ML21209A233

1 to Updated Final Safety Analysis Report, Chapter 10, Figure 10.4-13, Piping System Flow Diagram Steam Generator Blowdown

ML21209A233
Person / Time
Site:	Summer
Issue date:	04/30/2021
From:	Dominion Energy South Carolina
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21209A581	List: ML21209A111 ML21209A112 ML21209A113 ML21209A114 ML21209A115 ML21209A116 ML21209A117 ML21209A118 ML21209A119 ML21209A120 ML21209A121 ML21209A122 ML21209A123 ML21209A124 ML21209A125 ML21209A126 ML21209A127 ML21209A128 ML21209A129 ML21209A130 ML21209A131 ML21209A132 ML21209A133 ML21209A134 ML21209A135 ML21209A136 ML21209A137 ML21209A138 ML21209A139 ML21209A140 ML21209A141 ML21209A142 ML21209A144 ML21209A145 ML21209A146 ML21209A147 ML21209A148 ML21209A149 ML21209A150 ML21209A151 ML21209A152 ML21209A153 ML21209A155 ML21209A156 ML21209A157 ML21209A158 ML21209A159 ML21209A160 ML21209A161 ML21209A162 ... further results
References
21-167
Download: ML21209A233 (1)

Text

14 13 12 11 10 8 7 6 5 4 3 2 1 SYSTEM DATA J-14 ISOLATION VALVES CLOSE SIGNALS HIGH RADIATION SIGNAL FROM E-4

[(> GPM PSJG ° F REMARKS ~ SIX PLACES __

• NOTE:

1. CONTAINMENT !SOLA TION SIGNAL PHASE 'A'

2. START OF EMERGENCY F.W. SYSTEM

---

<"M""s=--- -011

--~

I RM RM-L3 CLOSES VALVE 524 &

OPENS VALVES 525 & 541.

HIGH RAO!A TION SIGNAL FROM RM-Ll0 CLOSES VALVE 547 I

A 1 111 ll'J93 557 MAX.BO RATE A MANUAL OVERRIDE IS PROVIDED A 2 1 13111 12111 SAMPLE FLOW FOR SIGNAL (*) ABOVE. ~ 3 PLACES 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 STEAM GENERATOR B

NEXT LETTER (j_)

STEAM GENERATOR WET LAYUP PURIFIER SKID

/

RGL-1 XPT-9-BD 7 ---;

XSG-2A-RC RGH-2 cqn 4

3 4"

B XHE-13A-BD2 "

RGL-1 I

I 1/4'f VEN/' 10534A-BD

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/ XFL-5045A-B0 2"

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RGL-1 2" I

/ 4716-HR-BD / RGL-1 1/2" / RGL-1 ROb-45 , \

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, - - .. I C ~ RGL-1 DRAIN ' RGh-2 C 2" RGL-1 - RGL-1 RO -15 I 519A-BD ROb-45 10512-BD

---

~ TURBINE 502A-BD 1/4" / 10533-BD \ 10532-80 2"

BLDG.

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100 GPM PUMP

/ XPP-501116-BD VENT XPS-5032-BD

/

RGL-1 10534B-BD 2"

~BY SCE&G RGL-1 530A-BO

/ XFL-5111458-80 2" 2"

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

~~

-102

~

10529B-B0 DRAIN 0 151X ROb-9 CO lPT-4707A-HR-BD RGL-1 / I RGL-1 4717-HR-BD

• ROb-64 RGH-2 G-4 ROb-9 NOTES:

)k I

RGL-1 10527-BD RGL-1 / 537-BD '-- XHE-13B-BDI 1 2 529A-BD

'1 XSG-2B-RC -102 1. ALARMS LOCATED ON NUCLEAR SLOWDOWN PROCESSING 1111528-BD \ RGL-1 IFM-4 719-BD 5268-BO 151X PANEL (XPN111029) WITH ONE COMMON ALARM ON THE

'ii.(' , 10531-BD 1 2" ' co 3"

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

• 1 i 0

211 G-13 RGH-2 XHE-138-B02 MAIN CONTROL BOARD.

.- .. - 3'1 ~~524~BD *. _3"]: . _1:'. _:. - . RAI_N_ - .. ~MPLE. ~---:._::-c1/4~'~~:--.,10"'~°'~"'~--,-k'-'o t--~--1)(1-- -771 ss

2. QUALITY RELATED PER TRP-13, SECTION 9.

E i~ l:~i-,,1,_ _3...,"-~--11 F-13

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---~0@0---~ 2" 2 11 1MB  ! 0MB ( I 14 ) 3" PIPING CONTROLLED FOR BREAK EUMINA TIDN ANALYSIS.

3. HOSE CONNECTION AVAILABLE TO SATISFY E

XPS-511130-BD ~

XPS-511!31-BD VENT 902X 151X OPERA TING LICENSE CONDITION 2.C.(34).

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

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/ 2A NOTE 2 I-BO m 536B-B0 !8 ROb-28 BY SCE8,G

/ 51/J4A-BD 5278-BD XST-96B-BD STEAM MRF-2111613 GENERATOR L L.C. /

XVG-1771-BD

./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

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SET Ill 135'F 1 '(1/ 2 ,,

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3/4, s DRAIN L!'.l 3/4" VENT 509-BD ROb-45

/ ss 01X 902X DRAIN -4 7 - - THIS IS A

~ 903R 902X /; 10522-BD ROb-64 \

NUCLEAR SAFETY RELATED

© VENT ROo-15 RMo-21 10511-BD E-13 r., 3/4 527C-BD 2" 529C-BD / DOCUMENT. NO DEVIATION SHALL BE J 1/2" f---, 806-005 ')-.L..[)!(J-,--f--.J--(}:--;

, I V-4 I -

~~ 902X 151X G,,.,.,._..__...1.~-,;"'--"'---fiB,..----I INITIATED OR PERFORMED WITHOUT PRIOR J

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'-----l 3 15::1:-;{X C ROb-9 MRF-21309 2"-151X RNo-44 519C-BD CO 151X DOCUMENTATION AND WRITTEN APPROVAL

~

L.C. 525-80 512-B0 FSAR Figure 10.4-13

\ ROb-29 511-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 SCE&G CAD ENHANCED PIPING SYSTEM FLOW DIAGRAM 4 14"' 125 40 125 <1% 60 JJW PLS STEAM GENERATOR SLOWDOWN 3 1185 125 1304 600 <1% 1480 EJA KL 2 1185 125 1304 600 <lY. 1480 EJA KL 27 7/B/03 JMR CADD ENHANCED PER ECR-50239 MGR DDJ K I 1185 600 1304 600 <1% 148111 EJA KL 26 11/13/97 AVN REVISED PER CGSS-97-0579 LEK MGR 6 SCE&G DESIGN ENGINEERING K OF 31 12/10/07 RHM REVISED PER ECR 50692A MGR RAT V. C. SUMMER NUCLEAR STATION JENl<JNSVILLE, S, C.

PSIG OF A SCANA COMPMY PSIG DURA.

~ ,.

M/>OE CHECKED LE APPROVAL HY* BY CHKO REMARKS 30 6/6/06 RHM REVISED PER ECR-70878 MGR CCB 1. 2.

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

DESIGN DATA NO SCALE D-302-781 NO. DATE BY REVISION LE CKD. BY APPROVAL 31 ORAIIINO NUMBER 1/4 11 ::: 1'*0 11 0' 1vl' 15' 20'