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 DATA

• THIS TEMP IS A MAX I MUM EXPECTED FDR q5*F 3" SERVICE WATER TEMP. AND LOSS OF ONE CCW MAX o HEAT EXCHAN G ER DUR IN G PLANT COOL DOWN MODE.

L;./ G PM PSI F REMARKS 6" 100 120 ROh-8 XPS-77A-CC 6" XPS-77C*CC A XPS*78A-CC D-302-852 262 80 145 ETBT-458 LOC.C-7 4

240 80 125  ?;.. 5"11C-CC t' \--~

R0h-t4=

5 CONTAI NMENT l!!"""l--1 START-UP ONLY 150 80 145 Jq5J2-CC\

6 ISOLATION PHASE 7 5 80 145 5 120 "B" SI G NAL I

120 llillil 6z 120 130 120 "'

M q ISi llil 40 80 145 f- - 13 PLACES>

DRAIN,:,

N 11 08 7 70 25 150 PSI "

E-qll-101 DRAI N ..,.

L.:J 6" 3**

14 PLACES> LDC.F-11 __.I RN1-4 l" UJ

___ t,i J UJ ...

MRF-20285 qsasA-tt ROh-q MRF-20285 rT7'1177 i B xPs-200c-cc 8

ROh*l XPS-021illilA-CC

- - ~ 1 5 il 19§ j"X1/2" ITYP. 4 PLACES> RNm*l21bl I" ROh-q RNm-121bl XPS-125C-CC u PS*125B*CC '-....j::\.,it-h u ROh*l q553A-CC RNm-l21bl p.,;3;1."_...,.:--1 xPS-l25A-cc ' ROh-cf MRF-20285 ROh-q 151X 1q643-CC ie' l" XPs-1qqB-CC 1"

REACTOR

---

.....4-1 Ill COOLANT

~

PUMPS 131 'A' lu ] u

-251i13N "RNm-12( e l I"

~

E I" 200PSI

iii" v Tl£-. -IER 47 48 XPS-l24C-CC

.. I... . ...l. XPP-31i1A-RC I1/2" RNg-6 lilt XPP-31i1B-RC 47 48 RN -6 q5q3B-cc I ..

01!_-

~--RN-6 q5q3c-cc C ROh-14 l" C ROh-1" "'9!1!1"".._IFT*7166*HR-CC I" IFT-7132-HR-CC /

l"

., I 0h-)4 ~~-

ROh*llil u F T-7178-HR-CC 'd I L.:J

!:mI:!

u'

/ q579-cc DRAIN l"

ROh-14 RDh-14 150 PSI 3" '

IFT-7158-HR-CC I

1q51q-cc A

DRA I N --I.,.___.

ROh-14 5"

nn .. *

/

15a: ...!!: E FM

~ J_

iii" xu,.i:o ii!

72 a:-

USE NEXT 15-CC 7178 01

~ .. X%"J ROh-14 I.. X1/2* IFT-7172-LR-CC 6" RN *5

...._ _., ITYP. 4 PLCS.

D ITYP.4 PLCS.I ROh-14 D q593-cc ROh-14 ROh-14 u XIL.u 72 IFT-7166-LR-CC 4 IFT*7152*1R)'t r:,

6"

/

q

> if HI FLOW M VENT IFT-7158-LR-CC CLOSE I1/2"

. .A_

@---lss R h- 4 r:6 IFT-7106-LR-CC 7J6 TE TM I- - Clill 1 7160 7160

.-- 1 ROh-2 ROh-15 I Clill I q594c-cc ROh-B /

I L Clill q59qc-cc

<o q5q.Jc-cc e:D i ALARM E-302-673 ROh-2 ROh-2 ROh-15 6 7 E

lilt DEFEAT ITL CS 6

q59.,tA-CC 4; 7 llil 7 q59qB-cc llil 3"

E EXCESS LETDOWN 3"

6" 6 cc cc 1q513 HEAT EXCHAN G ER /

~ .. ROh-14 1'1502-cc .. 3" I" 4

\"SIEM SUFFIX FIRST ICL qsqq ROh-14 1q505-cc ROh-14

~rt=;;?:...~~~--------------... L.:J 1----------,i~-.:.-.!!R:A~1N:.,_....;4~*~*~::::IL~1~%~";__.,:;!:=;:ILL_....,. . .;1~%~*~*_.J VALVE NUMBERIN G \

VENT []-1...""'-"'I I"

1qs1111-cc/

ROl-4 ~ .. 6" 4'

'-*v_E:'-.~-~:~~~:Jl'-f-----D<l-/*~-~-'2.~_c_c__ .;f,\.,__~~-~-i--c*c-....1""":....---*---------~.,;;';,.'---~~ ~5~ ~ ~ c=c~

6" 6"

8" ROh-14 F rnJ l...rJClill IFT-7116-LR-CC F 5

iii" X1/2" I" Cl ', RNn-5 ROe-3 3"

0i_ I (TYP.4 PLCS. I qs00-cc :iii" cBv*--.qnislilflr'-"'cc..-

xP"S- 15-cc _,,,,- -

ROh-1

"' "'...,..-"""",.-, L.:J u

u 3" ROh-1 IFT-7273A-LR-CC ROh-1 q5qq-cc TV L.:.J 2 +ti!

INSIDE x OUTSIDE ROh-14

~

SEE NOTE 4 I 2 C01 IFT-7273A-HR*CC REACTOR REACTOR 1qs21-cc 5 4" ii ROh-1

iii" I Ill CONTAINMENTl CONTAINMENT :E.J ROg-17 IPl-7103A-HR-C

/ h=* 1 4 1 ISi G ' ;::::' q5q1c-cc ..,.R""" f::,,.....,,=-, G XHE-12-WL I Pl-711i13C-HR-CC 1

RNn-4 CIV R0,-6 605-CC Cl01 q5q6A-CC q5q6c-cc

~ ~ ...............

CI V "R-50263 CIV qseq-cc

..AJ,i

~

REACTOR COOLANT TC RO -3 -*-. ROh-14

<o

\ROq-3 L t1/2*tr.-=-.-§l CRAIN TANK r:, ;qsq-cc ROh-1 I1/2.:::-- _,

q510-cc HEAT EXCHANGER 1<1504-CC 12.4 I 12.4HP I L.:J DRAIN NOTES, IEJ 1- (.) 34511 1qs2s-cc t'.jc01 CB

_.,,=R='G"=e'-::*4-=="'-1,.,11 3

468V I Clll 1--i:::::J: 01 -,C,="":':-:-=,---\s RG.. -,4 RPM 4611JV 1""'0Clill I. ALL PIPIN G TO BE ANS SAFETY PP-58A-CC CLASS 2b EXCEPT AS NOTED.

"t' <>

C u

c:- es--!IBC-CC 5 2" :iii.. _. 2:.." :iii" DRAIN--- ORA---

INSIDE REACTOR CONTAINMENT L...

2.ALL NUC SAFETY CLASS PIPIN G OUTSIDE REACTOR f.,2____:

• TO BE LINE SPEC 152N UNLESS

-I1-11 -11*1I*11*11*11 ****11*11* I1*1 11*1I*11*11*11****11*11*11*11*11*1I*11*11*11 _,

H

---

- I -- -- - - - - - - -- --- I CONTAI NMENT 2

COMPONENT COOL IN G u  ;'cc OTHERWISE NOTED.

3. ALL NON-NUC S.C.PIPIN G TO BE H BOOSTER PUMPS 3-1lillilX LI NE SPEC 151X UNLESS NOTED 120 G PM 11Iii" TDH OTHERWISE.

TC RN1-I 3.. RN,-1 4. DUAL ORIFICES - ONE FLOW RESTR ICTIN G

)(

r:, ITL*LO

,.._ R_ E_ s...,s,...u_ RE P _

I-3" 3" /<15<188-cC 1-:-1:-..--II*

THE OTHER BLIND FOR USE IN LEAK TESTIN G ISOLATION VALVE.

- ROh-14 5. ALL STATUS LI G HTS INDICATE BOTH in I _ OPEN"'lfiND CLOSED.UNLESS NOTED OTHERWISE.

qs42-CC 1 I 150 PSI 150 PSI R01-2 150 PSI RN 18-023

qs32-cc ROg-17 ROg-17 ROg-17 THIS IS A I 8° q561-cc q5q5A-CC \_ q5q5B-cc" q5'15c-cc\

NUCLEAR SAFETY RELATED DOCUMENT. NO DEVIATION SHALL BE tl 11 J INITIATED OR PERFORMED WITHOUT PRIOR J RN Q -25 ROh-1 DOCUMENTATION AND WRITTEN APPROVAL q625*CC IPl-7101-HR-CC \

A-6 8" 3" t---1 FSAR Figure 9.2-5

-611 8 DRAWING LEGIBILITY cc 8" ROh-1 SOOTH CMOl.11111 ELECTRIC

• GAS CORIO' IFS-7llillilB-LR-CC 3" CLASS 1

...,"r"i"'--. ROh-1 I FS-7llillilB-HR-CC VIRGIL C, SUl4ER IULEM STATI PIPING SYSTEM FLOW DIAGR COI.FONENT COOLflG SYSTEM BPh- I HYDRO TEMP - COLO WATER IFS-711illilA-LR-CC

--' INSIDE REACTOR 8U1LD111G

,iia>- '-......_ R O h -) 24 5/!i/02 RHM REVISED PER ECR-50263 DDJ LMS IFS-711illilA-HR-CC DESIGN ENGINEERING 6-47 1!111 23 6/2l/99 DDJ REVISED PER CGSS-99-0332 MGR ALB K K IF;45~i;,;1511~i-;;:;.i:;~i;;,;:.,e.-3~~;;;i...--1--------I 13 ESSENTIAL 28 6/29/18 JMR 27 04/02/12 DDJ REVISED PER ECR-50239 REVISED PER ETBT*458 DKC MGR AL GFK CHE:CICED LE #IPROVH.

V. C. SU.a.ER NUCLEAR STATION .ENCINSVLLE S. C.

A.V.N. M.G.R. R.S.B.

1.

26 04/14/09 RHM REVISED PER ECR-71263 MGR RHM REMARKS 25 2/IJ/08 JMR REVISED PER ECR-50239 MGR DJ DESIGN DATA

......... D-302-612 8 REVISION LE NO. DATE ev CKD.BY APPROVAL DRMIING PUIEIIER SHT. NLIIBER REV 1/4"= 1'-0" 0' 5' 10' 15' 20'