ML22194A231

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2 to Updated Final Safety Analysis Report, Figure 5.5-4, Piping System Flow Diagram Residual Heat Removal
ML22194A231
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
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: ML22194A231 (1)


Text

        • SOOfllSPECaasssssaasssssaasssssaasssss ssUSERNAtEss ssss&SYTIME&sssss 17 16 15 14 13 12 II 10 9 8 7 6 5 4 3 2 FOY 605A A R A ccws D-302-611 LOC, C*B V

RH-7A XHE5A-RH ITEM; RESIDUAL HEAT AHRS EXCHANGER NO. I TW-606A SAFETY CLASS TUBES 2A SHELL 2B B B 2

J 8*RH*60IR j"" - - - - + TR-604B I I I ~ I

~t1/4, y~R L

_..JO 628A REF, S ccws D-302-611 LOC.C-4 I V

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10*RH*601R C TE I RH-7B XHE-~ C l0*RH*601R 606B RESIDUAL HEAT TW-606B \l~.::itL.J~.....---",,,,+=;:::--'=~:="rilL ITEM: EXCHANGER N0.2

0--@c01 3/4" AHRS SAFETY CLASS TUBES 2A SHELL 2B I 3/4*RH*60IR H PLUGGED ,.. _...., T0631A I LO J XVA00005B*RH \ 1 REF.S I

ij

- TO VALVE , - ..... ANNUN G I TO VALVE I FCV*605B I REF C FCV*602B 8*RH*60IR I ~ O 3/4-RH*604X

@CY LOC. 0-8 ' LOC. E-12 NUC, DRAINS TO WHY B~TIV

/ D-302-822 I 605B R F0627A REF.S L.:.J LCX::. H*S V ~LIB~

+

D i

Y"-L-~

TW-604B 1 D

..,TOS30A

~- REF,S TY I 606B I I

--~".:- -t------------------------------------.. -.-~

IRC NOT~~

RH-9B A AN~Lc....,_~v, ---@B @'

~

) 3/4-RH*601R I

TY*606A 1

M l*FCV-602B REF. C 600B R 60 0B R 600B 1W-604A INST.

NOTE SEE 14 ~ 2 I .... - - J*QM78FNA ~ - - - - ~ 1 R BUS II

~ - - - - ~ 0*312*822 Pl.JC.DRAINS TO WHY I _- ____ L _ _ ~ TR 1-8708B LOC, l(*!i 604A 3*RV76LWB '--------',RH*l2 3/4" RH-10 E I - 4 3/4" V ccws l0*RH*601R E RCOT t- RH*l6B C

LOC. E-8 8708-8 CBV XPS-152A-RH XPS*l52B*RH D-302-614 LOC. H-6 FLUSHING CONNECTION NOTE 15 OTE 8 D-302-825 LOC. G-11 3/4*)MB 0MB I

.A._v 3*RH*60IR 1*8733B 2 A LC NOTE 3 NOTE 3 CO ~ RH-14 3/4*T78 NOTES1

~

D-302-825 RCS M LDC G-11 V lt-.e----, I, THIS DRAWING IS BASED UP WG. 114E074, REVISION 12 !"BASE ORAWING'I OF WESTINGHOUSE ELECTRIC CORPORATION, NUCLEAR ENERGY SYSTEMS NOTE E-302-601 PITTSBURGH,PA,WHO IS SOLELY RESPONSIBLE FOR THE ACCURACY OR LOC,C-6 I THE RELIABILITY OF THE DESIGN INFORMATION SET FORTH IN THE 1-8702B BASE DRAWING, 12-GMBBSEH

2. FOR ALPHA REFERENCES, SEE WG. E-302-002, FLOW DIAGRAM LEGEND.

~

1-87300 F 3/4*T78 3/4"X\!r" F

3. VALVE INTERLOCKED WITH REACTOR COOLANT SYSTEM PRESSURE SIGNAL, 4, FOR CONVENTIONAL PIPING SPECIFICATIONS, SEE GAi SPECIFICATION SP-329-4461-00, PAGE 29, !WESTINGHOUSE PIPE CLASS CONVERSION TO

~

ENGINEER'S PIPE LINE SPECIFICATOINI,

>>--"3'-/4'-*-'-'R:.;_H*_,6:::0.:,IR:.... 5.

3/4*RH*601R

6. p !WITH LETTER OESIGNATIONI INDICATES THERMAL TRANSIENT DESIGN FLAG, e

FLUSHING ECR51723 CONNECTION NOTE 15 7, LOCATE VALVE OUTSIDE OF SHIELD WALL, SAMPLE LINE MUST BE AT A XVAl874lll-RH 1-87310 3/4"xY.,** 10*RH*601R LOWER ELEVATION THAN RHR PIPE TO ALLOW GRAVITY FLOW.

1MB 0MB 3/4*T78 N

. SEE HI - . ~

ANNUN REF.C 600'Y/ - - ~

HR 600A B ~I 600A NOTE 8 LC . . / 8, LOCATE VALVE ABOVE RESIDUAL HEAT REMOVAL PUMP SHIELDING.

~

NOTE 14 ECR50723 1-87340 POY 9, TEMPORARY STRAINER IS PLACED IN SPOOL PIECE DURING INITIAL FLUSHING No 1*8708A .,.- XPS5036 3/4-T78 OPERATIONS. STRAINER MUST BE REMOVED BEFORE PLANT START UP. STRAINER

""" L----'-- 600A -

u,o.

U<">U 3*RV76LWB Pl AND SPOOL PIECE SUPPLIED BY OTHERS, 3/4" CAPPED LINE IS CONNECTED TO G we~ B708A PRESSURE GAUGE DURING INITIAL FLUSHING. G Jc~v 1/2*2505X 10.

3/4*RH*60JR NUC. DRAINS TO RC WHT 0-302-822

~

D E-302*602 II. PROVIDE 'II," ID FLOW RESTRICTOR PER NOTE 4, SEE WG. E-302*002, FLOW 2-82 1*8733A LDC. J-6 LOC. E-8 DIAGRAM LEGEND.

  • E*S NOT NOTE 13 3/4-T78 3/4* 12, LIR-1330 & LIR-1331 ARE ONLY USED DURING MID-LOOP INON POWER OPERATIONI, RCS r--..--1" *RH*60IR 13. THIS FLANGE HAS BEEN DRILLED AND TAPPED TO ACCEPT A 'II," COMPRESSION E-302-601 FITTING TO FACILITATE LLRT WORK, THE FITTING SHALL BE CAPPED AT OTHER TIMES.

3/4-RH*601R LOC.C-11 14, PIPE IS QUALITY RELATED 'RELIEF ANO SAFETY VALVE DISCHARGE' PIPING PER TRP-13, 725A T78 15, THIS FLANGE HAS BEEN DRILLED AND TAPPED TO ACCEPT A 3/4" COMPRESSION FITTING TO FACILITATE DRAIN. THE FITTING SHALL BE CAPPED AT OTHER TIMES.

NOTE 7 H

~ I 18700-RH H

,- - ,17 IM I -I(

- -t.,~ I LOCAL SAMPLE 3/4-RH-2501R

,- - ,17 IM I -I( SIS ESSENTIAL

--£.~ E-302*693 LDC. E*6 I

SIS E-302-693 LOC.J-11 SIS THIS IS A E-302-693 IRC ORC LDC. G-6 NUCLEAR SAFETY RELATED SIS DOCUMENT. NO OEVIATION SHALL BE E-302-693 INITIATEO OR PERFORMEO WITHOUT PRIOR J LOC, J-11 OOCUMENTATION ANO WRITTEN APPROVAL J FSAR Figure 5.5-4 SOUTH CARlllNA ELECTRIC & GAS COMPANY DRAWING LEGIBILITY CLASS I VIRGIL C, SLl41'1:R NUCLEAR STATION SCE&G CAD ENHANCED PIPING SYSTEM FLOW DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM MAY BE OPERATED AT P~ESSURE UP MW K

2 I

535* 350 400 350 600 450 350 350 750 563 35 35

  • TO 600 PSIG DURING NORMAL PLANT OPERATIONS, REFER TO DESIGN SPECIFICAIDN DSP-544DA, TABLE 3.

1B 17 1/4/l!i TGB RHM RHM REVISED PER ECR-5009~

REVISED PER ECR-50260 TGB RHM 6 DESIGN ENGINEERING K OF PSIG OF PSIG OF 16 REVISED PER ECR-50099

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PSIG +u"""'""-+:'=+--"-'-'="-'-""'-=-=-"""'-'-'----j-l!CeL.f-'LIL----j ,. SOilllilliBCEJ:..,. V, C, SU""ER t.fl.CLEM STATIDl'I JEt41<1t.lSVILLE, S. C.

AND ECR-50260 LEK MADE CI-ECICED LE APPROVAL t()RMAL UPSET HYDROTEST 21 J/17/18 MR REVISED PER ECR-50914 RHM TJB 3.

DESIGN DATA 20 11116111'1 JTS REVISED PER ECR-50723 DJ WTW AC! RHM ALB 19 NO, 1/13/l!i DATE DJ BY REVISED PER ECR-50099 REVISION JCL MW LE CKO. BY APPROVAL

. --* E-302-641 DAAw'ING l<<JMBEA SHI.N.H:IER 21 REV 1/4 ,,.= l'*B 0 If s* 10* 15'