ML21055A401

3 to Updated Final Safety Analysis Report, Drawing No. 4M721-5862 Rev. B, Residual Heat Removal Valve Positions During Normal Reactor Operations

ML21055A401
Person / Time
Site:	Fermi, 07200071
Issue date:	02/02/2021
From:	DTE Electric Company
To:	Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML21055A091	List: ML21055A061 ML21055A062 ML21055A063 ML21055A064 ML21055A066 ML21055A067 ML21055A068 ML21055A069 ML21055A070 ML21055A072 ML21055A073 ML21055A074 ML21055A075 ML21055A076 ML21055A078 ML21055A079 ML21055A080 ML21055A081 ML21055A083 ML21055A100 ML21055A101 ML21055A102 ML21055A103 ML21055A104 ML21055A105 ML21055A106 ML21055A107 ML21055A108 ML21055A109 ML21055A110 ML21055A111 ML21055A112 ML21055A113 ML21055A114 ML21055A115 ML21055A116 ML21055A117 ML21055A118 ML21055A119 ML21055A120 ML21055A121 ML21055A122 ML21055A123 ML21055A124 ML21055A125 ML21055A126 ML21055A127 ML21055A128 ML21055A129 ML21055A130 ... further results
References
NRC-21-0002
Download: ML21055A401 (1)

Text

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I CONTROL-MINIHUM FLO\\,/ BYPASS 3

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DIV. I DIV. II POOL 2

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NOTES:

ALL VALVE NUMBERS AND PIPING ORIACES SHOWN ON THIS DIAGRAM SHOULD BE PREFIXED BY E1150 UNLESS NOTED OTHERWISE.

ALL INSTRUMENTATION SHOWN ON THIS DIAGRAM SHOULD BE PREFIXED BY E11 UNLESS NOTED OTHERWISE.

THIS DWG. SHOULD NOT BE CONSTRUED AS THE CONTROLLED Pl<ID Of THE RESIDUAL HEAT REMOVAL SYSTEM.

CONTROL-MINIMUM fLO'J BYPASS I

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ULTIMATE HEAT SINK RHRSI,/

• coLING Tl,/ERS 4

RHR PUMP 'A" E1102C002A E1100 FOJ1A moo F0181.

moo F046A E1100 FO.l4C moo moo ro111:

F031C 1100 F046C Ef100 E1100F014A E1100F002A F0J0A B DCD'S INCORPORATED:

EDP 21215 REV. g EDP 2132.q REV. m RHR PUMP 'C E1102C002C E1100 F0340 E1100 F031D RHR PUMP 'D' E1l02C002D X ;J;

~~

E1100 ro,

.~1:-:-::--JRHR E11 1B HEATI------'

EXCH. E1101B001B Ef100 F014B E1100F0028 MO F073 E1100 F034B E1100 FOJ1B El151C0018 RHR PUMP 'B' E1102C002B 0-l-E----luL T!MATE E1100 SER';ICE WATER HEAT F148B PUMPS

.~~--"!:::~S;IN;;K~

TC E1100F0208 A PORTION OF THIS DRAlllNG IS AFFECTED BY THE l'OLI.OWING:

CHANGE DOCUMENT RHRSV COOLING TOVERS PREPARED BY INC.CODE TlTLE u

4M721-5862 LATEST REVISION B

!NUCLEAR SAFETY RELATED!

THIS IS AN AUTOCAD PRODUCED DRAWING.

CHANGES OR REVISIONS MUST BE BROUGHT TO THE ATTENTION OF THE PLANT ENGINEERING DESIGN GROUP TO ENSURE THAT CONFIGURATION CONTROL IS MAINTAINED.

Detroit Edison Fermi 2 RESIDUAL HEAT REMOVAL VALVE POSITIONS DURING NORMAL REACTOR OPERATIONS B

CHECKED BY DATE j__ __________

.j-----f-------t-~=="-""'--t-===---i _______________ ---tA OTHER REVISIONS:

APERTURE CARD TITLE PREPARED BY JIGNESH SHAH APPROVED BY HCc5,g~

EDP POSTING ENTRIES REQUIRE THl!l ADDITION OF THE ARIIS STATUS CODE:

EITHER "AFC" OR ".ASB" UFSAR FIG. 5.5-14 APPROVED BY PLANT IDENTIFICATION SYSTEM NUMBER E1100 ARMS RECIPIENT#

1---0-T-H-ER_AP_P_R_OV_A_LS_+-_D_A_TE_-l DOCUMENT TYPE CODED DD ME C NUC OPS FILE NO, DATE ISSUED TO IS 1801 DRAWlNG NUMBER 4M721-5862 2

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