ML23241A630

7 to Updated Final Safety Analysis Report, Chapter 3, Figure 3.2-8, Drawing 102008, Revision 115, Reaactor Coolant Drain Tank, Sheet 4

ML23241A630
Person / Time
Site:	Diablo Canyon
Issue date:	05/25/2023
From:	Pacific Gas & Electric Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML23241A052	List: DCL-23-044, 7 to Updated Final Safety Analysis Report, Chapter 9, Figure 9.4-10, Drawing 512904, Revision 15, Mechanical Air Monitoring Technical Support Center and Post-Accident Sampling System Air Flow Diagrams ML23241A053 ML23241A054 ML23241A055 ML23241A056 ML23241A057 ML23241A058 ML23241A059 ML23241A060 ML23241A061 ML23241A062 ML23241A063 ML23241A064 ML23241A065 ML23241A066 ML23241A067 ML23241A068 ML23241A069 ML23241A070 ML23241A071 ML23241A072 ML23241A073 ML23241A074 ML23241A075 ML23241A076 ML23241A077 ML23241A078 ML23241A079 ML23241A080 ML23241A081 ML23241A082 ML23241A083 ML23241A084 ML23241A085 ML23241A086 ... further results
References
DCL-23-044 102008, Rev 115
Download: ML23241A630 (1)

Text

40 41 42 43 44 45 46 47 48 49 OMS CONTAINM ENT LEGEND REF DWG 6632 I 0- I 4 & I 5 INSIDE I OUTSIDE - ::;-c-o PIPING UNDER THE J URISD I CTI ON OF ASME BOILER AND PRESSUR E VESSE L CODE SECT I ( 1968 l DES I GN TO ANSI B31. I ( 1967)

A A OUTS IDE REACTOR CONT Al NMENT COMPONENT COOL I NG WTR

~

B K- 126-8 TO VOLUM E B SI 24 f CONTRO L TK I - I 2 - RV52JWB,i'.J~

VALV E L EAK - OFF TO MISC . E0 OR TK 0- 1 SHI A LOOP SAMPLE GROSS FAI L ED l;/,J S2 - 2 FU EL DETECT SYS I 28C IT EM I I SPEC 8729 ~ S2-2408- /z 1 []

REGENERA T I VE HEA T EX CH AN GER I - I MULT IP L E SHELL IT EM : AHRG DC - 6632 10 -7 2&73 8408A PCV-135 8408B 3X2 2 - T58 2 -R A56D0 2 -T5 8 C S2 - 3/4 C

[BJ@ 9368(

8407A 84078 S2 - 1462 - 2 ~ t~~?!

1/~ -T5 8

-ill 3/4-T58 S-169 1 -1/s

~

_3/4-TSS @[Bl S1 -4 34 - 2 FT

~ ' 3' SI -3/~ 8409 TO SAMPLE 3/4-T58 LJ SYSTEM S2 1507 - 3/4 D NOTES :

TC NOTE 7 <D)

S6-6026-3/4 @ I.

2.

3.

SPECIAL LINE INSULA TI ON TO LCV-460 PRESSURIZER LOW LEVEL S 1GNAL <}QJ)

LETDOWN LINE TO BE ROUTED LONG ENOUGH FOR RADIATION INCLUDING VALVE DRAIN TO M!SC NOTE 8 DECAY I NG PURPOSES ~

RCS PRESSURIZER EQUIP DR TK 0-1 D REL !EF TAN K I - I

4. 1/a " TUBING INSERTED IN 3/4" NOMINAL PIPE AT VALVE <3]) D

5. FLOW THROUG H R0 - 27 IS 45 GPM . FLOWS THROUG H R0 - 28 T

T58 & R0-29 ARE 75 GPM <ill)

S6 3 6. SPECIA L LINE INSU L A TI ON I NCLUDING CHECK VALVES (E>

C>-- --<36;)-"' S6::..._:

' ~8 -~ 3'-(,~9D8-o~

J

7. REFER TO owe. 049094 FIG . 470B @=0 8378C CHARG I NG PPS

~3/.-T58l D

1MB p S 31/,C5s 88 S 'h DISCHARGE 8.

9.

3/4" GLOBE ANCHOR OAR L !NG MODEL NO. 1878GB ,

CODE 94-2820, DWG 6006473-97<TI])~

2-600= GATE VALVE , VE LA N, DWG .

STOCK 6006473- 167 . <3I0 OMS 10. VALVES LC V - 460, 8 14 6 AND 8 147 ARE 2" SIZE S6-3/4V WIT H ENDS PREPARED TO MATCH 3 " PIPE <JI]) ~

0  :%-T58 N < TYP. 9) I I. I" GLOBE DARLING MODEL 1878, 590 V O 565 STOCK CODE 4, DWG. 60 I I <ill>

[B_@_ _ill_@ 12. POR T IONS OF THESE L INES HAVE ADD IT IONAL BANDS lNS T ALLED lE_J@ lE_J@ ON 3 " CENTER-TO-CENTER (MAX) SPACING. SEE owes 437992, 52-4248-3/4 52)3/,I S2-6027-3/4 437995 and 501505 FOR SPECIFIC LOCAT IO NS.

S2-6024- I UN IT E

~ /'c1 ~ /cu1 DI AB LO CANYON POWER PLANT - PG&E CO .

S2 4250 -1/~

l;;! V ~ ~ 0 CHEM ICA L & VOLUME CO NTROL SYS TEM S2-3208 21VP _ / S2 4263-3/4 S2-4264-3/4 DRAW i NG SHEET PAGE REV REACTOR COO L ANT ORA I N TANK 102008 4 0 I I5