ML21209A265

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1 to Updated Final Safety Analysis Report, Chapter 9, Figure 9.2-5 / Drawing D-302-612, Revision 28, Piping System Flow Diagram Component Cooling System Inside Reactor Building
ML21209A265
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 04/30/2021
From:
Dominion Energy South Carolina
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21209A581 List: ... further results
References
21-167
Download: ML21209A265 (1)
v • d • e


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' \--~

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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 "

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

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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

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

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<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"

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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

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

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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

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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.

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INSIDE REACTOR CONTAINMENT L...

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

  • TO BE LINE SPEC 152N UNLESS

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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

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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'

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