ML23241A605

7 to Updated Final Safety Analysis Report, Chapter 3, Figure 3.2-4, Drawing 102004-5, Rev. 121, Sheet 5, Turbine Steam Supply System

ML23241A605
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 ML23241A087 ML23241A088 ML23241A089 ML23241A090 ML23241A091 ML23241A092 ML23241A093 ML23241A094 ML23241A095 ML23241A096 ML23241A097 ML23241A098 ML23241A099 ML23241A100 ML23241A101 ... further results
References
DCL-23-044
Download: ML23241A605 (1)

Text

C B

50 STM. GEN.

PG&:E I -A 1-B NOZZL ES MFR. IA IB 30 -C SEE SHT 3 TO MAI N STM LEADS 3 & "1 3

2 4

3 K2* !8"9 - I 5-A 4A 5-B 4B 6

5 7

6 80-1 7B 8D -2 7A 9A - I BA 9A - 2 BD 9B-1 BB 9B -2 BE 9C - I BC 9C - 2 BF ABOVE NOZ. EQU IV.

TYP. FOR ALL GENS.

SEE NOTE 8 FLOW LI NE L EGEND HI GHPRESSURESTEAM8'C0NDENSA TE

--1 L OW PRESSURE STEAM a. CONDENSATE i PIPI NG UNDERTHE JURISDI CT I0N0F ASMEBOI LER S.. PAESSUREVESSEL CODE

~

SECT. 1( I 968.

DES IGNTOANS IB3I. I ( I %7)

NOTES :

I. L I MJTS OF ASME BO IL ER AND PRESSURE VESSE L CODE SECTI ON I ( 1968)

J UAJSOI CTlON.

MANUA L AND MOTOR OPERA TED VALVES WI TH ITEM NUMBER AND WI TH IN LIM I TS ARE UNDER SPEC.

87 29.

2,

MANUAL VALVES WIT H ITEM NUMBER ON CLASS E L INES ARE UNDER SPEC. B762 EXC EPT AS NOTED, MANUA L VALVES WI TH I TEM NUMBER ON CL ASS B OR C LINES ARE UNDER SPEC.

8729 EXCEPT AS NOTED.

3. ON ALL TRAPS &r LCV DRAINS, FULL I NSULAT I ON I S US ED UPSTREAM&

PERSONNEL PROTECTION DOWN STREAM.

4. NI TROGEN BLANKETI NG TUB I NG SEISMICALL Y SUPPORTED PER owe.

NO. 049238.

5. ALL STEAM TRAPS ARE TO HAVE I NTEGRAL STEAM STRAINERS.

6. CHECK VAL VE I S QA CL ASS

' Q ',

DES I GN CLASS I, AND WELDED TO I SOLA TI ON

~~ARE UNDER SPEC,672 1

7. MANUAL VAL VES WIT H THI S NOTE SHALL

~N0.

I 3. I 8.

(S EE TABLE(w)SUBSCR I PTSA,

B, A -1, A - 2, ETC. WERE ADDED TO NOZZLE NOS, TO DIFFEREN TI AT E SERV I CE & I NSTRUMENT TAGG ING.

FEEDWA SUPPL 4 9D03

~

~ 16 555 s-,

REACTOR COOLANT SYSTEM RE F.

DWGS:

DC-663206 - 3, -I JT0

- 20.

~

9. <FE-I) ORI F IC E PLATE REMOVED.

OR IF ICE FLANGES WI TH VALVES RETA INED.

<TI:[>

FEED WATE

10. VEL AN MODEL "W04-2074B - 02MS, SUPPLY owe. *oC - 60064 73-40,<lli) 49D03 1 1, CAL-S I L I NSULATION REPLACED \o/lTH BL ANKET I NSUL AT10N FOR90° EL BOWS NOT E

~iE6~A ~~i* ~~1~~ E 5~~&r~G1+* B~~g/~~~

11 FI RST 90" EL BOW (LINE 55 4&5551.

12. SC57&SCS8ARED ES I GNCL ASS I I &ARE SEI SM I CALLY ANALYZED I N ACCORDANCE WI TH DESI GN CR IT ERIA MEMORANDUM M6 I,

51 IN STE.AM UNIT

!SJ ~TM. DU TO ATM.

¥-14-~0 -~ Y.

52 HT-3

~ J.\4.*~l*\Si

• 4';1, 76CA 31 A

13. MA I N STEAM L EAD DRI P POT DRAIN P I P I NG l l6-554-I SHALL BE I N ACCORDANCE WI TH DC - 049063 TYPE V,

-==--6~~~

14, 1/z', P0722 732, IT EM I.

15.VEL AN 8 122054P - 02 TS<]}])

~: ~~~~~~~:

\

~

ll~~ri? ;f&.r*

18. l NSP POR T ASSY VALVE RECORD NO, 6006473-3 9

~

SHT-71

19.

I '

VELAN CHECK VALVE o we.

RPf.1'AIL f7 1C. ~ STMt,E.N C

• oc - 6006473 -1 69 STOCK *93 - 29 1s.<IE[>

BLOWC:OWN

! §.i

20. r~~Pg~~~~ ~~~S~~~~ I ~~A6~o~g~~95.<ill) kl<..* 1040*1.1/2i u,v, 22, 4" 0, 900* RJWN FLANGE.<TI;>

\. c-1o~il*iY.P

(.TVP,)

52

g~~:. ~~~~**;ia o".

2'. :;~ :'a£"H 80.SME" '°'*

c1<1>t-4t1~~6'w~~AAM 4"

900

• 00, GATE, 8\o/ANCHOR/OAR L I NG DWG. 60 1 1930 - 7 a, 8 RPE P - 7385, <TI;>

INSIO OU'T~IDE.

~~~~ H!~cE TUNNEL 53 MA IN STEAM LEADS I & 2 RV ORA I NS GsEe Coo,,tO. 4/A) e X A/OU I F'l.00/<l. -="'-'-"'"-'.-..-1.-M' (n'J0!,...0-. 10)

J I(

~11-8 ijV

• IO OJ<lAIN

)(

I( C 1/2_

S NOTE S:

( CON T. I

26. VALVES/C93 - 684 7 O\o/G. OC-60064 73 -40. VAL VES WHEN REPLACED MUS T BE I NS TAL LED WITH THE MA I N STEAM PRESSURE UNOER THEOISC.~

27. ~~- 6~g~ 6~~~~~/ill> RECORO 28. 3/4" -

1500

• GLOBE VAL VE KEROTEST S/( *94-3774 owe.

<TI>

32. FOR SPEC TACLE PLATE DETAIL,

SEE DRA\o/ lNC066 I 42, <'.M)~

33. MA INSTEAMP I PI NCOOWN -

STREAMOFMSIV ' S(FCV - 4 1,42, 438,44lTOT HE G* L INE ANCHOA ATTHE TURBI NEBU ILOING\IAL L I S SEISM I CALLY ANALYZ£0.

D

,-834 *ti 34' i?~~ 1 g~;D 0~1 c~~g.

R g~~ ~ r A~ ~ ~~~ 97

!.A0 66 559.@)

35, PORTIONS OF LINES 3414, 3434, EJ( ':;.~t~u."'

!i!~~~~~N~!~~ ~~~i~~~ii~;~gl~gN.

MCA.TEP.S I SOMETR I C DRA\IINCS FOR LOCA TIONS.

36.SONOZZLE NUMBERSARE FOR RSCs.

SEE602 I 772-7d FORCROSSREFERENCE TABLE FOROSC NOZZLENUM8ERS.

UNIT DIA BLO CA NYON POWER PLANT - PG&E CO.

TURBINE STEAM SUPPLY SYSTEM C

B A

~;

-;;- Siu;

~~G~P:!~~; : ~~~:~~~:T~o::~

94 3175 REACTOR CO~TAINME~T 1 0 R2 AWO I NGO 4 SHSEE T PAGE REV cR_~;~~~og0NTD~~6~~~;69 - I. (w O I 2 I

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