ML22194A157

2 to Updated Final Safety Analysis Report, Figure 9.2-5, Drawing D-302-612, Rev. 28, System Flow Diagram Component Cooling System Inside Reactor Building

ML22194A157
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: ML22194A157 (1)

Text

14 13 12 11 1111 q 8 7 6 5 4 J 2 I SYSTEM DA TA

• THIS TEMP IS A MAXIMUM EXPECTED FDR q5*F 3" MAX o SERV ICE WATER TEMP. AND LOSS OF ONE CCW L;./ GPM PSI F REMARKS HEA T EXCHAN GER DUR IN G PLAN T COOL DOWN MODE. 6"

100 120 ROh-8 XPS-77A-CC 6" XPS-77C*CC A 4 262 80 145 R0h-t4= XPS*78A-CC D-302-852 ETBT-458 5 240 80 125 START-UP ONLY Jq5J2-CC\\ ?;.. LOC.C-7 5"11C-CC 6 150 80 145 CONTA INMENT l!!"""l--1 7 5 80 145 ISOLA TION PHASE t' \\--~ I 5 120 llillil 120 "B" SI GNAL 6z M

q llil 120 130 120 DRAIN,:, ISi "'

40 80 145 f--13 PLACES> 150 PSI " N 11 08 7 70 25 E-qll-101 L.:J 6" 3** 14 PLACES> LDC. F-11 l".. DRA IN..,.

___ __.I RN1-4 t,i J UJ... UJ 8 MRF-20285 qsasA-tt ROh-q MRF-20285 rT7'1177 i B j"X1/2" ITYP. 4 PLACES> ROh*l < XPS-021illilA-CC --~15il 19§ xPs-200c-cc RNm-l21bl p.,;3;1."_...,.:--1 ROh-q RNm-121bl XPS-125C-CC RNm*l21bl I" u u ROh*l xPS-l25A-cc ' q553A-CC ROh-q '

1" 1q643-CC ----ROh-cf PS*125B*CC '-....j::\\.,it-h MRF-20285 151X ie REACTOR..... 4-1 l" XPs-1qqB-CC Ill '

COOLANT lu ] u ~

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6 7 q5q.Jc-cc e:D i ALARM L E-302-673 ROh-2 ROh-2 ROh-15 lilt DE FEAT ITL CS q59.,tA-CC q59qB-cc 3" E 6" EXCESS LETDOWN ~.. ROh-14 6 7.. llil 6 7 llil 3" E cc 1q513 HEAT EXCHAN GER / 1'1502-cc 4;.. 3".. I" 4 cc qsqq ROh-14 ROh-14 L.:J

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1qs21-cc I 5 4".. 2 ROh-1 ~ ROh-1 OUTSIDE INSIDE x SEE NOTE 4 :iii" I IPl-7103A-HR-C Ill ' C01 IF T-7273A-HR*CC REACTOR REAC TOR ii

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CONTAINMENT 2".. DRAIN --- L... "t' 2:.."

-I 1-11 -11*1 I *11*11*11 **** 11*11* I 1*1 ---- - I -- -- - - - - - - -- --- I 11*1I*11*11*11 **** 11*11* 11*11*11*1I*11*11*11 _, 2. ALL NUC SA FETY CLASS PIPIN G OUTSIDE REACTOR 2 f.,2 __ __:* TO BE LINE SPEC 152N UNLESS H CONTA INMENT COMPONENT COOL ING u ;'cc OTHERWISE NOTED. H BOOSTER PUMPS 3.ALL NON-NUC S.C. PIPIN G TO BEL INE SPEC 151X UNLESS NOTED 3-1 lillilX OTHERW ISE.

120 GPM 11 Iii" T DH RN1-I 4. DUAL ORIFICES -ONE FLOW RESTR ICTI NG TC r:, 3" 3" /<15<188-cC 3.. RN,-1 THE OT HER BLIND FOR USE IN LEAK TES TIN G

)( ITL*LO I-in,.._P_R_Es...,s,...u_R_E _. -- -& 1-:-1:-.. --II* ISOLA TION VALVE.

- ROh-14 I I _ 5. ALL STATUS LI GHTS INDICATE BOTH qs42-CC 1 OPEN"'lfiND CLOSED.UNLESS NOTED OTHERWISE.

R01-2 150 PSI 150 PSI 150 PSI RN 18-023

qs32-cc ROg-17 THIS IS A I tl 8° 11 ROg-17 ROg-17 NUCLEAR SAFETY RELATED q561-cc q5q5A-CC \\_ q5q5B-cc" q5'15c-cc\\ DOCUMENT. NO DEVIATION SHALL BE J INITIATED OR PERFORMED WITHOUT PRIOR DOCUMENTATION AND WRITTEN APPROVAL J RN -25 Q ROh-1 q625*CC IPl-7101-HR-CC \\

A-6 3" t---1 FSAR Figure 9.2-5

-611 8" 8" ROh-1 8 DRAWING LEGIBILITY cc IFS-7llillilB-LR-CC 3" CLASS 1 SOOTH CMOl.11111 ELECTRIC

• GAS CORIO'

..., "r"i"'--. ROh-1 VIRGIL C, SUl4ER IULEM STATI IFS-7llillilB-HR-CC BP I h-PIPING SYSTEM FLOW DIAGR HYDRO TEMP -COLO WATER IFS-711illilA-LR-CC COI.FONENT COOLflG SYST EM 6-47 1!111,iia>---' '-......_ ROh-) 24 5/!i/02 RHM REVISED PER ECR-50263 DDJ LMS INSIDE REACTOR 8U1LD111G K IF;45~i;,;1511~i-;;

;.i:;~i;;,;:.,e.-3~~;;;i...--1--------I IFS-711illilA-HR-CC 23 6/2l/99 DDJ REVISED PER CGSS-99-0332 MGR ALB DESIGN ENGINEERING K 13 28 6/29/18 JMR REVISED PER ETBT*458 DKC AL V. C. SU.a.ER NUCLEAR STATION.ENCINSVLLE S. C. CHE:CICED LE #IPROVH.

ESSENTIAL 27 04/02/12 DDJ REVISED PER ECR-50239 MGR GFK 1. A.V.N. M.G.R. R.S.B.

REMARKS 26 04/14/09 RHM REVISED PER ECR-71263 MGR RHM 25 2/IJ/08 JMR REVISED PER ECR-50239 MGR DJ......... D-302-612 8 DESIGN DATA LE NO. DATE ev REVISION CKD.BY APPROVAL DRMIING PUIEIIER SHT. NLIIBER REV 1/4"= 1'-0" 0' 5' 10' 15' 20'