ML22194A303

From kanterella
Jump to navigation Jump to search
2 to Updated Final Safety Analysis Report, Figure 9.2-2, Sheet 3, Piping System Flow Diagram Service Water Cooling B - Train Outside RB
ML22194A303
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: ML22194A303 (1)


Text

14 SYSTEM DATA mo GPM PSIG*

'F BY REMARKS 2

9000 50 95 NORMAL 7700 50 13111 POST ACC!D A

3 1000 50

'l5 NORMAL 820 50 116 POST ACCID 4 1000 to 45

> 65 NORMAL 600 500 45

> 65 POST ACC!D

  • APl'ROY.

8 C

D E

F G

H J

HYDRO STA TIC TEST TEMP. 60" 10 125 95 165 95

<1%

210 RJS 9

16 150 20 150 (1%

25 ccs 8

16 95 20 214

<1%

25 ccs 7

IS 124 20 130 25 WTW K s 65 124 65 130 82 WT\>/

5 65

'15 65

'35 82 ccs PSIG F

PSIG F

DURATION HYDR BY UPSET DESIGN DATA 13 LAC LRC CHD LOOP 'B" J-9

-221 SW NOTE 3 REMARK 7

COUPLING/

RNm-8 (9 REQ'D) 12 11 10 9

8 7

6 5

4 3

2 1

16'

~-------------------------------~--------------------------------------------"'""'s*_~

C PLING RNm-6 30' 30'x24' 8'

20'x1W 24' ECR5l1J605 r 13135B-SW 3/4*

!---flll1ll*-3

.@~

13'

~~

31228-SW HVAC CHILLER~

B CONTROL CGAI DWG B-211!

llil'l SHT VU02 I

I 6'

RNn-55 3126B-SW

<G>

ROh-1 IPX4485A-HR-'Slil\

3/4" 1CH!LLEO WATER

)

3/4",.--

LD-302-841 LOC 0-5 ROh-1 ~--

13122-SW 20' ROh-1 STATION DRAINAGE E-911-106 LOC H-9 IPX4515A-HR-SW ROh-1 ROh-1 13123-SW VENl 3/4' Hl:§>-(TM\Q) 0_4 L co~

~

D-4 I

l'vu-,:_/-

-a41 5

XHX-18-VU 3/4" HVAC~S~Y_S_T_E_M_M_E_CH~A-N-IC_A,,_LI WATER CHILLER COND 'B' [ID IPX4485B-HR-SW ROh-1

!FT 4491-HR-SW J-13

~>---

14*

cc ROh--1 IPX45158-HR-SW ROh-1 IFT4490-HR-SW MRF-31489

?

13124-SW W

SET AT 65 PSJG RGo--1 SAMPLE_,,

3180B-SW STATION DRAINAGE I E -911-106 1--------"

_ _h,OC, H-11 BPb-1 (i)'IFT4490-LR-SW 20* ~c--

l' 1

!PX4506A-HR-SW~

---=-----

3" iJ)

j' 4

RN -14 31238-SW

~

(6TI)

~8' 8'

cd DSP-661 XHE-17B-DG RNg-15 /~

TSC 31218-SW CD 41)-

ZS J_~---/4<

~to1

~o DIESEL GENERA TOR

'B'COOLER --~

<rsc

{)I ROh-1 IFT4492-LR-SW BPb-l

!PX4506B--HR-SW SEO_~

j CO2 DG 'B' HI LUBE Oll/Hl WATER JACKET TEMPERATURE LOGIC SEE GA! DWG D-81112-014, SHT 5

.fl I

!J5X +SP-l?J H-3 L----------------------J,,V]-----,------1"-J-l--'-----vi'----=--,~---,-----'4-' -J\-----1 I f-1 --<(231 SHT. 31

~

3/4'*

ROi-2L_~

R0!-39

,-1:

\_'.:=

FS 31048-SW 31198-SW 3121118-SW 3/4"

~~ /w

-~.~P~~~.~4,~A~-~s~w 31318-SW 0

XPS-14 78-SW 13127-SW l/4u= i' "0,_,

0' 5'

10' 15' 20' cqD 6'

I RN~-16 31278-SW MRF-21746 31'l58-SW 7

8 241x205 afu COUPLING RNm-6 20' 8

9 16' 20'x1s~

COUPLING

,..RNm-7 (8 REQ'D)

RDi-21 313l1JB-SII NOTE 11

" '----£0UPL!NG RETURN TO S.W. PONO NOTES:

RNm-7 (3 REO'D)

I. ALL PJP!NG TO BE LINE SPEC 152N.

EXCEPT AS NOTED, G-3

-222, SHT. 4 3, TEMP CORRESPONDING TO PERTINENT HEAT EXCHANGER OUTLET.

5, ALL STATUS LIGHT INDICATE BOTH OPEN AND CLOSED POSITIONS, 6,

  • DENOTES MISSION DUO CHECK OR EllUAL.

9,RECORDER SHARED WITH REACTOR BLOG SPRAY PUMP FLOW INSTRUMENTATION.

11, XVC03130 A/8 MAY NOT PROVIDE ADEQUATE ISOLATION FOR USE AS A BOUNDARY DURING SYSTEM DRAINING, REFERENCE NCN5063 OJSP, 0 4.

THIS IS A NUCLEAR SAFETY RELATED DOCUMENT, NO DEVIATION SHALL BE INITIATED OR PERFORMED WITHOUT PRIOR DOCUMENTATION AND WRITTEN APPROVAL FSAR FIGURE 9.2-2 SH,3 SOUTH CAROLIN/\ ELECTRIC & GAS COMPllllY VIRGIL C. SUMMER NUCLEAR STATION PIPING SYSTEM FLOW DIAGRAM SERVICE WATER COOLING B - TRAlN OUTSIDE RB Q

DESIGN ENGINEERING f---+--1------------f----j----j A :00.:~ V. C, SUMMER NUCLEAR STATION J£Nl<!NSVILLE, S:. C.

MAD£ CHECKED LE ~PROV/IL i--+--+--+----------J---,-----1'-

JNC P AH

3. MGC 0

1/6/09 JNC REVISED PER ECR-71215 P/>H MGC LE D-302-222 3

0 NO.

DATE BY REVISION OOA\fENG HlMBEfl SHT, NUM8E1l REV A

8 C

0 E

F G

H J

K RN 09-002 January 2010