ML21055A202

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3 to Updated Final Safety Analysis Report, Drawing 6I721-2230-01, Logic Diagram Reactor Core Isolation Cooling System
ML21055A202
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: ML21055A202 (1)
v • d • e


Text

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SEAL.. IN AUXILIARY ZCNE C7 CJNT. 721

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WITCH ON VALVE PERMISSIVE

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REACTOR VESSEL I I SI/ITCH B21N692A DR B21N692B LEVEL 2 TRIP LEVEL 2 T'1P AND B2IN692C OR B21N692D TO START SYSTEM I

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LIS B21 N692A LP REACTOR VESSEL LEVEL 2 TRIP US B11 N692C LP REF l ciS B11 N691B LP REACTOR VESStl LEVEL 1 TRlP LIS B11 N692D LP I

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AUTO ISOLATION SIGNAL j SEE NOTE I SEAL-1" AJXILIARY CGNT. 721 ZONE C7

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LIMlT ON S1JITCH VALVE SEAL -lN AUXlllARY cNi. 721 ZONE CJ j AUTO. !SOL. SIGNAL---~.

GROUP 8-ISDL. VAL VE MIMIC DISPLAY K

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VAL VE UMIT WITCH VALVE FULLY CLOSED LIMIT S'wlTCH ON VALVE 4--GROUP 8 IS L. VA MIMIC DISPLAY M

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LVE PERMISSIVE 'JH(N VALVE IS:

< 10oz OPEN

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UMlT S~lTCH ON VALVE PERMISSIVE UNLESS VAL' YERTQRQUE IJHILE OPDll

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AUTO ISOLATION SIG. (NOTE 1)

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E>ERGENCY I

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HIGH TEMPERATURE I

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'TEST'

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RMS CR

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PERMlSSlVE UNLESS BYPASSED Al !EMOTE SHUTDliN PANEL

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PERMlSSIVE SHEN RSP TRANSFER SVlTCH IS 'ON' POS!TIGN

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TRANSFER SVITCH RSP

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LEAK DETECTlON BY'ASS

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PERMlSSlVE UNLESS BYPASSED AT REMJTE SHUTDDVN PANEL SELECTOR RSP WllCH PERMISSIVE 'JHnl I

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'OPEN'

'CLOSE' PUSHDUTT N PUSHBUTTON SEAL-111 WITCH IS SVJTCH IS (BY AD rEPRESSED DEPRESSED PB CR PB CR AUX ZCNE Bo i

CONT. 42t PERMISSIVE UNLESS

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VALVE

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OPEN CLOSE AC RE:VERS[NG Cl)ITACTOR ~21

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STEA~ SUPP~ Y LINE ISOLI\\Tl N V,~LVE MO E5150F007 SEE NOTES 2 & 5 5

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GROUP 8

!SOL. VOLVE MIMIC DISPLAY E IDCD'S INCORPORATED EDP-34041.B003, REV. ¢ OTHER REVISIONS:

PREPARED DY 1,1 J ADLER APPROVED BY

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DATE I cHtcfSeyi ijY 4/27/'.)9

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NUCLEAR SAFETY RELATED ti.ATE

<f/U:/o'f l DATE THIS DRAWING WAS REFORMAITED BY MtCROSTATION AT REVISION "E. AIL PREVIOUS APPROVAL SIGNATURES.ARE ON FILE ON MICROFILM IN DOCUMENT COl'ITROL TC A PORTION OF THIS DRAVl1NG lS AFTECTED BY THE FOLLOWING:

CRANCE DOCUMENT PREPARED BY CHE;CKE;J:;J_)c!Y

---+----------------;

.. __.. Af>PRtivt:D-BY EDP POSTlNG ENTRIES REQUIRE THE ADDITION OF THE ARMS STATES CODE:

El1'HRR

  • AFC" OR '" ASS" OTHER APPROVALS 2

1 NOTES:

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THE RCIC SYSTEM IS ARRANGED FOR TEST OF PUMP AT FULL FLO\\./ & ALL VALVES FOR OPEN &

CLOSE CAPABILITY AT ANY TIME EXCEPT

\\/HEN INITIATION SIGNAL OR AUTO ISOLATION SIGNAL IS ACTIVATED IN EVENT THE INITIATION SIGNAL OCCURS VHILE TEST IS UNDERVAY, THE SYSTEM AUTOMATICALLY RETURNS TO STARTUP MODE.

2.

ALL POI/ER FOR OPERATION OF DC. VALVE MOTORS SHALL ORIGINATE FROM A PLANT D.C.

BUS. PDVER FOR AC OPERATED SHALL ORIGINATE FROM AN EMERGENCY A.C. BUS.

3. 'UNLESS OTHER\\/ISE SHVN, ALL INSTRUMENT PIS NOs. ARE PREFIXED ES!

ALL VALVE AND EQUIPMENT PIS NOs. ARE PREFIXED E5l00

4.

ISOLATION SIGNAL SVITCHES SHALL BE OF THE TYPE THAT CLOSE CONTACTS FOR THE SPECIFIED ISOLATION EVENT. VHERE AUXILARY RELAYS ARE USED IN THE ISOLA TIDN CHANNELS THEY SHALL BE PO\\IERED FROM THE STATION BATTERY SO THAT THE LOSS OF AC POVER DOES NOT CAUSE AN ISOLA fl N TRIP

5.

AUXILARY RELAYS & DEVICES NOT SHO\\IN ON FUNCTIONAL CONTROL DIAGRAMS EXCEPT \\,/HERE REQUIRES TO CLARIFY FUNCTION.

6.

DELETED

7.

FLRNISHED \\,IITH TURBINE.

8.

DELETED

9.

THE RCIC SYSTEM SHALL BE DESIGNED IN ACCORDANCE \\JITH PROPOSED CRITERIA FOR t!UCLEAR POVER PLANT PROTECT:ON SYSTEM IEEE -279 INSCFAR AS PRACTICABLE.

10. FOR LOCATION, IDENTIFICATION AND SET POINTS oc INSTRUMENTS SEE THE MASTER INSTRUMENT LIST.

11 FOR CONFIGURA TI N OF PANEL MOUNTED OPERA TORS AND INDICATORS SEE D\\,IG, 6M-2290 SH2, REF 12 PURCHASE SPECIFICATION DATA SHEET SECT, 2.4.

12 ALL MOTORS SHALL BE PROTECTED BY THERMAL C\\/ERLOAD TRIPS AND BREAKER SHORT CIRCUIT CURRENT PROTECTIVE TRIPS.

REFERENCE DOCUMENTS:

1 NUCLEAR BOILER P&ID--------------- M-2089, M--2090, M-5538

2.

NUCLEAR BOILER MISC. SYSTEM LOGIC DIAGRAM- -- -I -2090-01

3.

RHR S~STEM LJGIC DIAGRAM--------------

- ------ 1-2200-01

4.

CORE SPRAY SYSTEM LOGIC DIAGRAM--------------1-2210-01

5.

HPCI SYSTEM LOGIC D!AGRAM---------------------1-2220-01

6.

RCIC SYSTEM P&ID--------- -----------M-2044, M-2045

7.

LOGIC SYMBOLS-----------------------209A4756J R!-20

8.

TURBINE CONT. SYS & ELEC V!RfNG--------------

TERRY "URBINE VENDOR MANUAL #E51-0l-C-002-J4-002 9

REACTOR \\/ATER CLEANUP SYS P&IO-----M-2046, M-2047

10. LEAK DETECTION SYSTEM DESIGN SPACE---------22A1441; Rl-138
11. ELEC EQUIP SEPERATIDN

,- R SAFEGUARD SYS.---------------------22A3777, Rl-1410 12 GENERAL R:QUIREMENTS FOR INSTRU-MENTATION & ELEC EQUlP.------------21A1768; Rl-446, 448 13 RCIC SCHEMATICS

-- l-2231-01 THRU IO I-2235-0l THRU 11 14LOGIC DIAGRAM-GROUP 8-RCIC ISOLATION VAL VE MIMIC DISPLAY-------------------1-2230-07 15LOGIC DIAGRAM-GROUP 9-RCIC ISOLATION VAL VE MIMIC DISPLAY-------------------! -2230-08 LEGEND:

CMC PB AM

  • RSP RMS cP CR COORDINATED MANUAL CONTROL S\\,IITCH PUSHBUTTON S\\IITCH AMMETER SVITCHGEAR DEVICE FUNCTION NUMBERS ANS] SPEC C37.2 REMOTE SHUTD0 1JN PANEL REMOTE MANUAL SVITCH LOCAL PANEL CONTROL ROOM & RELAY ROOM i 61721-2230- 01

,... i=---===cc----

=?RVT~mN LATEST ___,._, ___

E THIS DRAWING SUPERSEDES EDISON'S SITE MASTER (VENDOR DRAWING 729E622AB SHT 1 REV S) OF EDISON Fil_E NO.Rl -151 INC.CODE THIS IS A lv!ICROSTATIO'f PRODUCED DRAWING.

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

Detroit Edison Fermi 2

--- --**----t=,.--------------------------1 TITLE u

DATE DATE:

LOGIC DI_A.GRA1'I REACTOR CORE ISOLATION COOLING SYSTE1'1 H

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D C

B I APERTURE CARO TITLE

! A PATE LOGIC DIAG RCIC SYSTEM PLANT ID~NTH'lCATIO:N SYSTEM NUMBER E5100 DOCUMEN1' TYPE CODED DD INC NUC Of'S Fn.E NO.

1801 DRAWING NUMBER 61721 _ 2230 _ 01 1

ARMS RECIPlEN'l' #

DATE ISSUED TO IS 5 \\.

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