ML21305A639

6 to Updated Final Safety Analysis Report, Figure 3.2-7, Sheet 2 of 9, Drawing 108007, Revision 49, Sheet 3, Reactor Coolant System

ML21305A639
Person / Time
Site:	Diablo Canyon
Issue date:	10/11/2021
From:	Pacific Gas & Electric Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21306A142	List: DCL-21-074, 6 to Updated Final Safety Analysis Report, Figure 3.2-4, Sheet 1 of 16, Drawing 102004-3, Turbine Steam Supply System ML21305A089 ML21305A090 ML21305A091 ML21305A092 ML21305A093 ML21305A094 ML21305A095 ML21305A096 ML21305A097 ML21305A098 ML21305A099 ML21305A101 ML21305A102 ML21305A103 ML21305A104 ML21305A105 ML21305A106 ML21305A112 ML21305A113 ML21305A114 ML21305A115 ML21305A116 ML21305A117 ML21305A118 ML21305A119 ML21305A120 ML21305A121 ML21305A122 ML21305A123 ML21305A124 ML21305A125 ML21305A126 ML21305A127 ML21305A128 ML21305A129 ML21305A130 ML21305A131 ML21305A132 ML21305A133 ML21305A134 ML21305A135 ML21305A136 ML21305A137 ML21305A138 ML21305A139 ML21305A140 ML21305A141 ML21305A142 ML21305A143 ... further results
References
DCL-21-074
Download: ML21305A639 (1)

Text

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31 CONNECTION FOR VAC.

REFILL SYSTEM

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NOTE 13 NOTE 13 32 REACTOR COOLANT* PUMP 2

• I ITEM: PCPC I DC-663207-6 STEAM GENERATOR 2-1 ITEM: PCSG I DC-663206-44,-45

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NOTES I & 14 STEAM GENERATOR 2-4 ITEM: PCSG4 DC-663206-50, -51

~

FOR PUMP I NS TRUMENT AT I ON SEE DWG 11 OE360 LOOP 4 TYP. ALL PUMPS NOTES j 2 & 14 I. 05" O.

0. 234" I 33 NOTES 3 & 14 34 35 36 37 38 eves EXCESS LETDOWN DRAIN TO REACTOR COOLANT DRAIN TANK 36A-B12 32.-E 0 SIS ACCUM NOTE 19 30*8 09 BIOLOGICAL SHIELD S6 63 I 2 K)-<J~PIPING DESIGNED "fO THE 1955 EOITIONOF AN51831.I AWO APPLICABLE NUCLEAR CODE CASf5 S6 237 6S SAFETY !NJ PP 2-2 ReF: OW6, DC-663f.2.0-2 5 NOTES:

I. 29" INSIDE DIAMETER <IEQ)

2. 31" INSIDE DIAMETER (30-0

3. 27. 5" INSIDE DIAMETER QED

4. ALL@ ITEM NUMBERS IN RCS ARE SHOWN WITHOUT PREFIX PGE RC. REF@STATUS REP.

5. SPRAY LI NE SCOOP QED eves REGEN HX ALT. CHARGING

10. LOCATE CONNECTION IN BOTTOM HALF OF REACTOR COOLANT PIPING ON 45° ANGLE TO VERTICAL~

6. ELBOW FLOW METERS (30- >

I I.

REACTOR COOLANT PUMP 2-2 ITEM: PCPC2 DC-663207-6 STEAM GENERATOR 2-2 ITEM: PCSG2 DC-663206-46, -47 OC[JQD_**~*,

39

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NOIT72 NOTES 2

& 14

19. INSULATION ON PORTIONS OF THESE LINES HAVE ADDITIONAL BANDS INSTALLED ON 3" CENTER-TO-CENTER

< MAX. I SPACING. SEE DWGS 226226, 226227, 226229, 226230, 226263, 226241 & 226269 FOR SPECIFIC LOCATIONS.

15. TS-67 IS STRAPPED TO LEAK-OFF; 18" TO 24" FROM VALVE~

16. CLASS E TUBING SHALL BE INSTALLED IN ACCORDANCE WITH CLASS I INSTALLATION REQUIREMENTS

7. LOOP PIPING IS PROVIDED W/ REMOVABLE 12

• CONVENTIONAL INSULATION AT RT DUAL ELEMENT RTD'S <TYP FOR 161QED SPECIAL LINE INSULATION BEFORE ISOLATION VALVE INCLUDING VALVE~

LOCATIONS PER DWG. 663320-471

13. ANCHOR DARLING 2" DOUBLE DISC GATE VALVE DWG. 6006473-2 S/C. 93-6294 (32-E>

REACTOR COOLANT SYSTEM INPGIC I Size I 7. SEE SHT 7A FOR RVRL IS AL I GNMENT FOR OPERATION ~(39- >

18. DWG. DC-6006473-159, S/C. 94-3773~

8. HEAD GASKET MONITORING CONNECTIONS FURN I SHED WI TH REACTOR VESSEL (34-D>

9.

RT INSTALLED IN WELL AND INSULATED, SEE DWG 663320-498<'.n::D

14. REACTOR COOLANT LOOPS AND PRESSURIZER SURGE LI NE-FURN I SHED BY @, INSPECT I ON DOCUMENT AT I ON TO ASME B&PV CODE SECT. I. I 968 03-16-2015 ZNS4 FxC2 SWH2 NOT REQUIRED PER CF3olD5 REVISED PER DFT-7*3000

>----------+------i----+-----+------------------+-------+-------+----------1 DATE OWN RE IV PROFESSIONAL ENGINEER PE DISCO PE""

PE EXPO DFT-7*3062 DRAWING SHEET PAGE REV 108007 3

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