ML22194A164
| ML22194A164 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/27/2022 |
| From: | Dominion Energy South Carolina |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22194A236 | List:
|
| References | |
| 22-179 | |
| Download: ML22194A164 (1) | |
Text
{{#Wiki_filter:B C 0 E 14 SYSTEM DATA ~MAX o L.?;,/ GPM PSI F REMARKS I 087 100 120 4 5 6 7 8 9 !0 11 262 80 145 240 80 125 150 80 145 5 80 145 120 100 120 120 130 120 40 80 145 1087 70 125 l<RC KRC START-UP ONLY KRC KRC KRC KRC KRC KRC 13 '3/4"X1/2" <TYP. 4 PLACES) - _..f R0h-1 \\ !FT-7263A-HR-CC USE NEXT cc 19500 1%13 cc 951110 9699 SYSTEM SUFFIX FffiST NO. LAST NO, VAL VE NUMBERING 12
- THIS TEMP IS A MAXlMUM EXPECTEO FOR 95.F SERVICE WATER TEMP. AND LOSS OF ONE CCW HEAT EXCHANGER DURING PLANT COOL DOWN MODE.
CONTAINMENT ~ ISOLATION PHASE ~a~ SIGNAL I 6" r-- ~(3 PLACES) 3(4 Pl.ACES) ~ 6" 6" ~ ROh-14 ~~ 6" ROh-14 .------J.'3 \\19506-CC !'l507-Cc --i,, 9691-9699 DWG. E-911-108 ~ 3/4" VENT[
- I VENT[:
11 ROJ-4 9573-CC 10 6" EXCESS LETDOWN HEAT EXCHANGER 9 XP5-77A-CC RNl-4 -9577-CC \\ £ b 6" ~ '3/4" ROh-10 \\~J~ll-101 > '-+-----r:,oc,1_'l_5_1_2_-c._c ___ 'N ___ 1_50_P_s_1 -'--'3/4"-*'_' __ c_. _F_-1_0a,----------,. D~IN F G H J HYDRO TEMP - COLD WATER 46-47 150 K 2.13 48-55 120 1G0 150 180 2 HR iC:10 f;') PS!G °F PSJG °F OURA HY-j-'--' NORMAL UPSET ORO BY CHKD DESIGN DATA 8" RNn-30 ~ A crv. TC w-
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!lJ "'._,_,ROh-14 9642-CC ROL-2 963 -cc E-6 -61! cc REMARKS R0,-2 'l632-CC 1/4"':: I' -0 u 0' 6" ROh-14 5' 10' 15' 3" FE'\\ 7118 6" ROh--14 lFT-7116-HR-cr-ROh-14 I I VENT 7116 r<Sc ~: .._____,n 3/4" _J F-6 Cl1J! E-302--735 XHE-12-WL WD REACTOR COOLANT DRAIN TANK HEAT EXCHANGER INSIDE REACTOR CONTAINMENT OUTSIDE REACTOR CONTAINMENT !TL-LO PRESSURE (Pr 7111l! 1:~ ROh-1 '!PS-7105-HR-CC R0h-1 lPI-7101-HR-CC \\ l:-11!<!1!!---l -,*;-:;-;---3/4" / ROh-14 I.Cl 1.9504-CC-DRAIN 8 R0h-14 !950'l**CC ROg-17 9595A-cc\\._ 3" RO -17 9597A-CC 7 6 6" 3" (.) y R0g-17 "' l 95978-CC
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5 3" ~ i , ~ I _[.lOg-17 ii:~ 9597C-CC ~ 0 R01-6 '-Co(!-- 9 968-CC ~ VENTn ~ B 1f) t t!i"\\Sf____ 0 ROh-1 / 12 ~,-~ 19524-CC 3/4" 12,4 HP I COMPONENT COOLING BOOSTER PUMPS 3-1001/. 120 GPM 110" TDH RGs>-4 34~0 ~ XPP-588-CC R, M -c=:J C01 ROg-17 95958-CC~ 460V I ' ~ 3/4." ~-~ L -*v '-1~-cJ DRAIN - <i;;°;2J-tc 05X -- RN1-l 311 ~rr=cr w< A 1~ -"-{> 150 PSI E"r 1 ~ 11TIAl , ~r.... ~. -,c Ji,.1, t, \\ ;z-.d ~,~. \\I ~iij ~3/4l ! I 6 ", ~ "* 4 24 23 22 21 26 25 NO. 3 2 3" 11/211 I 3" Ll u ' '° r--. ' (J) "-x I ROh-1 9599-CC l..!.J l CIV RNn-5 600-CC 3/4" CBV ROp-3 9601-CC ROh-1 !Fr -*=12=7=3~A~--L~R~-.=c TV <L~ '-'-'~ r-2a OUTSIDE INSIDE c. xi-Oh-! 150 PSI ROg-17 9595c-cc\\ 5n5102 RHM 6/23/89 DDJ 10/01/llll JTS 01107/!l!I JTS 04/14100 RHM 2/!J/08 JMR DATE BY DRAWING LEGIBILITY CLASS 1 REVISED PER ECR-50263 DDJ REVISED PER CGSS-99-0332 MGR REVISED PER CGSS-98-0424 MGR REVISED PER CGSS-97-0569 LEK REVISED PER ECR~ 71263 MGR REVISED PER ECR-50239 MGR REVISION CKD.BY REACTOR REACTOR ~ 1/2 CONTAINMENT, CONTAINMENT t(l I
- NOTES,
- 1. ALL PIPING TO BE ANS SAFETY CLASS 26 EXCEPT AS NOTED.
- 2. ALL NUC SAFETY CLASS PIPING TO BE LINE SPEC 152N UNLESS OTHERWISE NOTED.
- 3. ALL NON-NUC S.C. PIPING TO BE LINE SPEC 15!X UNLESS NOTED OTHERWISE.
- 4. DUAL ORIFICES - ONE FLOW RESTRICTING THE OTHER BLIND FOR USE IN LEAK TESTING
!SOLA TION VAL VE,
- 5. ALL </;;> STATUS LIGHTS INDICATE BOTH OPEN AND CLOSED, UNLESS NOTED OTHERWISE.
THIS IS A NUCLEAR SAFETY RELATED DOCUMEMT_ NO DEVIATION SHALL BE INITIATED OR PERFORMED WITHOUT PRIOR DOCUMENTATION AND WRITTEN APPROVAL UIS._ ALB MWD MGR RHM DJ LE APPR:OVAJ.. PIPING FSAR Figure 9_2-5 SOUTH CAflOllNA ELECTRIC ~ GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION SYSTEM FLOW DIAGR COMPONENT COOLING SYSTEM INSIDE REACTOR BUILDING DESIGN ENGINEERING If. C. SUMMER NUCLEM STATION J£MQ"1SV!U.. E, S. C.
- s.
A.V.N. M.G.R. R.S.B. D-302-612 26 tlRA\\flNG /l!UMBEfl A B C D E F G H J K RN 09-010 May 2009}}