ML22194A234

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2 to Updated Final Safety Analysis Report, Figure 9.3-3A, Rev. 13, System Flow Diagram Instrument Air Backup
ML22194A234
Person / Time
Site: Summer 
Issue date: 06/27/2022
From:
Dominion Energy South Carolina
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22194A236 List: ... further results
References
22-179
Download: ML22194A234 (1)


Text

14 13 12 SYSTEM DATA

[(> SCFM PSIG OF BY REMARKS A

1 636 120 100 JN 8

C D

E IA 22670 22671 IA 2672 2691 SYSTEM SUFFIX FIRST NO.

LAST NO.

VALVE NUMBERING F

G H

J K

1 120 110 135 150 (11/.

170 JN PNEUM. TEST PSIG °F PSIG °F DURA. HY-NORMAL UPSET DRG BY CHKD REMARKS 11 SCE&G 2681M-IA R.C. PUMP 3/4' SEAL CAVITY LOOP 1C1

~

2661N-IA MANWAY ACCESS PLATF LOOP 'C' l"

OUTSIDE SECOt-lDARY SHIELD WALL LOOP 'C' 10 EQUIP, HATCH SCE&G

/

26811-IA SCE&G 2681J-IA \

3/4' REFUELING Jo-l~-::i,,;;;..a.--

CANAL

\

SCE&G 26B!L-IA 2'

1" OUTSIDE SECONDARY

!ELD WALL LOOP 'B' G

2681K-IA UPPER PRESSURIZER CUBICLE

/

~

2661E-IA R.C. PUMP SEAL CAVITY LOOP '8' 3/4" B

SCE&G

/

268JH-IA 2'

1" 7

SCE&G

/26SIG-IA t-.,.i~-c LOOP 'B' MANWAY ACCESS PLATF 3/4" 3/4" SCE&G

~

RC PUMP SEAL CAVITY LODP 'A' 26810-IA LOWER PRESSURIZER CUBICLE 2661C-IA OUTSIDE SECONDARY SHIELD \/ALL LOOP 1A1 SCE&G 26818-IA I REACTOR VESSEL HEADSTAND 2"

SCE&G

/

2681F-[A 3/4" SCE&G

~

MAN\IAY ACCESS IRC PLA TF. LOOP 'A' 6

5 2'

2" 4

SCE&G

/

2682-IA ROb-1 2" I 2683-IA ROp-37 2ss0-IA \

~ ;n.c. ~

3/4" c1v**-----f' L.C.

ORC LOCAL &

~

XAC-12-IA SCE&G 2690C-IA EL. 401'-0"- e SCE&G

/

26908-IA EL. 416'-0"--e SCE&G

/

2690A-IA L.C.

LO c1v.,. ______ -~

ROp-37

/

~

_2_6_7_9-IA-~

J T.C.!fl AUX. BLDG. AND

,*,~

BREATHING AIR INTERMEDIATE BLDG.~

3/4"~

ROb-1 2"-155X 2"-155X 2"-155X 2"-l55X 2"

2684-IA EL. 378'-0" -G---"*-------~.,:;;;;;;:;,. ___ J..:;...~;;.;._ ______.1,..;;;_.;,;.,;_ __ ~_,~::.,.------,------_;~.,:.-1 XAC-12-TPl-IA 3/4"-151X

"' ROb-1 2687-IA RAIN 151X 2'-155X 2"-155X EL. 440'-0" --~..iM-1 EL. 416'-0" - ~~M~

SCE&G

\

\

SCE&G 2689B-IA 2669A-IA EL. 440'-0"--e""""M-I SCE&G

\

2"-155X 26900-IA EL. 489'-6" --i;-M-------J SCE&G\

2690F-IA 2"-155X EL. 467'-0"--G'--.... I--~

ROb-1 22670-IA

\3/4"x1/4"

\

RGd-6 XTK-131-IA

,,--'-...!2~"'..t,_~1 1/4~* '_' j RGd-G 22671-IA 3-"

6 //

---1--....~

/

RNb-20 2672-IA AIR RECEIVER 1"-151X

~

2685-IA DRAIN SCE&G\

2690E-IA RNb-20

/

2676-IA RNb-20

NOTES, SCE&G 2878-IA LW DRAIN ROb-1 2686-IA ROb-50 2677-IA I.COMPONENTS CLASSIFIED 2"

2" X -

ID -

3" AS QR PER TRP 28 I.A.

C-1

-271 I.A.

13 2/9104 TGB 12 4/23103 JMR 11 10111199 JMR 10 01/0819!

JTS 9

09/17/95 AVN 8

11115194 JHM 7

10* 13-93 SRM 3

!RC ORC 2

DRAWING LEGIBILITY CLASS 1 SCE&G CAD ENHANCED REVISED PER ECR-70483 MGR AME GADD ENHANCED PER ECR-50239 MGR DDJ REVISED PER CGSS-99-0501 MGR DKW REVISED PER CGSS-97-0569 LEK MGR RE~SED PER MRc-22640 MGR JEW REVISED BORDER PER CGSS-94-1680 RHM MGR REVISED PER MRF-21475 MGR RLJ LE 1

THIS IS A NUCLEAR SAFETY RC:LATED DOCUMENT. NO DEVIATION SHALL BE INITIATED OR PERFORMED WITHOcT PRIOR DOCUME~T ATION AND WRITTEN Af'PROV />L PIPING FSAR Figure 9,3-3A SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION SYSTEM FLOW DIAGRAM INSTRUMENT AIR BACKUP

~

DESIGN ENGINEERING A sc..w. cowPNf!'

V. C, SUMMER NUCLEAR STATION JEN1<1NSVILLE S. C, l.1ADE CHECKED LE APPROVAL 1,

SRM MGR

3.

RLJ MO SCALt D-302-274 13 A

B C

D E

F G

H J

K -

0 8

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t'-

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~OR!!!**!2;1N~O..!"~""~'E;:!!R ___

i.;s~H"'T,,:!!SU!!,!MB!!!E.!!.Rl!R~EV4-NN, I 1/4":::1' 0/,

0' 5'

10' 15' 20' c;".l DESIGN DATA NO, DATE BY REVISION CKD. BY APPROVAi...

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