ML22194A149

2 to Updated Final Safety Analysis Report, Figure 9.3-12, Rev. 28, Piping System Flow Diagram Reactor and Auxiliary Building Sump Bumps

ML22194A149
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: ML22194A149 (1)

Text

{{#Wiki_filter:14 13 12 11 10 9 8 7 6 5 4 3 2 SYSTEM DATA 151R 2505X "7 SAMPLE 3/4" ROc-29 ROf-38 GPM PSIG "F BY REMARKS 155X 151R 151R 155X 6216-ND \\ 6230-ND \\ 50 35 100 DJK CONTAINMENT ROf-38 3" 3" -155X ISOLATION 2 50 20 100 DJK PHASE A >----< A RO -35 6262-ND 6241-ND,--------------'---+---------'---,-------11------------r'-J----H--------------------------- I 3" LC A 02 2" 3/4" 0.0. 2" 2" A-13 2"-155X I A 3 50 30 100 DJK 2a Q ~I\\ TV 3 -736 5 I 4 50 30 100 DJK 3/4"~: ~ n CTl3/4" WO ROf-36

~-~ \\ r-- ROf-36 ROf-36 \\ ROf-36 2" I 5 50 20 100 DJK s ---ED I I f-_.,>, EO / 6214A-ND / 6214B-ND 62468-ND I 3" 2" 3" -155X 2 >------J_----~if-~,-----{424}-_l_L\\ _ __.,,.ifL----_l_ _ __J k-t:;.,,'-NOTE 1-~- ROc-23 3/4" PEN. CBV S 3/4" ~ 62458-ND ~

6 100 40 100 PLL 7 50 20 100 DJK CIV,-1-- 1,,-l CIV~ 2505X 155X ROf-36 / 6231A-ND :-':~[") ' " 3 2" ROc-23 2,, ROc-23 6217A-ND 2" <I ' 8 150 40 100 PLL F C '' ! 3/4" ' F C RNn-34 I L I I I L / 6228A-ND / 62288-ND 3 ROc-23 2" 9 50 40 100 PLL 6242A-ND 1, A !, - 1 6242B-ND 155X 2505X 2505X 155X 6231B-ND\\ 155X 2505X WASTE HOLD UP TANK

'L ___________________________ J ~ ! :0, ROf-38 ROf-38 10 75 55 100 DJK 2" :,,\\_ TSCi I TSC 6203A-ND 3/4" 0.0. 6205A-ND~"'--._-~::::::i"':r ROf-38 B 2" : ~ ri--: ~ ~-~.----+---< ROf-38 ROc-23 6205B-ND B
' ESF : : 0v LEAKAGE 3/4" I 62038-ND / 6245A-NO 1 1 ! L 1 )45 GPM f--{)'Ch 3/4" 0.0.

ROf-36 L ________ _, I 6213A-NO\\ ESF I F-9 ROf-35 RKf-62 LS -641 / ROf-36 1965 RHR ROf-39 \\ 6246A-ND H-9 ROf-36 1" ~ ~ 6215-ND -641 6213B-ND\\ FL. EL. 374'-0' ~ 3/4,, RH-601R 3"- 155X 3/4" RH-501R RHR FLOOR ELEV. 388'-0" ROc-23 I RHR I 6227A-ND ROc-23 I TS~0~--+i-g-~-~-M I I PUMP 50 GPM (Ls"\\

~ SUMP
; ~f-38 ~ ~ "A" _J I 40 FT ~

XST-81 -ND MF-lC / \\ MF-IC

~ y XPP-114A-ND 1 C LEAKAGE XPP-114B-ND BOT. OF SUMP C 3/4" 1- ~ ~ PI )45 GPM EL. 385'-0" WASTE -:-;_, 7 1-7457 EVAP.FEED..,. LI~ LO PUMP SUMP RHR PUMP BOT. OF SUMP I RECYCLE HOLDUP

11 811 EL. 371'-0" ROOM SUMP TANK ROOM SUMP 13'-0" x 4'-0" x 3'-0" DEEP).,- ~ID,M3 14'-0" x 3'-0" x 3'-0" DEEP)

<I "

3" FL. DRAIN TANK R f-41 ROf-39 ~

D 3" z 3"-151X I ROf-40 D <I ' \\ £CE&G 10 f------=-_:_:=-~)<:J----, / 6259-ND D

-------' _L EL. 400'-0" 2505X HOLDUP TANK 3"

G;)n 15'-0" x 5'-0" x 11'-0" EEPI : ~ 1 ROf-38 155X 2505X ROf-41

I 1971,0- 1972 6207A-ND 6247B-ND

C <__:) C SUMP (4'-0" x 1'-0" x 1'-0" DEEP) ROc-65 I

I NO LONGER USED 3/4" /6238B-ND E FOR L.. OUTSIDE R f-40 E ROf-38 6209B-ND 3"

@ CONTAINMENT REACTOR 6207B-ND 3/4" 0.0.

6 INSIDE 3/4" 0.0. @] REACTOR L _ _ I CONTAINMENT FLOOR ELEV. 374'-0" 3/4" 0.0. !1/2" FL. EL. 374'-0"

'-r--,-L------+--------,---+--+-

MF-3 100 GPM /XPP-112B-ND MF-3 NOTE 2 40 FT. 2505X 151X 2505X 151X /XPP-112A-ND

~~ LS LS ~~

2" -155X MF-10 / 100 GPM \\ MF -10 7772 XPP-50A-ND 40 FT. XPP-50B-ND 75 GPM 75 GPM F 110 FT 110 FT F BOT.OF SUMP BOT. OF SUMP EL. 370'-0" EL. 371'-0"

NOTE: 2" 2" AUX BUILDING BLOWDOWN SYSTEM

1. THESE VALVES SHALL BE SET SUMP 2" SUMP TO OBTAIN FLOW RATE OF ROf-36 ROf-36 (10'-0" x 6'-6" x 4'-0" DEEP) (3'-0" x 3'-0" x 3'-0" DEEP) 50 GPM MAXIMUM. /6218B-ND

2. REMOVABLE SPOOL PIECE TO PERMIT ~ 3" -155X INCORE INSTRUMENT SUMP PUMP 8 DISCHARGE TO REACTOR COOLANT 2" DRAIN TANK IPER MRF 207071 7 >-----,-----II!~-----, / D-5

ROc-23 ~ r 6260-ND 1 -661 __ ~2~"-:--<:::::=;~::::i G 6226A-ND ROr-36 G-9 2"-155X 155X SP G 2505X 155X ROc-23 6222-ND \\ -661 2" 9 ROf-36 62268-ND"" ROf-38 SP 155X 2" E-5 3" -155X 2505X 155X ~ -661 6200B-ND 155X SP 3/4" 0.0. 7704 7705 ROc-23 2" [") TO WASTE lS)

' I L ___ _ ' I \\_ ___ _ L _________ - --------------------~-~----------7 ',.J ITT ~ HOLD-UP TANK 2"-155X

-- ~-----1 __ I :i:-' ' - ROc-23 LEAKAGE ' 1 ! I O" / 6234-ND I~ > 1 GPM0.J i - ROf-38 ~ 155X 2505X 2505X 155X 1 6200A-ND 3/4" 0.0. I ' LS I A ---------------------,,~!--i----- 1973 6210-ND I

, ~----------------------_, ! @s 4" RKb-218 H I ~ Pl MB-4F ILG07760-HR-ND ~~~ H

-........ :...._ I '~ I L - -, __________ _J ' r 1974 XTK-109-ND
----- I \\__! : \\----------r--- RKb-21B I FL. DRAIN TK.

1 I ILG07760-LR-ND 3/4" 0.0. R f-38 I 1 FLOOR EL. 387'-6" 4" 9 I I ~ -, 6211-ND ~I I MF-lA I 3/4" 0.0. MISC 1 XPP-59A-ND I WASTE GPM I DRAIN 1---, \\ ______________ I ____ _J r FL. EL. I LE I ,__ 1973 FT. --- FL. EL. 412'-0"--+--~ TANK : _ 3~4'-0" THIS IS A I~ 50 GPM MF-IA NUCLEAR SAFETY RELATED BOT. OF SUMP 65 FT. XPP-59B-ND DOCUMENT.NO DEVIATION SHALL BE EL. 386'-6" MF-lB 2" -155X INITIATED OR PERFORMED WITHOUT PRIOR XPP-130-N \\.,__~ ----..-----'/ X PP -111 - ND LE DOCUMENTATION AND WRITTEN APPROVAL J i 7759 2" 7761 J INCORE INSTRUMENTATION 50 GPM I "' 50 GPM, 50 FT. I "' ESSENTIAL SUMP BOT.OF SUMP-+--+-, 40 FT. I - t c-23 \\ ROf-36 EL. 409'-0" I :\\ 15'-0" x 2'-0" x 1'-0" DEEP) I ~ 6235-ND 6221-ND

I i\\l I FSAR F1gur-e 9.3-12

!RC ORC EAST PENETRATION,-------- WASTE HOLDUP t BOT. OF SUMP 0HI-LO INTERLO EL. 371'-0" SOUTH CAROLINA ELECTRIC & GAS COMPANY ACCESS AREA SUMP HI-HI RH-2 6 HP TANK ROOM SUMP
=~~ 3450 RPM DRAWING LEGIBILITY 13'-0" x 3'-0" x 3'-0" DEEP) RKf-23 XPP-116-ND 460 V (3'-0" x 3'-0" x 3'-0" DEEP) VIRGIL C. SUMMER NUCLEAR STATION ILS07759-HD-ND CLASS 1 PIPING SYSTEM FLOW DIAGRAM HYDRO TEST TEMP. 60 'F SCE&G CAD ENHANCED REACTOR & AUXILIARY 26 !7111/ii JMR REVISED PER ECR-50267 MGR AME BUILDING SUMP PUMPS K 25 li/19/97 AVN REVISED PER MRF-21902, MCN-8 GJM LEK U DESIGN ENGINEERING K ~""

24 11/1 /95 JTS REVISED PER MRF-22640 MGR JEW A 9:Alf\\ COlffllfT" V. C. SUMMEFI NUCLEAFI STATION JENKINSVILLE, S. C. MADE CHECKED LE APPFIOVAL 100 145 125 200 30 MIN 160 RWG 23 li/26/'13 DDJ REVISED PER CGSS-93-2241 MGR RSB 1. 2. 3. I#] P511i 'F PSIG "F DlJlATl N UPSET HYDRO BY CHKD REMARKS 28 05/17/1i2! CMS REVISED PER ECR-71356 chk AJL SRF RHM AME I-"' NORMAL r--t-----t---j-------------j-----j----,-::----j t<<l SCALE 27 i3/03/i5 JTS CADD ENHANCED PER ECR-50239 MGR DDJ DESIGN DATA LE D-302-821 28 NO. DATE BY REVISION CK

• BY APPROVAL ORAW!t,C NUMBER SHT, NUMBER REV 1/4 "=1'-0,,

0' 5' 10' 15' 10'}}