ML21055A122

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3 to Updated Final Safety Analysis Report, Drawing 6I721-2156-01, Rev. s, Instrument Diagram Reactor Protection System (Part 1) C71
ML21055A122
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: ML21055A122 (1)


Text

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18 NOTES: DEVICES USED IN TRIP SYSTEM 'A' ARE IDENTIFIED BY LETTERS A, C, E, G, ETC. THOSE USED IN TRIP SYSTEM 'B' ARE B, D, F, H, ETC. SYSTEM SHALL BE ARRANGED SD THAT THE BUS CANNOT BE ENERGIZED FROM THE M-G SET AND ALTERNATE SOURCE SIMUL TANE USLY, l NE RESET SwITCH SHALL BE USED FDR BOTH TRIP SYSTEMS A AND BAND SD ARRANGED THAT NE ACTUATION OF THE Sw!TCH will RESET ALL SCRAM PILOT VALVES (A AND B) IN GROUP 1 AND GROUP 4 AS wELL AS BACKUP SCRAM VALVE A. A DIFFERENT ACTUATION F THE Sw!TCH w!LL RESET ALL SCRAM PILOT VALVES <A AND B) IN GROUP 2 AND GROUP 3 AS \\JELL AS BACKUP SCRAM VALVE B ACTUATI N F THE Sw!TCH TD BOTH GROUP 1-4 AND GROUP 2-3 P SITI NS SHALL BE REQUIRED BEFORE THE CRD DRAIN AND VENT VALVES RESET. THE RESET Sw!TCH SHALL BE SD CONSTRUCTED THAT RPS CHANNELS A2 AND B2 ARE PHYSICALLY SEPARATED FROM CHANNELS Al AND Bl. MAIN STEAM LINE IS LATI N VALVE CLOSURE TRIP SHALL BE ARRANGED SO THAT ANY ONE STEAMLINE MAY BE ISOLATED (BY FULL CLOSURE F ITS IS LATI N VALVES) AND THE IS LATl N VALVE FDR ANY ONE OTHER STEAM LINE CAN BE CLOSED <MORE THAN 10%) w!TH UT CAUSING A RPS SCRAM. LOGIC FDR THE 'TURBINE STOP VALVE CLOSURE' TRIP SHALL BE ARRANGED SD THAT CLOSURE OF 3 UT OF 4 STOP VALVES w!LL CAUSE A RPS SCRAM. PROVISION SHALL BE MADE TO ALL w CLOSURE OF NE STOP VALVE (FDR TEST PURPOSES) w!THOUT CAUSING A TRIP OF EITHER TRIP SYSTEM A DR B. TRIP CHANNELS FDR THE 'TURBINE CONTROL VALVE FAST C~ SU.~E' TRIP SHALL BE DERIVED FRO~ THOSE E\\/EI\\/TS CAUSING F ;.sr CLOSURE OF THE CONTROL VALVES. NOTE DELETED. THIS SIGNAL, wHEN ABSENT, DE-ENERGIZES THE SCRAM C NTACT R. y y y y y y y ( NOTE DELETED. 0 UNLESS THERw!SE SHOwN, ALL INSTRUMENT PIS NUMBERS ARE PREFIXED C71. ALL VALVE AND EQUIPMENT PIS NUMBERS ARE PREFIXED C7100 FDR L CATI N AND IDENTJFICATIN OF INSTRUMENTS SEE CECO, SELENIUM THYRECT R SUPPRESSORS (OR EQUIVALENT) SHALL BE USED TD SUPPRESS ELECTRICAL ARCING OF SCRAM SOLENOIDS. THE DISCHARGE VOLUME HIGH LEVEL BYPASS Sw!TCH SHALL BE SO CONSTRUCTED THAT RPS CHANNELS Al AND Bl ARE PHYSICALLY SEPARATED FROM CHANNELS A2 AND B2, SHEET 2 OF THE GENERAL ELECTRIC DwG, 732El81 wAS REPRODUCED AS I-2156-03 &-04 THIS DRAw!NG DOES NOT SHD\\./ ALL DEVICES IN THE SCRAM VALVE PILOT AIR HEADER. SEE REF. 4 AND 19. THIS DRA\\./ING SH ws DEVICES CONTROLLED BY THE REACTOR PR TECTl N SYSTEM. FOR PROCESS COMPUTER INPUT POINTS SEE DI.JG 1-2155-14, FDR INDICATI N OF SCRAM DISCHARGE VENT & DRAIN VALVES SEE NOTE 33 F REFERENCE 4. ADJUSTABLE TIME DELAY (0-30 SEC) FUNCTIONS TD ENERGIZE VALVES C11F409A & Cl!F409B FDR OPENING VALVES CllOOFOlO ~ CllOOFOll i 61721-2156-01 INC.CODE TITLE T

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LATEST I ** ---*-** NUCLEAR SAFETY RELATED THIS IS A MICROSTATION 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 H G F E D C B PREPARED BY DATE INSTRUMENTDIAG RAM REACTOR PROTECTION SYSTEM (PART 1) C71 CHECKED BY DATE

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D REACT PROT SYSTEM SHT 1 AF'~~ VED BY PLANT IDENTIFICATION SYSTEM NUMBER I ARMS RECIPIENT# C7100 DATE SSU TD IS PREPARED BY A DITTMAN DATE 9/10/18 ~ 1-/4 10-;-1( OTHER APPROVALS DATE DOCUMENT TYPE CODED DD INC NUC OPS FILE NO.* 1801 0 tli' DAll to/<fl/41 8 7 6 5 4 3 EDP POSTING ENTRIES REQUIRE THE ADDITION OF THE ARMS STATUS CODE: EITHER "AFC" OR ~ASE" DRAWING NUMBER ? RE 61721---2156-01 s 1}}