ML23241A619

7 to Updated Final Safety Analysis Report, Chapter 3, Figure 3.2-7, Drawing 102007, Rev. 71, Sheet 4, Reactor Coolant System

ML23241A619
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
Download: ML23241A619 (1)

Text

40 41 42 43 44 45 46 47 48 NOTES: cor-JT'D. FROM (fl:6)

LEGEND:

~ VALVE LE:AK-PFF 1~- ~~s"'u~zLifR AtfcfztJ:UJ-~bE~s~ VALVES NOTE 22 WITH F.EFL~CTIVE AND FIBERGLASS - VEHT

---0-0- PIPING DE.SIGNED TO THE. 16\SS EDITION 52 1e,ss l/2filP 1NSULATIONPER663320-96. ~

5 2 891 IE OF ANSI ~::!>1.1 AND APPL.ICAm.E-

--ill -ill 11 NOJE5: (CONTl~~'i-v1AR C.OOE. CASES. 20. PR IMARY WiR FOi( MAINTENAt-JCE

23. 3/4-X4ZD, ITT VALVE. No. :2471-10-M-3/4 11 OWG- t-Jo. 0lD.321"1*26~ WAf.JH DOWIJ AREA . ~

STOCK COOE. 42-2542>JFOR Tf::ST CO)J!JECTlOf.J . @:D E 41-C I '21 - F.EtlOTE OPE.1!:ATOR.$ Dl.$C.O E 6:-d~t*~T~~~7~~~-1f~J"')~P~ AND ABAr-.1.DONED fN* Pl.

1-8000 C 1-SOCX)A Z4- 5

~~~~~~1~z'.~ 8

25. ANCHOR/DARLING .J/4-* -l878GB. -OC-6006413 -97 P0"0/9183~ NOTE 32

~

25 l.-- ENO OF SCH ~/.sN~Te 1a 1 12."x.6 SI 2057 12lVP

~

NOTE to I Sb DEC. 45-D R~v~~u~1;: 6:N~E::/::~!~s.QIT)

PRAY PIPE DO..,NWARt) TO D D

'S. ACTUATED AUTOMATICALLY BY &AS ANl"ILYZER CONTROI.LER. ~

4 PLl"ICE- DETECTORS .ii TO SFffT D0WNST~=i0t"'1 CF- RE1.IEF VALVE$. ~

5 SLOPE PIPE C¥)WNWAR.O TO PROVIDe=: WA,eR EiEAi.. ON RELIEF V.Ai..VEG ~

6 . LOC.ATE APP ROXIMATE LY M\O'Wln' BE.TweEtJ LOOP AND PRESSUR.IZER. <J2})

7. ALL@ l'l'E.N\ NUMBER$ IN R.<..$. -'IRE SHOWN 'wlTHOJT PRfFIX PGEl.'C REF, WIG. 663200 --4 7 5PE C IAL INSULATION ON PoWCR RELIEF PIPING I~ LIHITED TO AND IN(;LUOES ISOLATION MOTOfUZ..lD VALV[S <1ill)

Cf. DR.LINE TQ6E SLOPED t>OWN FR.OM LooP SE~3 TO CDNM. WITH P'RT. MDR, LIN.E GIT) lO. P,.Fn OR U. ~ f'tPE 1tl 8E SUUCJs WP. <::£I)

I\ . f>RESSURlllR RELIEF NOZ"'Z.1.E N05.REF- C OC*f&>(;,~208-it , ~

B B IN~U>E AUX. 8L06

~,('. I I *1..

ABANDONED IN PLACE I

~ !D~co~_J INSIDE C.ONTAINME.._,T HDR.

• . STATION, ,.RE-, G <JII) lt.iSTfl. NO ZZl.E CRO~S REFERENCE .

LFli)}";~~D t 4?~0N t3. '~i;:;:N HALF OF ~~A w:T~M*ON.

THIS [)R ...W-11>16- >.\FR. [)F(A,W\t.16, NOZ . R.~CC>i D WK.. 28 . ;,:;;:; *;;;:::,;t,m __ FIC. W*234B CHE~C 4/45*E) ~

14*

15.

'~ri.~:::-:..:1' ~~~A TS - 53 W:T ~ TION, TO TS-S8 ARE STRAPPED TO LE AK-OFF A W(j. OC.~663 2 -6 PIPE, 18 ' TO 24 " FROM VA LV E . ~

DI AB LO CANYON POWER PLANT - PG&E CO .

REACTOR COOLANT SYSTEM S*lC. LT-4"1 S"F DRAW i NG SHEET PAGE REV 5., Tl- S n.-+!f-,

Sli UN IT I 102007 4 0 71 10-09-2015 ZNS4 FxC2 KJ03 NOT REQUIRED PER CF3.105 DA~[ DW"J R[ :v PRQi:-~SSIO'ML CNG I N=::::R PE