ML21055A288

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3 to Updated Final Safety Analysis Report, Drawing No. 6I721-2126-01, Instrument Diagram Feedwater Control System
ML21055A288
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: ML21055A288 (1)


Text

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NOTES,
1.

ALL EQUIPMENT AND INSTRUMENTS ARE PREFIXED BY SYSTEM ND. C32 UNLESS THER\\./ISE SPECffiED.

2.

FDR LOCATION & IDENTIFICATION F INSTRuMENTS SEE CECO. 4 FDR INSTRUMENT RANGES & SETP INTS SEE CECO.

5.

6 THE POWER SOURCE FDR TfcE FEEDVATER INSTRUMENTATI N AND CONTROL SYSTEM SHALL HAVE AT LEAST THE SAME DEGREE F RELIABILITY AS "HE POWER SOURCES FDR THE REACTOR/BOOSTER/CONDENSATE PUMPS. _ l --- _ _ l __ Cl-2174-15.:_ _ --- __ t - _t,, __ ----L I L t AC/CUSTOMER SHALL PROVIDE -w NORMALLY PEN CONTACTS PER TURBINE DRIVEN REACTOR FEED PUMP TD OPERATE \\./HEN TURBINE FEE~ PUMP UNIT HAS TRIPPED OR BEEN SHUTDOWN. THE CONTACTS SHALL PREFERABLY BE DERIVED FROM A FLO\\./ SWITCH MOUNTED ACl,CSS THE R.FP. LOW FLOW RECIRCULATION FLO\\./ ELEMENT PROVIDED BY THE AE/CUST MER DR R.F.P. DISCHARGE VALVES IF THESE AUT MATICALL Y RUN CLOSED ON R.FP. TRIP G.E. (APED) REQUIRE THESE CONTACTS FDR INITIATION OF REACTOR RECIRCULATION PUMP RUN B.ACK IN EVENT OF A 1 UT OF 2 R.F.P. TRIP AT HIGH LOADS. -t I .I. - - - - TD STARTREC I PNL H11P919 I POINT #87 r I I I 1-1 I -r-- [321<669 DCS-Fw (CO!'\\JTINUED) r I I I I I r I I I 1- - I I I I I

7.

DELETED.

8.

DELETED. 9 DELETED.

10. PROCESS COMPUTER TD COMPUTE SQUARE R T AND PROVIDE DENSITY C MPENSATl N.

11 SEE DRAWING I-2105-21 FDR C NF.IGURATI N DETAILS,

12. FLAT PANEL DISPLAY IS COMMON TD F\\./CS AND RRSC.

REFERENCE DRAV!NGS,

l.

FEEDWATER CONTROL SYSTEM DESIGN SPEC *- *- - GE 22A3086

2.

NUCLEAR BOILER SYSTEM P&ID - - M-2089,2090 I I I I I I cr-2042-13> I I i REACTOR XRESS ~ 3Dl68 t- - - - TD STARTREC I I I I I I I <J; I CR u 6 CR CR I / / ~ POST SCRAM

3.

REACTOR RECIRCULA Tl N SYSTEM P&ID - M-2833, 1-2106-01, 02 I I £ A156 I FL V I I ,i-i I 'l': I I I I I I I I I I I I -+--*'-' t

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I r I V:!!'_ NOTES, 1. ' /LCV'\\ 1v1c.-e~1.L;(;,:--:,; I I,_ e SEE REFE.RENCE :___J ALL DEVICES ENCLOSED ABOVE ARE PREFIXED WITH SYSTEM ND. N21. I I I I I I l LOSS OF RFP 'A' CCNTACT FSEN21N436A I L--/4-4, REF. 15 < LOSS OF RFP 'B" CONTACT FSEN21N436B I L - -<E-3, REF. 15 < PNL H11P919 PCINT #81 (]-2042-14) r--------------------- ---------------------7 SIGNAL 1-- INPUT SIGNAL --1 SIGNAL I CONVERTER DIVIDER CNVERTE~ I I AMPLIFIER H t I i~~Gf ~6----J L w SIGNAL SELECTOR MOTOR PER P TENTl METER ACTUATOR CONTROL SERVO AMPLIFIER PD\\./ER SERVO AMPLIFIER I I I I I 7 I I I L---o~ i~~Gf 1 MANUAL CONTROL ,EF. 7 & 8 __________________________________ J NORTH RFPT CONTROLS .I._ TD STARTREC I - PNL HllP919 PD!NT #82 (]-2042-14)

______ l ______ 7 SOUTH RFPT CONTROLS IDENTICAL TD NORTH L _____________ _J DCS FAILURE 3D164 i

FwCS/RRSC DCS CONSOLE (NOTE lD I I FLAT Pl\\NEL DISPLAY F'w & RR CN TE 12) s iDCD'S INCORPORATED: POST SCRAM LJGIC H11P634 -1JL.. K816

4.

CONTROL ROD DRIVE HYDRAULIC SYSTEM FCD - M-2081 POST 1.0GIC ACTUATED SCRAM 3D157 SETJD\\./N

5.

EEED\\./ATER SYSTEM P&ID -- *-* - M-2023

6.

MAIN TURBINE GENERATOR TRIP LOGIC ELEM. - - - I-2339-2

7.

RFP TURBINE SPEED CONTROLLER MECH DIAG. - EDISCN FILE S23-111

8.

RFP TURBINE SPEED CONTROLLER w!RING DIAG. - 1-2313-03 & 04

9.

INSTRUMENT SYMB cs ---------*.,.,, ______ GE 921-D280 (Rl-404)

10. PIPING & INSTRUMENT SYMBOLS -

EDISON FILE Rl-25

11. REACTOR FEED PUMP I URBlNES TRIP LOGIC ELEM *-* -
    • 1-2339-04
12. MAIN AND REHEAT STEAM SYS DIAG. - -

M-2002

13. REACTOR RECIRCULATION PUMP SPEED CONTROL DIAG.- 1-2106-02
14. INDEX c* R STARTREC P INTS ----------- 1-2042-01 & 02
15. DIAGRAM CONDE~SATE SYSTEM -

UNIT 2 - - M-2004-1 61721-2126-01 LATEST REVISION s LEGEND

  • - EQUIPMENT SUPPLIED BY OTHERS. <NOT GD

£ - CCMPcTER ANALOG INPUTS. ~ NET POSITIVE SUCTION HEAD. START-UP CONTROL VALVE <THROTTLING TYPE VALVE>. THIS DRAWING WAS REFORMATTED HY MICROSTATION AT REVISION "S". ALL PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON MICROFILM IN DOCUMENT CONTROL. A PORTION OF THIS DRAWlNG IS AFFECTED HY THE FOLLOWING: PREPARED BY INC,CODE T DATE TITLE NUCLEAR SAFETY RELATED THIS IS A :\\!ICROSTATION 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 INSTRUMENT DIAGRAM FEEDWATER CONTROL SYSTEM H G F E D C B I TC CHANG-E DOCUMENT CHECKED BY DATE I A 10THER REVISIONS: APERTURE CARD TITLE I 7 R f') 4 CORRECTED TYPO PER PEPS-0019, B21M005 SHOULD BE B21N005. INST DIAG FEEDWATER CNTRL SYS I REVISED ABANDONED IN PLACE NOT A TIDN AT ZONE G-6, APPROVED BY D-t\\Tl!;, -- PLANT IDENTIFICATION SYSTEM NUMBER I ARMS RECIPIENT# I LCR 19-012-UFS REMOVES FIGURE FROM UFSAR C3200 PREPARED BY \\/J ADLER APPROVED BY DATE j CHECKED BY 3-23-18 David Knkoczki forT. Murphy Ill ~ DATE EDP POSTING ENTRIES REQUIRE TIIE ADDITION OF THE ARMS STATUS CODE: EITHER "AFC" OR "J.SB" OTHER APPROVALS 0 NUC OPS FILE NO.I DA'l'E ISSUED TO IS DATE rno1 I 3/1:1,/?.014

DOCUMENT TYPE CODED DD INC DRAWING NUMBER 61721-2126-01 REV. s 1}}