ML21055A152

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3 to Updated Final Safety Analysis Report, Drawing 6M721-2082, Rev AB, Diagram Standby Liquid Control System
ML21055A152
Person / Time
Site: Fermi, 07200071  DTE Energy icon.png
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: ... further results
References
NRC-21-0002
Download: ML21055A152 (1)


Text

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4' AB'DCD'S INCORPORATED, FOOS s 3'

2' THIS DRAWING WAS REFORMATTED BY MICROSTATION AT REVISION* AB~. ALL PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON MICROF!LM rn DOCUMENT CONTROL A PORTION OF Tt-US DRAWING lS AFFECTED BY THE FOLLOWING:

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DIAGRAMS I REF I

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I DIAGR,l\\M -

CONTROL Rw.1,.1 J.JKJ. v t...

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SYSTEM <CRD)

N-2081 2 I DIAGRAM -

STAND-BY LIQUID CONTROL I

I SYSTEM (SLC)

~-2082

-++I IAGRAM - RESIDUAL HEAT REMOVAL SYSTEM I

IVISl N I <RHR)

!AGRAM -

RESIDUAi_ HEAT REMOVAL SYSTD1 DIVISI N II CRHR) 5 LIAGRAM -

CJRE SPRAY SYSTEM (CSS) 6 I CIAGRAM HIGH PRESSURE COOLANT :N~E:;TION SYSTEM (HPCD 7

j DIAGRAM -

HIGH PRESSURE COOLANT INJECTION SYSTEM BAR M::TRIC C NDEt,,iSER <HPCD 8

j DIAGRAM -

REACTOR CORE ISOLATION COOLING SYSTEM CRCIC) 9 j DIAGRAM -

REACTOR CORE ISOLA T!ON CODLING SYSTEM BARCMETRIC CONDENSER <RCIC) 10 j DIAGRAM -

REACTOR WATER CLEAN-UP SYSTEM CR\\./CU) 11 DIAGRAM -

REACTOR WATER CLE~N**UP FIL TER/DEMINERAL!ZER (R\\/CU) 12 DIAGRAM -

FJEL POOL CODLING SYSTEM ffPC)

FIL TER/DEMINERALIZER (FPC)

N-2084 M-2083 M-2034 M-2035 M-2043 M-2044 M-2045 M-2046 M-2047 M-2048 M-2049 I

13 I DIAGRAM -

FUEL POOL COOLING SYSTEM I

f---l------------------+ --**------- -f-14 I 15 16 17 18 19 20 21 22 23 DIAGRAM -

RE:ACTOR BLDG, CLCSED COOLING

& EMERG. EQUF1* COOLING \\./ATER SYSTEM IIAGRAM -

DEM1N:::RALIZED SERVICE \\./ATER RISER SYSTEM DIAGRAM -

NUCLEAR BOILER SYSTEM DIAGRAM -

REACTOR \\;/ATER CLEAN-UP SYSTEM PHASE SEPARATORS CR\\JCU)

DIAGRAM - CJNDENSATE STORAGE SYSTEM DIAGRAM -

STATION AIR SYSTEM DIAGRAM -

'EED \\./ATER SYSTEM DIAGRflt,' -

REACTOR REC1RCUL.A TION SYSTEM (RRC)

DIAGR1'\\M -

RESIDUAL HEAT REMOVAL SERVICE

\\./ATER SYSTEM DIP.GRAM --

NUCLEAR BOILER SYSTEM M-2027 M-2678 M-2089 M-2088 M-20C6 M-2085 M-2023 M-2833 M-2C12 M-2090 24 25 S/J ERIS SIGNAL POINT #96 I-2174-31 26 27 28 INSTR. is CONTROL NOTES:

A, NONE DELETED B. NOTE DELETED C, NOTE DELETED

REFERENCES:

1. PIPING & INSTRUMENT SYMBOLS GE !97R567 Rl-25 2, LC:GEND OF SYMBOLS & INSTR !DENT DECO M-2001 FOR PLANT SYSTEM DIAGRAMS
1. THE El.EVATIDN OF THE DEMINERAL'.ZED 1,iATER AND PLANT AIR SUPPLY LINES SHALL BE A3JVE THE TOP OF THE STCRAGE TANK 2 THE ELEVATION OF THE STORAGE TANK SHALL BE ABOVE THE PUMP SUCTION TD ENSURE THAT THE SUCTION L'.NES ARE AL\\./AYS FLCCDED 3, IN ORDER TD SERVICE THE EXPLOSIVE VALVES AFTER FIRING IT IS NECESSARY TD REMOVE A 6' SPOOL ?IECE :MMEDIATEL Y UPSTRE'\\M OF THE RESPECTIVE VAL VE, EAC'"I EXPLOSIVE VAL VE IS FURNISHED \\./ITH A !'IAT,NG SOCKET \\./ELDING TYPE FLANGE FOR SJC:KET \\./ELDING TJ A 6' SPOOL PIECE, 4, THIS DIAGRAM REPLACES GENERAL ELECTRIC DIAGRAM ND, 729E601AB DECO FILE lt RI -3 5, THE PLANT IJ:ENTIFICATI N NUMBER FDR THE STANDBY LIQUID CONTROL SYSTEM IS C4100
6. SPECI,:-IC SYSTEM DESICN REQUIREMENTS ARE GIVEN IN THE SLC DESIGN SPECIFICATION NUMBER 3071-507
7. PIPING HEAT TRACE FROM STORAGE TAN.< (C4'.01AOOD TO VALVES FC04A AND =-004B AB/\\ND NED IN PLACE FDR C:NRICHED B R[N USE, PIPING LD'v/ TEMPERATURE ALARMS IN THE CONTROL R M ARE OPERATIONAL, REFER TO CECO FOR SETP INTS,
8. QA LEVEL I UNLESS N TC:L FDR PIPING NL Y. SEE CE:

FDR INSTRUMENiS AND EQUIPMENT CLASSIFICATION, 9, 'UNLESS THER\\./ISE SHD\\./N*

ALL INSTRUMENT PIS NOMBERS ARE PREFIXED C41 ALL VAL VE AND EQUIPMENT PIS NUMBERS ARE PREFIXED C4100'

10. TANK HEATER 'A' CC4IO!SOOD IS ABANcONED IN PLACE PER TSR-30753.

LEGEND 1

-=

J\\./G NO.

M----- I IDENTIFIES PIPING ISOMETRIC FDR FABRICATION AND ERECTION INC.CODE TITLE T

[ 6M721-2082 LATEST REVISION AB

~------------------------~

NUCLEAR SAFETY RELATED THIS IS A lvl!CROSTATION PRODUCED DRAWING.

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

Detroit Edison Fermi 2 DIAGRAM PREPARED BY DATE STANDBY LIQUID CONTROL SYSTEM H

G

}'

E D

C B

TC CHANGE DOCIJ'MENT CHECKED_,BY _

DATE l A OTHER REVISIONS:

APERTURE cARD TITLE I

/

8

?

6 5

4 C

CORRECTED DRA\\/ING RE 0 ERENCE AT DRA\\/!NG ZONE

  • a DIAG STANDBY LIOUID CONTROL H-5 PER MES09 S:"EP 3.1.2.4 APPROVED BY PA
  • PLANT IDENTIFICATION SYSTEM NUMBER

]

ARMS RECIPIE:NT #

REF, LCR 13-079-UFS, REV

  • C4100 DATE C

.~

JUSTIN /v.OSES 9-19-20

lot (JI~ A.N1oso5 PREPARED BY DATE 1vi-t1,~

AP~ROVED BY fo/l'/..,l,<./6t;j'~5' ~:,;,e:.

IJ_/,.n/J J

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7h(

..... ///~

'77..-fR.r' l':'D0::/,8 DATE

/,te(.A 3

EDP POSTING ENTR!Ef:I REQUJRE THE ADDITION OF THE ARMS STATO'S CODE:

EITHER

  • AFC" OR "ASB" OTHER APPROVALS 2

DOCUMENT TYPE CODE PATE I DDDMEC NUC OPS FILE NO.I DATE lSSUEt> TO r.s 1ao1

/a...J- /?

DRAWING NUMBER REV.

6M721--2082 AB 1