ML21055A267

From kanterella
Jump to navigation Jump to search
3 to Updated Final Safety Analysis Report, Drawing 6I721-2090-02, Rev. C, Logic Diagram Nuclear Boiler System
ML21055A267
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: ... further results
References
NRC-21-0002
Download: ML21055A267 (1)
v • d • e


Text

8 H

G F

E D

C B

A 8

llRY\\1£ll PRESSURE BUav TRIP PDINT PIS C71--N658A zrac H5

!PIS C7l-tfiSOCJ l.lf'l!I"-

PERMISSIVE WEN REACT!R VATER LEVEL IS AIIIVE LEVEL,

\\

LIS-N681A 11.IS-NGalCI LP

\\

I 6120!!1-3 zoo: H1 PERMMISIVE VHEN LDGIC "A~Cl ISatATDlN TEST SSITCH IN 'NORM" RMS CR PERMISSIVE WEN INIIIIARI IOOTIIIIARDI RESET SWITOl DEPRESSED I

\\

Pi 6110'!0*3 I/

lJll,ES B8,IB6]

~-~

I I

I I

I 7

AUXILIARY IEVICE ENERGIZED

<IOIW.l AUXILIARY IIEVlCE AUXILIARY DEVICE IE-ENERtilZED CR L -

.,"rc'.:=c:::.---1 AUXILIARY IIEVlCE

\\

DRYIIELL PRESWRE OCLDW TRIP PlllNT PIS C71--N650B ZONE H4

!PIS C71-ti£mll PERMISSIVE \\/HEN REACTOR VATER LEVEL IS AIIIIVE LEVEL 1 LIS-N681B ILIS-NGalDI LP

/

6l21l'lll-3 ZilH[ HI PERMISSIVE WHEN LOGIC "l'IDI ISILA TlaN TEST SVITCH IN 'N(llll' RMS CR I PERMISSIVE VHEN AUXILIARY IEVIC£

}

DlRGIZEI

~

\\

AUXILIMY lllNE F4

/.

I DEVICE I

I

_____ _J CLOSE PCRMS ISOLATION VALVES T50-F 450 [F 451l, T50-F 456 [F 4551 6

41-210D-l~ 1B2)

I C,

5 DRY\\IELL PRESSURE BELDV TRIP POINT PIS 1:71*N6:'M LP

£PIS C7M~SOCJ 612090-3 ZONE G2 PERMISSIVE W:N REACT[!!

VA TER LEVEL IS AIIIIVE LEVEL 3

\\

LIS-N680/i, Il!S-NGOO::J 1-8

/

\\

PERMISSIVE VH£N LIIGIC'A~Cl ISDLATIDN TEST S\\JITCH IN 'NORM' RMS CR PERMISSIVE VHEN INIIIIARI IDUTBDMII RESET SVITCH DEPRESSED I

\\~_PB--+-CR-=c'/.

612090-3 ZIINi Bll.lB61 4

DRYIIELL PRESSURE B£Lll\\l TRIP POINT PIS C7Hf650J WIS C71..ft650lll LP PERRMISSIVE VHEN REACTIJ?

VATER LEVEL IS AIIIIVE LEVEL 3 ZIIN[ H7 612090-3 ZONE 61

\\ llS-NGaOa llJIC J)7

/

ll.IS-N680ll PERMISSIVE VH£N LIIGIC'l'IDI ISDLATICN TEST SI/ITCH IN 'NIFM"

\\

RMS CR I PERMISSIVE VHEN AUXILIARY IEVICE ENERGIZED r--i

\\

AUXILIARY ZDNE n /

I IEVlCE I

I AUXILIARY DEVICE ENERGJZ[I I +----'-NDR..,HAl.l

_J AUXILIARY CR I

DEVICE I

I I

AUXILIARY DEVICE IE *ENtRGIZED L -

AUXILIARY DEVICE AUTO ISOLATION SIGNAL GROUP 13-ISOL. VALVE --

MIMJC DISPLAY H CLOSE DRY\\o/ELL EQUIP DRAIN VALVES -

[Gll-FOl9l Gll-FOl8 REF.8 3

2 1

H G

F

/ E

/ F r-- CLOSE TORUS WATER MANAGEMENT VALVES

<REF. 4I72l-2610-17,26,4!72!-2780-2,Al 41-2100-(\\]3 AUTO ISOLATl N SIGNAL

..-- GROUP 17-JSOL VALVE H CLOSE DRY\\o/ELL FLOOR DRAIN VALVES

[Gl!-F003l Gll-F600 REF.8 41-2160-7.i' B4 FUEL POOL EXHAUST RADJA TI ON-HIGH DIV.I [II] <REF.5l REACTOR BLDG.

EXHAUST RADIA TIN-HIGH DIV.I [Ill <REF.5)

MIMIC DISPLAY

,... CLOSE RECIRC PUMP SEAL WATER VALVES B31 -FOi 4A,BEB31 -F016A,B](REF.2l

,... CLOSE PRJMARY CONTAINMENT PNEUMATIC SUPPLY VALVES

<REF. 41721-2610-!7,26,41721-2660-D e--. START NIAS COMPRESSER,NORTH,DIV.J [SOUTH, DIV. !Il <REF.41721-2450-2)

/ cc 41-2100-14 jC2 '

DD 41-2100-14 JB2 HCLDSE PROCESS SAMPLE Ell-F079A,B [EU-F080A,Bl

( BB l

_ 612200-w

( JJ '

'-lWITHDRAW TIP SYS PROBES--~r-'~-:7:;-Tr's)

Vr, 612140~ z C5 c-* START SGTS DIV. I [Ill (REF. 41721-2610-17,61721-2640-l

{T46-F400 ET4B-F410.T46-F401,T46-F4121

'--- CLOSE DRYWELL & SUPPRESSJON POOL VENT SYSTEM VALVES T4803-F601 ET48-F408,T48-F407l

' ~ (REF. 61721-2650-12)

T4803-F602 ET46-F 41L T 46-F4021 INITIATE CONTROL CENTER A/C RECIRC. MODE WITH MAKE -UP T 4B-F 4o4 [T 4B-F 4o5, T 4B-F 4o9J

'\\.'.::.-1/-

,.._ A[R DIV.I [I!l.(REF. 61721-2610-15,41721-2610-17)

_. CLOSE NITROGEN INERTING SYS. VALVES

{ T48-F455 [T48-F453,T48-F454l

<REF. 6I721-2650-12)

T 48-F 457 ET 48-F 456,T 48-F 4581

-.,.. STOP REACTOR BLDG. SUPPLY & EXHAUST FANS. CLOSE VALVES T 41-F009J010 [T 41-FOOB,FOIIJ <REF.4172J-2610-L2,17,19l INBOARD ISOLATION LOGIC <EXCEPT MAIN STEAM)(NOTE 9)

TYPICAL FOR OUTBOARD OR AS NOTED. OUTBOARD DEVICES IN BRACKETS [ l REACTOR WATER LEVEL AIIIIVE LEVEL 3 LIS-1161lOA ll.lS*N680CJ LP PERMISSIVE WEN L[K;IC'A'ICJ ISDLATICN TEST S.w'ITCH IN 'Nl:RM'

\\

RMS CR

/

PERHISSIV[

IIHEN REACTflR PRESSURE JS Lill/

\\

PIS B3Hi611A

/

[PIS B3Hf611B1 LP PERMISSIVE WHEN JN![IARD muTBaMDJ RESET SWITCH IEPRESSED

\\

PB 6120!!1* 3 I/

ZllNE llll.[B6J

~--~

I I

I I

I AUXILIMY IIEVIU: ENERGIZED (NIJ?IW.J AUXILIARY DEVIU:

AUXILIARY DEVICE IE-ENERGIZED CR L -

.,'r.:::;;:;;;:;-,--

AUXILIARY DEVlCE I

REACTaR WATER 1£VEL AOOVE 1£Va 3 LIS*N680B lLIS-ll6811Dl LP PERMISSIVE WHEN LllGIC'B1Dl ISIJLATIIIN TEST SVITCH IN 'NIRK'

\\

RMS CR

/

/

PERMISSIVE WHEN AUXILIMY DEVICE ENERGIZED r--i AUXILIARY ZllNE B4 I I DEVICE I

I

_____ _J CLOSE RHR SUCTl N Ell-F009 [Ell-FOOBl CLOSE RHR HEAD SPRAY Ell-F022 [Ell-F0231 -

RHR INBOARD ISOLA TJON LOGIC TYPICAL FDR OUTBOARD EXCEPT DEVICES IN BRACKETS [ l 7

(

A 412100*~

(

B 412200*~

AUTO !SOL SIGNAL GROUP 4

,q,~---- IS!ll. VALVE

  • ( pp 611200-~8

( MM 612200-w 6

MIMIC DISPLAY LOGIC j

REACTOR WATER LEVEL AOOVE LEVEL 3 LIS-N68M

[LIS-N68<1Cl ZllNE 18 PERMISSIVE VHEN LIIGIC'A'ICJ ISDLATICN TEST SVITCH IN 'NllRM' REACTflR WATER LEVEL !BOVE LEVEL 3 LIS*N611Ji ILIS*N68<1Dl ZIIN[ D7 PERMISSIVE

\\IHEM LEK;IC'~lDJ ISIJLATlllN TEST SVITOl JN 'NORM'

\\

RMS CR

/

\\

RMS CR

/

I

\\

PCRMISSIVE

\\/HEN INBIJARD IIIJTBDMDJ RESET

/

PERMISSIVE

,tt[N AUXILIARY DEVICE SWITCH D£PRESSED PB 612891-3

/

ZIIN£S B8.IB6J ENERGIZED

~

\\

AUXILIMY ZDNE 87

/

. i DEVICE 5

I I

AUXILIARY DEVIC£ ENERGIZED r +----(N[IR-,MAL_> _____ -

_J I

I I

I AUXILIARY DEVICE CR t;JXILIARY IEVICE IE -ENERGIZED L -

  • -t--:::::-cc-.---,

AUXILIARY DEVICE CLOSE

~--; RHR INJECTl N Ell-f0!5A,B RHR ISOLA TJON LOGIC El!-F015B DEVICES IN BRACKETS [ l 4

j C DCD'S INCORPORATED:

N/A NOTES

1.

SEE 61721-2090-1 FOR NOTES, REFERENCES, AND LEGEND.

c0 J

161721--2090-02 C

LATEST REVISION NUCLEAR SAFETY RELATED

'I'HIS DRAWING WAS REFORMATTED BY AU'l'OCAD AT REVISlON C. ALL PREVIOUS.U'PROVAL SIGNATURES ARE:

ON FILE ON MICROFILM IN DOCUMENT CONTROi.

A PORTION OF THIS DRAWING lS AJ'J'ECTED BY THE FOLLOWING:

PREPARED BY INC.CODE u

TITLE DATE 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 LOG IC DIAGRAM NUCLEAR BOILER SYSTEM E

D C

B TC CHANGE DOCtna:N"l' CHECKED BY DATE l----=cc:,,---------1---+-------.~=~~---,1------------------_,A OTHER REVISIONS:

APERTURE CARD TITLE AT ZONE E-4* CHANGED DRA\\J]NG REF. TO 1-2140-7.

LOGIC DIAG NB SYSTEM AT ZONE B-2* REMOVED SUPERSEDED VENDOR DRAWING NOT( 2.

APPROVED BY PLANT lDENTJF(CATION SYSTEM NUMBER REF. DBD OPEN ITEM EllOD-OIO AND LCR 94-064-UFS.

B21 QQ PREPARED BY T, MI l:il Al',.

APPROVED BY I.DATE I CHEC.Y DATE 4-22.-94 DATE EDP POBTING Bl'JTRIES Rl!lQUIRR THE ADDI'l'ION OF THE ARMS STATUS CODEl EITHER

  • AFC OR ~ ASB" DOCUMENT TYP. CODEDDDINC NUC OPS FILE NO.

OTHER APPROVAU!i DATB:

1801 DR.<WING NUMBER 61721-2090-02 I

1 ARMS RECIPIENT#

REV, C
Retrieved from "https://kanterella.com/w/index.php?title=ML21055A267&oldid=3822144"