ML22194A359

2 to Updated Final Safety Analysis Report, Figure 10.4-13, System Flow Diagram Steam Generator Blowdown

ML22194A359
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: ML22194A359 (1)

Text

14 13 12 11 10 8 7 6 5 4 3 2 1

SYSTEM DATA ISOLATION VALVES CLOSE SIGNALS J-14

1. CONTAINMENT !SOLA TION SIGNAL PHASE 'A' E-4 HIGH RADIATION SIGNAL FROM HIGH RAO!A TION SIGNAL FROM

~ SIX PLACES __

• 2. START OF EMERGENCY F.W. SYSTEM :--~ RM-L3 CLOSES VALVE 524 & OPENS VALVES 525 & 541. RM-Ll0 CLOSES VALVE 547

[(> GPM PSJG ° F REMARKS NOTE: ----< -011 "M""s=--- I RM 1 111 ll'J93 557 MAX.BO RATE A MANUAL OVERRIDE IS PROVIDED I A 2 1 13111 12111 SAMPLE FLOW FOR SIGNAL (*) ABOVE. ~3 PLACES A 3 84 1080 120 MAX.BO RATE SWITCHES FOR THESE VALVES ARE PROVIDED ON 4 250 40 120 MAX.BO RATE MAIN CONTROL BO <XCP-6112).

A COMMON SWITCH IS USED FOR "B" TRAIN VALVES.

stfl'EY Cl.ASS VERIFJCATH>>JS allGINATED BY I EJA 2-12-74 RE\\IIEIIED BY I RHK 2-12-74 IRC ORC GENERATOR STEAM

4" B NEXT LETTER (j_) STEAM GENERATOR WET 7 LAYUP PURIFIER SKID 4 B 3

RGL-1 XSG-2A-RC cqn

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RGL-1 VEN/' 10534A-BD I ------------- I 1/4'f RGL-1 I 4 / XFL-5045A-B0 I 2" !MB ! 0MB I C@:]1i,-,,---1 F i--ll)§l'.J;,....,--, 2" N2 PURGING\\ I RGL-1 I

/ 4716-HR-BD / RGL-1 1/2" / RGL-1 I 10525A-BD s 10526A-BD 1111513-D r., ROb-45, \\ I C 1/2", - -.. I C

~ RGL-1 DRAIN ' RGh-2 RGL-1 - RGL-1 RO -15 I 519A-BD ROb-45 -----~ TURBINE 2" 1/4" / 10533-BD 502A-BD 10512-BD BLDG.

\\ 10532-80 2" TS Q) ~I SUMP 1-'-ll~f-SAMPLE 2" Y---:---r--.:;;,..-,!~s*- -t---, 2 " ~-<4706A - - - - - A RGL-1 4" BY SCE& NOTE 1

/ XPP-501116-BD XPS-5032-BD RGI -l ~

100 GPM VENT RGL-1 PUMP / 10534B-BD 2" RGL-1 ~BY SCE&G 530A-BO ----@

2" / XFL-5111458-80 2" D C@:]11o------1 F o D 3" ----------- / RGL-1 STEAM 1" 2" 4715-HR-BD 10526B-BD 1/2"' RGL-1 10525B-BD / RGL-1 T

~ GENERATOR 151X -102 10529B-B0 DRAIN 0 ROb-9 ~~

CO lPT-4707A-HR-BD RGL-1 4717-HR-BD

• RGL-1 / I ROb-64 RGH-2 G-4 ROb-9 NOTES:

RGL-1 10527-BD RGL-1 / )k '1 XSG-2B-RC 537-BD '-- XHE-13B-BDI 1 2 -102 529A-BD 1. ALARMS LOCATED ON NUCLEAR SLOWDOWN PROCESSING 1111528-BD \\ RGL-1 IFM-4 719-BD 5268-BO 151X co PANEL (XPN111029) WITH ONE COMMON ALARM ON THE

'ii.(', 10531-BD 1 2" ' RGH-2 3" MAIN CONTROL BOARD.

,1::5," RGL-1 2 'r

• 1 i 0 t--~--1)(1-- -771 211 G-13 I XHE-138-B02

. -.. - 3'1 ~~524~BD *. _3"]:. _1:'. _:. -. RAI_N_ -.. ~MPLE. ~---:._::-c1/4~'~~:--.,10"'~°'~"'~--,-k'-'o ss 2. QUALITY RELATED PER TRP-13, SECTION 9.

PIPING CONTROLLED FOR BREAK EUMINA TIDN E i l: F-13 ---~0@0---~ 2" 2 11 ANALYSIS. E 1MB ! 0MB ( I 14 ) 3" 3. HOSE CONNECTION AVAILABLE TO SATISFY

~ ~i-,,1, __ 3...,"-~--11 -E0~5) !,, OPERA TING LICENSE CONDITION 2.C.(34).

XPS-511130-BD ~, "' 902X 151X XPS-511!31-BD VENT r::,

,* -.. I I IFT-470 B-HR2-BD ROb-9 ROb-9 10500-BD 2" 2"

3" 3" 903R PRT-RNn-63 503B-BD ~rtr.:r~'4;.__" J., 1" \\ R0b-64 F 2 L 3" 528B-BO F

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'-[;"(1--1 -771 DRAIN VE'NT ~

2A NOTE 2 -45 S - 2" ROb-28 ROo-15 / ss I-BO m 536B-B0 !8

/ 51/J4A-BD 5278-BD BY SCE8,G XST-96B-BD GENERATOR STEAM L XVG-1771-BD MRF-2111613 L.C. /

./L-'"----3/4" BODY VENT 3 "

G XSG-2C-RC RO -15 RGH-2 I 2 "-. MRF-20613 G 526C-BD ' ' XHE-13C-BDI XVG-1772-BD

. HI -TEMP CLQSE ~ NOTE 1 '

SET Ill 135'F 1 '(1/ 2,, H-13 ! "-'~

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" IFT-4 702C*HR2-BD 3/4" RDb-9 2" *----- - - - *1 ROb-'l b-9~ IPT-471117C-HR-BD 4 X PEN. IFT-4702C-HR1-BD 0503-BD

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• FE 4702C 528C-BO X L!'.l LD I" H-13 ~~=~"t:~l"""~-...,~r _ ~--;- ~ ~ s 3/4, 3/4" LO \\ RNc-12 155X 151X VENT

- 509-BD '-!;lll(l"'-1 -771 2A NOTE 2 "'-' 105 !1!1-BD c,, DRAIN

/ ss 01X 902X DRAIN -4 7 - -ROb-45 THIS IS A VENT ~ ROo-15 903R 902X /; 10522-BD ROb-64 \\ NUCLEAR SAFETY RELATED E-13 r., 3/4 527C-BD RMo-21 10511-BD 529C-BD / DOCUMENT. NO DEVIATION SHALL BE J © 1/2", I V-4 I - 902X 151X 2" G,,.,.,._..__...1.~-,;"'--"'---fiB,..----I INITIATED OR PERFORMED WITHOUT PRIOR J

'-----l 3 f---, 806-005 ')-.L..[)!(J-,--f--.J--(}:--;15::1:-;{X C ROb-9 MRF-21309 519C-BD ~~ ~ 2"-151X RNo-44 CO 151X L.C. 525-80 DOCUMENTATION AND WRITTEN APPROVAL

~ 512-B0 \\ ROb-29 FSAR Figure 10.4-13 511-B0 MRF-20613 /

XVG-177111-BD SOUTH CAROLINA ELECTRIC & GAS COMPANY DRAWING LEGIBILITY HYDROSTATIC TEST TEMP. TO BE 60' CLASS 1 VIRGIL C. SUMMER NUCLEAR STATION 4 3 4 14"' 125 40 125 <1% 60 JJW PLS SCE&G CAD ENHANCED PIPING SYSTEM FLOW DIAGRAM 3 1185 125 1304 600 <1% 1480 EJA KL STEAM GENERATOR SLOWDOWN 2 1185 125 1304 600 <lY. 1480 EJA KL 27 7/B/03 JMR CADD ENHANCED PER ECR-50239 MGR DDJ 6 DESIGN ENGINEERING K I 1185 600 1304 600 <1% 148111 EJA KL 26 11/13/97 AVN REVISED PER CGSS-97-0579 LEK MGR SCE&G K PSIG OF PSIG OF DURA. HY* BY CHKO REMARKS 31 12/10/07 RHM REVISED PER ECR 50692A MGR RAT A SCANA COMPMY V. C. SUMMER NUCLEAR STATION JENl<JNSVILLE, S, C.

30 6/6/06 RHM REVISED PER ECR-70878 MGR CCB 1. M/>OE CHECKED LE APPROVAL

2. DCW,. PJS

~ NORMAL UPSET ORO 29 04125/06 JTS REVISED PER ECR-70799 MGR LHF TAK 28 7/13/04 DDJ REVISED PER ECR-70481 MGR CCB "~

DESIGN DATA LE NO SCALE D-302-781 31 NO. DATE BY REVISION CKD. BY APPROVAL ORAIIINO NUMBER 1/411 ::: 1'*0 11 0' 1 vl' 15' 20'