ML21209A463

1 to Updated Final Safety Analysis Report, Chapter 9, Figure 9.2-2, Revision 7, Sheet 1, Piping System Flow Diagram Service Water Cooling

ML21209A463
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: ML21209A463 (1)

Text

I~ 13 12 II q 8 7 6 5 3 2 SYSTEM DATA ao GPM Psrn* .F BY REMARKS ROhl IFT 4462-HR-SW 2 'l000 50 'l5 NORMAL ROh-1 7700 50 130 POST ACCID PX A 3 1000 50 'l5 NORMAL XHE-17A- A 820 50 116 POST ACCID ROhl 4 L\\0 to 45 124 NORMAL IPX4476A-HR-SW RETURN TO 500 45 130 POST ACCID SW POND 17 45 124 NORMAL ROi-21 500 45 130 POST ACCID 3 l 30A-SW L

"APPROX.

B OG 'A' HI LUBE OIL/HI WATER B JACKET TEMPERATURE LOGIC SEE GAi DWG D-802-014, SHT 5 l

I 75XiSP- 1~4

---"'V1--..... ----~-----4 I J-2 H 31 SH.3I

~ ROp-4'l / I\ FS 3104A-SW 3l31A-SW (OR.l ROi-22 3l1'lA-SW 0 13126-SW C XPS-1468-SW C XPS-146A-SW 6'

ECR-70724 D

v~l D 20' \13100-sw ROh, IPX4455A-HR-sw 20'

/PX\ .BOb::L....J NOTES:

~ 3138A-SW I. ALL PIPING TO BE LINE SPEC I 52N.

EXCEPT AS NOTED, 2' 3/4' 3, TEMP CORRESPONDING TO PERTINENT HEAT EXCHANGER OUTLET.

5. ALL STATUS LIGHT I NDICATE BOTH OPEN RNg-14 , .YI-----E::------,t-....;._,-, _,,-i~-:.'!')_-.?ir--~'~ ANO CLOSED POSITIONS.

6.

• DENOTES MISSION DUO CHECK OR EDUAL.

3l22A-SW B' II. XVC03130 A/ B MAY NOT PROVIDE ADEQUATE I SOL ATION FOR USE AS A BOUNDARY DURING SYSTEM DRAINING.

REFERENCE NCN5063 DISP. 0 4,__.,.....,...,_....,_....,....,,........_

E 20'

12. Bl 6.5 150

• TEE. 316 SST TO RESIST CORROSION AND MI C.

E 155X 20' 2' 2' l 55X 2' 2' MRF- 22144 F 3141-SW F 6'

<pTsc

-K;)Q)

I 4461 CO!

6'

'-© ROh- 1 4461 LO

!FT 446 1-LR-SW 6'

G 16' G RNn-55 3126A- SW F-14

-222, ROh - 1 SHT.2 I PX44958- HR- SW ECR50585B

/ 1314 7 -SW AT 70 PSIG ,.......;..;._m*:1vENT H H ROh- 1 1' RN 10-012

! F T 4463-LR-SW 60 t - - - - - - - - - tlXt-,

ESSENTIAL

_ MRF-21746 RNg-16 3196- SW

- 312 98- SW 3' MRF-21746 3195C- SW MRF - 21746 THIS I S A

-..._ RNg-I6

/ 319 7-SW NUCLEAR SAFETY RELATED 312 9C- SW DOCUMENT. NO EVIA TION SHALL BE J PENDING/HOLD CHG n I NI TIATED OR PERF ORMED WITHOUT PRIOR DOCUMENTATI ON AND WRI TTEN APPROVAL J HYDROSTATIC TEST TEMP. 60" RNn-55 CHILLED WATER Use With reference to D- 302 - 841 312 8 C-SW ECR: @t,,90 LDC D- 6 FSAR FIGURE 9.2- 2 SH. 1 RNg-16 DATE: 1#-/ 1*1/

16 16 130 20 135 ( 1% 25 JPM 312 8D- SW STATION DRAINAGE INITIALS:""71111\ /i,

-911-106 LDC H-8 SWTH CAllll. llt\ ELECTRIC I r.AS COIWft 15 65 130 65 135 82 JPM 2 10 RJS RNg-16 10 125 95 165 95 ( 1% VIRGIL C. SlHER tu:LEAR STATlllt 3129D-sw 9 16 150 20 150 (1% 25 ccs PIPING SYSTEM FLOW DIAGRAM 8 16 95 20 2 14 ( 1% 25 c cs SERVICE WATER COOLING

• M 7 16 12 4 20 130 25 7 ....: A

• TRAIN OUTSIDE RB K 13 0 82 TW L RC CD I ~ DESIGN ENGINEERING 6 65 124 65 ECR- 5 0585 K 5 65 95 65 95 82 NOTE 3 PER ECR- 50585 V. C. Sl.lMER NUCLEAR STATION JENKINSYL LE S. C.

Cl-£CKED LE APPRO\/Al.

F PSIG F DURATION YOR CHO REMARK REVISED PER ECR- 505 85 MGR RS

1. UPSET 7 1l/26/12 RHM REVISED PER ECR- 50695C RHM WTW JNC PAH MGC 6 4/fl/'O. ODJ REVISED PER ECR50585A MGR RS

..,...... 0 -302-222 DESIGN DATA NO. DATE BY REVISION LE CKO. BY APPROVH.. CRAVING lUIER ,.,,_....,.. 7 1/ 4" = I '

• 0 "

0' 5' 10* 15' 20'