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
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References
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Download: ML21209A377 (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

<13/4 10 125

'15 165

'l5 (13/4

'l 16 150 20 150

(];(

8 16 95 20 214

(!3/4 7

16 124 20 130 6

65 124 65 130 5

65 95 65 95 3

(J)

Jl "'

o-0: M 235 ccs 210 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 10'l SHT VU OG '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 D-802-014, SHT 5 X -

ID -

z

(\\J

!!l

..J 0 u f-

...... z

)

t:J z

..J 0

0 u 0..

a:

Cl 0 f-a:

w f-

<J:

3 t:J z

..J 0

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

<I3/4 (13/4 235 ccs 235 ccs NOTE 3 2

160 PSIG F

185 PSIG 95 F

DURATION HYOR 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 3126B-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-22I44 MRF-22I44 155X 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~

!:<r

>----.::-y~~~~~~, '~

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 TO S.W. POND PEN.*

R0p-1e 2"

I3I34-SW DETAIL 8 2"

ROq-11 3137A-SW 16" ROp-15 I3135-SW OR 5

2 X -

Ill -

PEN.'

ORC* !RC R0,-14 3I36B-SW ROq-11 3I37B-SW 3/4" 4031}--'-'-'-rc-2,::-,-f'r--:2:::,:-r, ---i 1su cs, ROp-15 2"

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

ROhl 3

2 151X 152N RN,-'l

!FT 4498-LR-SW 3146D-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 OUO CHECK OR EOUAL, ROH-17 13139-SW

7. ** IND I CA TES SWITCHES, ALARMS AND 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 1

152N ROH-17 I3138-SW X -

!!l 151X XVV13I43A-SW ECR-50567 VENT I'

YoRAIN I'

YDRAIN 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. D-302-221.

VIRGIL C, 51JNMER NUCLEAR STATION 11* j?g~0fi\\,3f tef8A 'lii1N"b0.Jif~'if Ptfc \\0fs°T'if'MTEo~~9~fN1f.0N PIP<NG SYSTEM FLOW REFERENCE NCN5063 ISP. *4.

tr:c~[:-D,c~,c~e7.~cc=,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 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~~5~6';1_11 R;t:JHMM18sacss7,,.,::"'...,.. v. c....... NUCLEAR STATION JEN<..... LLE ** c.

r 56 t/28/08 RHM REVISED PER ECR-50567 RHM BCB CHECl(E!)

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

J K

RN 08-026 November 2008