ML22194A334

2 to Updated Final Safety Analysis Report, Figure 9.2-2, Sheet 1, Rev. 7, Rn 10-012, Service Water Cooling a - Train Outside RB

ML22194A334
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: ML22194A334 (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'