R~V~IC~E;~W~A;TE~R;;C~O~O;Ll~NG;======1 52 4/271115 RHM REVISED PER ECR-50064 RHM BCB 58 9118/08 RHM REVISED PER ECR-71211 MGR GK C:,

DESIGN ENGINEERING 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_11 R;t:JHMM18sacss7,,.,::"'...,.. v. c....... NUCLEAR STATION JEN<..... LLE ** c.

r-56 t/28/08 RHM REVISED PER ECR-50567 RHM BCB CHEOOD LE,.PROV"-

DIAGRAM 53 5126/05 RHM REVISED PER ECR-50605 RHM CCB LE REVISION CKD. BY OVAL NO.

DATE BY D-302-222 DRAWING Nt.>>eER 58 SHT. NUIIIK1II REV B

C D

E F

G H

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RN 08-026 November 2008