ML21055A287

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3 to Updated Final Safety Analysis Report, Drawing No. 6M721-2083, Diagram Residual Heat Removal (RHR) Division 2
ML21055A287
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: ML21055A287 (1)
v • d • e


Text

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l. THE METHOD or MOUNTING LOCAL INSTRUMENTS IS TO BE DETERMINED BY EDISON.
2. PIPING HIGH P INT VENTS AND LO\\J P INT DRAINS ARE TO BE ADDED AT ALL SUCH HIGH POINTS DR LO\\/ POINTS NOT SERVED BY EQUIPMENT VENTS DR DRAINS.
3. CHEMICAL CLEANING CONNECTIONS ARE TD BE PROVIDED AS NECESSARY & \\JILL BE QA LEVEL 'NONE'.
4. DISCHARGE LINES FDR CODLING \\JATER T BE ROUTED UPSTREAM OF SERV[CE 'w'ATER RADIATION MONITORS.
5. ALL POSITION INDICATING LIGHTS ARE LOCATED IN CONTROL ROOM UNLESS OTHER'-'ISE NOTED.
6. ALL MOTOR PERA TED VAL YES ARE A.C. OPERATED UNLESS OTHER'w'ISE NOTED.
7. ALL VENTS & DRAlNS ARE 3/4' UNLESS THER\\JISE SPECIFIED.
8. DELETED
9. DELETED
10. REFERENCE DOCUMENTS TlTLE DEC FILE ND GE ND REV (A) DESIGN SPECIFICATl N

<B) RHR SYS PROCESS DIA (C) RHR SYS P&ID 3071-503 Rl-24 RI-70 729E623AB 729E602AB 3 6

11. THE PRIMARY AND SECONDARY PIPING SYSTEMS ARE QUALITY LEVEL EXCEPT AS F LLD\\JS, A. 'w'HERE OTHER'w'ISE NOTED.

B. ALL VENT AND DRAIN LINES SHALL CHANGE TD QUALITY LEVEL III AFTER THE FIRST SOURCE VALVE.

12. VALVES VS-2546 & 2547 ON THIS SHEET & VS-2548 & 2549 ON M-2084 ARE DOUBLE ACTING \\JlTH DUAL COIL SLENlDS. VALVES FAIL 'AS IS'. ON LOSS OF P 'w'ER POSITION INDICATION IS IN THE CONTROL ROOM.

lJ. [ M-D'w'G ND l IDENTIFIES PIPING ISOMETRIC DRA\\./ING F" R AND ERECTI N. FABRICATION

14. FOR TRANSMITTER PD\\./ER SUPPLY S. TRIP UNIT SEE TABLE ON 0\\./G M-2084.
15. NOTE REMOVED.
16. OPEN B. CLOSE BACKLIGHTED PUSHBUTTONS \\./ITH RED 8. GREEN INDICATING LIGHTS AT REMOTE SHUTDO\\./N PANEL H21Pl00.
17. INSULATION CLASS "RW MOTOR REPLACED \\JITH CLASS NB* PER EDP-4874.
18. OPEN & CLOSE BACKLIGHTED PUSHBUTTONS \\JITH RED & GREEN INDlCATING LIGHTS AT DEDICATED SHUTDO\\JN PANEL H21P625 FDR MD F009.
19. ABANDONED IN PLACE PER ABN 13861-l.
20. ABANDONED IN PLACE PER EDP-29021.
21.

THESE LOCATIONS ARE REQUIRED TD HAVE A UT EXAMINATI N PERFORMED F LLD',/lNG DRAINING AND Flll AND VENT TO VERIFY THAT ND VOIDS ARE PRESENT. THE F LLD'w'ING PST EVENTS APPLY. SEE THE PST EVENT FDR THE SPECIFIC AREAS TD BE EXAMINED. A. UPSTREAM OF Ell50F017B-PST EVENT 2904 B. UPSTREAM OF Ell50D011B-PST EVENT 2904 C. UPSTREAM OF EU50DOl3E-PST EVENT 2904 D. DD\\JNSTREAM OF El150F006B-PST EVENT 2904 [. D0\\JNSTR[AM OF El150F006D-PST EVENT 2304 INSTRUMENT~ CONTROL NOTES, A. ~UNLESS THER\\./ISE SHO\\o/N, ALL INSTRUMENT PIS N s. ARE PREFIXED El1 ALL VAL VE AND EQUIPMENT P!S Ns. ARE PREFIXED EtlOO

8.

THERE ARE TWO KEYLOCK SWITCHES FOR VALVE E1150F608. ONE KEYLOCK SWITCH IS LOCATED IN THE MAIN CONTROL ROOM ON H11 P602 ANO ANNUNCIATES WINDOW 2D43 Vv'HEN NOT IN THE,.LOCK'* POSITION. THE OTHER IS A LOCAL KEYLOCK SWITCH ON R1600S005C (MCC 42F-4A, POS 4D-R) WHICH PROVIDES A PERMISSIVE FUNCTION TO OPEN THE VAL VE WHEN PLACED IN THE "OPERATE" POSITION. THE LOCAL SWITCH HAS NO ANNUNCIATION. C THERE ARE TWO KEYLOCK SWITCHES FOR VAL VE E11F6108 ONE SWITCH (2B225) IS LOCATED IN THE MAIN CONTROL ROOM ON H11P602, THE OTHER (E11M001B) IS LOCATED ON THE 1ST FLOOR OF THE REACTOR BUILDING IN BOX E11P4048. THE LOCAL SWITCH PROVIDES A PERMISSIVE F'UNCTION TO OPEN THE VAL VE WHEN PLACED IN THE "OPERATE" POSITION. THE LOCAL SWITCH HAS NO ANNUNCIATION. RE,ERENCES

1. PIPING & INSTRUMENT SYMBOLS G.E. l97R567-Rl-25.

6M721-2083

2. LEGEND OF SYMBOLS 8, INSTRUMENTS IDENT. DEC M-2001 FDR PLANT SYSTEM DIAGRAMS.

LATEST REVISION cc

3. REACTOR PROTECTION SYSTEM I-2156-01 AND I-2156-02.

INC CODE T PREPARED BY DATE CHECKED BY DATE ~PROVED BY OTH!:R APPROVALS 2 TITLE 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 DIAGRAM RESIDUAL HEAT REMOVAL (RHR) DIVISION 2 APERTURE CARD TITLE DIAG. RESIDUAL HT REMOVAL DIV 2 PLANT IDENTIFICATION SYSTl!:M NUMBER E1100, E1150, E1155, 82100 ARMS RECIPIENT # DOCUMENT TYPE CODE ME I NUC OPS FILE NO, DDD C ,ao, DATE ISSUED TO IS 7-/0***.)-U DRAWING NUMBER 6M721-2083 REV. cc 1 G F E D C B A}}

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