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Category:Drawing
MONTHYEARNRC-23-0062, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-10-12012 October 2023 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 ML22325A1542022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Figures (for Public Use) ML21055A3012021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2512, Side Stream Lrwp System P&ID ML21055A3382021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-3045, Diagram Main Steam Isolation Valve Leakage Control System ML21055A3372021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-01, Rev. AC, One Line Diagram, 120VAC Inst. & Cont., Power Feeders Division 1 & 2 Reactor Building ML21055A3352021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4953, Radwaste Building Heating Ventilating and Air Conditioning Flow Diagram ML21055A3342021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721TS-2002-3, Technical Support Center Miscellaneous Diagrams of HVAC Systems ML21055A3332021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721N-2050, P & Id Equipment Drains & Floor Drains Divisions I & II R.H.R Complex ML21055A3322021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5861, Process Diagram Core Spray System ML21055A3302021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-10, One Line Diagram 260/130V Ess Dual Battery 2PA Distribution - Division I ML21055A3292021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-11, One Line Diagram 260/130V. Ess. Dual Battery 2PB Distribution - Division II ML21055A3282021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4945, Piping & Instrumentation Diagram Fill Station Auxiliaries, Cooling Water Booster Pumps ML21055A3272021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2500-01, One Line Diagram Plant 4160V. & 480V. System Service ML21055A3262021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5875, High Pressure Coolant Injection System-Simplified Drawing Test Mode During Plant Operation ML21055A3252021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6A721-2402, Fire Protection Evaluation Reactor and Auxiliary Buildings Basement - Plan - El. 562'-0 ML21055A3242021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2833, Diagram Reactor Re Circulation System Nuclear Boiler System ML21055A3232021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5668, Core Spray - Accident Condition ML21055A3222021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5007, Diagram Primary Containment Pneumatic Supply System ML21055A3202021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2711, Flow Diagram Air Conditioning & Ventilation Radwaste Control Room & Health Physics Lab ML21055A3192021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4100, Diagram Torus Water Management System ML21055A3182021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2510-01, Rev. BC, One Line Diagram 480V E.S.S. Bus 72B, 72C, 72E, & 72F ML21055A3172021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5538, System Diagram Nuclear Boiler System Instrument Information Tables ML21055A3142021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721N-2047, P&ID Diesel Generator System Division II R.H.R Complex ML21055A3132021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4127, Reactor Drywell Cooling System Flow Diagram (P&Id) ML21055A3122021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2500-08, One Line Diagram 4160V Diesel Gen. Buses L1EA, 12EB, 13EC & 14ED Diesel Generator Building ML21055A3112021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5871, Core Spray System Minimum Flow Bypass Mode Suction from Suppression Pool ML21055A3102021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 5M721-2756, Diagram - Steam Tunnel Cooling System Reactor Building ML21055A3092021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721TS-2002-1, Technical Support Center Diagram of HVAC Systems ML21055A3082021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-12, One Line Diagram 260/130 BOP Battery 2PC Distribution ML21055A3052021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5866, Low Pressure Coolant Injection System Test Mode During Plant Operation ML21055A3032021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2110-03, Logic Diagram Control Rod Drive Hydraulic System Part 3 ML21055A2812021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2263, Evaporator Feed Diagram Radwaste System ML21055A2682021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6C721-2361, Reactor Building Framing Section 40-40 Upper Area ML21055A2692021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2089, System Diagram Nuclear Boiler System ML21055A2702021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2220-06, Rev. D, Logic Diagram High Pressure Coolant Injection System ML21055A2712021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6M721-2017-1A, Diagram Off Gas Process System and Vacuum System Sheet 1A Vacuum System and Recombiner Chains ML21055A2722021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2215, Chemical Waste System Diagram Radwaste System ML21055A2732021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2090-05, Rev. a, Logic Diagram Nuclear Boiler System ML21055A2742021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2003, Diagram - Main Turbine Extraction Steam System ML21055A2752021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Figure 6C271-2539, Rev. Q, Steam Tunnel Upper Pipe Whip Restraint Structure Plan and Section ML21055A2762021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing M-2240-1, Rev. Aq, (Zone B/C-8) ML21055A2772021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2005, Diagram Feedwater Heater Drains, Emergency Drains and Heater Air System ML21055A2782021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 5I721-2440-06, Logic Diagram Emergency Equipment Cooling Water System Valves Div. I Auto Open ML21055A2792021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2007-01, Arrangement of Equipment on Combination Operating Panel H11P603 ML21055A2802021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2271, Heating Flow Diagram for Turbine-Radwaste & Reactor Buildings ML21055A2942021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2008-1, Rev. Ak, Diagram - Turbine Building Closed Cooling Water System ML21055A3392021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5743, Biocide Injection/Dehalogenation Systems Functional Operational Sketch and Diagram ML21055A3002021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2349, Reactor Building Framing Plan Elevation 684' - 6 North West Area ML21055A2982021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-05, Logic Diagram Emergency Equipment Cooling Water System Valves - Auto Open Division II ML21055A2972021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6A72IN-2044, Fire Protection Evaluation Residual Heat Removal Complex Section A-A and B-B 2023-10-12
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22325A1242022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Appendix a, Applicable Regulatory Guides ML22325A1252022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22325A1262022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22325A1272022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 14, Initial Tests and Operation ML22325A1292022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Main Page ML22325A1302022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML22325A1312022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22325A1322022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis ML22325A1332022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22325A1342022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML22325A1352022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22325A1362022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Appendix B, Aging Management Programs and Activities ML22325A1382022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22325A1392022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems ML22325A1422022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics ML22325A1432022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22325A1442022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22325A1452022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22325A1462022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22325A1472022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, List of Effective Sections, Tables, and Figures ML22325A1542022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Figures (for Public Use) NRC-22-0052, Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 20222022-11-17017 November 2022 Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 2022 ML21055A2202021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2230-04, Rev. E, Logic Diagram Reactor Core Isolation Cooling System ML21055A1742021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2796-01, Rev. F, Remote Shutdown System Division I System Diagram ML21055A2192021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6A721-2411, Fire Protection Evaluation Reactor and Auxiliary Buildings Section D-D ML21055A2182021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2431, Reactor Support Sections & Details ML21055A2172021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2200-4, Rev. D, Logic Diagram Residual Heat Removal System ML21055A2162021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2043, Diagram High Press Coolant Injection System Barometric Cndr (HPCI) Reac Building ML21055A2152021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2313, Reactor & Auxiliary Building Foundation Reinforcing Plan ML21055A2142021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6I721-2196-01, Area Radiation Monitor System Diagram Sht 1 of 2 ML21055A2132021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2090-6, Logic Diagram Nuclear Boiler System Document Control No. B21-00 ML21055A2122021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6A721TS-2002, Onsite Technical Support Center Grade Floor Plan ML21055A2112021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721Y-2003, Rev. G, Condensate Storage Tanks Retaining Barrier Details ML21055A2102021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2004-1, Diagram Condensate System ML21055A2092021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2140-01, Rev. B, Logic Diagram Neutron Monitoring System Part 1 ML21055A2082021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2441, Reactor Drywell Framing Plan El. 646-91516 Unit 2 ML21055A2072021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2200-09, Rev. B, Logic Diagram Residual Heat Removal System ML21055A2062021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-08, Logic Diagram Emergency Equipment Cooling Water System Valve - Auto Close Division II ML21055A2052021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2181-06, Rev. O, Diagram Process Radiation Monitoring Subsystems ML21055A2042021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-07, Logic Diagram Emergency Equipment Cooling Water System Valve - Division II ML21055A2032021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2570-01, Functional Logic Diagram Operation of Power Line Feed & Tie Breakers 4160V Buss 64B & 11EA ML21055A2022021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2230-01, Logic Diagram Reactor Core Isolation Cooling System ML21055A2012021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2513, Side Stream Lrwp System P&ID ML21055A2002021-02-0202 February 2021 3 to Final Safety Analysis Report, Drawing No. 6A721-2406, Fire Protection Evaluation Reactor and Auxiliary Buildings Cable Spreading Area Plan El. 630'-6 ML21055A1992021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6I721-2400-03, Diagram of Samples in Turbine Bldg ML21055A1982021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2035, Diagram High Pressure Coolant Injection System (HPCI) Reactor Building ML21055A1792021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2010-1, Rev. a, Diagram General Service Water System ML21055A1852021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2551, Flow Diagram of Floor Drains in the Radwaste Building ML21055A1842021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6M721-2007, Diagram Circulating Water System ML21055A1832021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2029, Rev. H, Process Diagram Information Tables Sheet 1 Radwaste System 2022-11-17
[Table view] |
Text
8 7 6 ~
0 4 3 9 r_ 1 H i I
~:D,TS CONTI~,LED FRJ'1 JRl\'w!NG '-2106**01
- 17. DELE,.ED
,8. TYPF c PIPING FCR 'HE VENTS & DRAINS TO CR'w' CR DR\.'
BEYOND Tl-'E F"lNAL Vf.\L.\!E IS TO BE SELECTED BY PJ?l~iG JES:GNER$.
RECIRC PUMP 'A' 19.
DJS:H. V'- V. PEN/CLOSE RECiRC PlJMP 'B'
,,-;31P404A 331?403A B3!05F031A
7 MG SET A SCOOP TUBE C NT9 1. PANEL MG SET A SCJOP TUBE LOCAL PANEL B31P403B MG SET B SCJOP TUBE LOCAL PANEL BJ1F;,404B
~G SET B SCOOP TU3E -- -- -- -- -- ~**- -- --
DISCH. VL \/, OPEN/CL,:SE 2C. THESE SPEED LIMITERS REDUCE RECIRCULAT!Cli FLCV. IF ANY i'EEDl.'ATER PUMP rs NOT RUNN1NG AND THE LEVEL IN THE REACTOR iNCR DECR CONTROL ?ANEL VESSEL rs BELO\.' THE LOI.' LEVEL ALARM P INT.
WCR G I P ',IER LOCAL LJCKING UM/TORQ l!M/"ORQ L!MITORQ DECR c!M/TORQ LOCAL LJCKING POl.'ER B3105F031B FF LOCKING TROUBLE LCCK <LOC,\L LIGHT) S',iFCH S\.'ITCH 21. THIS BLOCK IS PART OF THE NEUTRON MONITORING SYS~EM FLO\.'
$\./ITCH Sl.'ITCH LOCK (LOCAL UGHT) FF LOCKING TRCUBLE 7 I l I I l 7 U~IT. EAU, UNIT IS GROUPE;) FOR ISJLATION AND SEPARATION (
MC SET 'A' SCCOP TLBE LOCKS I I
'-..;:;::;:; I l 1 l \.'!THIN THE PANEL AS INDICATED.
-- -- -- -- I i I I L, MC SET 'B' 22 LOCATE BRANCH COS,NECTION AS CLOSE AS POSSIBLE AFTER THE B31K5A 7 I _I I I 0 I I I I I I
0 L I' i -- - - - - - ---
SCOOP TUBE LOCKED f-1ANUAL IS-DLATIO~J VALVES.
I I i J I I I "22N508A HEA I ER DRAINS CHK B3100M059 1122N508B HEATE, ~RAINS CHK I I L __ I 1 B31K5B 23. CLOSED COOLING \.'ATER TD THE MOTOR BEARING IS TO SERVE BOTH THE UPPER MOTOR BEARING Arm LC',iER MOTOR BEARI-NG.
RETURN FLD\JS ARE J INED UPSTREAM OF THE TEMPC,ATURE ELEMENT.
THE I I -: - I I VLV ~!MIT $\.'ITCH LIMITER 213 VL V LIMIT S\¥ITCH -* 7 I
MG SET 'A' I
I , A" RUN/DE,EAT 'B' I L I SCOOP TUBE P SITl t I I _J , ENFORCE LIMFER 3 S\.'ITCH ENF 2CE LIMITER 3 I I I THE ;,PPL!CATI N OF THE AMMETERS (NOT SHOl.'I~) FDR THE LUBE
)._____ ~ -- **- -- - - - - -- ****- -- -- --
7 I ! I ! \JIB I <~mTE 30)
\,/ /B tL L __
7 V1G SC JP SET *"B' TUBE P SIT, N 24.
- L PU~IP A*l, A-2, B**l, B-2, E*MERGENCY LUBE IL PUMP C & D r--- __ J
\.. - I <ALSO NOT SH 'w'M) 1\RE LISTED BELD'w'.
~-* ~*.*-~ ---..:::.-.- ~....i- ~
B3103C003A I i I I I !
I I B3103C003B I 1 ~-~.:d,, I 331 '!630A AMMETER FOR LUBE OL PUMP A 1 I B3100M06C I I I 331R630B AMMETER FDR LUBE DlL PUMP B-1 I
I B31R6JIA AMMETER FOR LLBE IL ?UMP A-2 MAGNETIC PICKUP FROM MG SET 'A' I RECIRC RUNBACK RECIRC RECIRC RUNBACK RPV HYDRO I I I MAGNETIC PICKUP B3,R6313 B31R632A AMMETER AMMETER FOR FOR LUBE Oil PUMP B-2 E~ERGENCY L'JBE OIL PUMP C LIMITER 1 L.__ _ _ _ __ / --..,._**------*----~
I RESET 'A' PLMPS RUNBACK RESET 'B' DEEEAT SVITCH I I I f'ROM MG SET 'B' B31P632B AMMETER FOR EME.~GENCY LJBE OIL PUMP D F B31Nll6A.B,C PB KEY ,.DC< r-I I lN TE 28) I I I B31NI17A,B,C PR*JVISI N FDR INSTRUMENT LINE IS LAT,ON BY CUSTOMER IN I
1 (NOTE 28) I 1 25.
ACCORDANCE \./ITH AP.0 L'CA3LE LICENSING Pl!ACT!CES. AN ORfflCE F I I I I I 0/4' MIN.l IS TD BE PROVIDED, \.'ITHJN THE PRIMARY CONTAINMENT, MG SET ~A~
BREAKER PEN/CLOSED FlEL::l i- - 7 I I ~I
~ CR
.B31R621A .
I I c.~
B31R621B
[@l LJ I I
i I -- -
MG SET 'B' FELD BREAKER IN EACH 11,STRUMENT LINE VHICH CONNECTS TD THE REACTOR COOLANT PRESSURE BOUNJRY.
B3!ACB!A I I I I I RECl~CLLATlN I I I RECIRCULATlN I I I OPEN/CLOSED
- 26. THE RECJRCULATTCN SYSTEM PIPING DESIGIJ PRESSURE AND TEMPERATlRE I I I I I MG I SHALL BE AS SPECIFIED IN THE PROCESS DIAGRAM.
I I MG "A" GENERATOR SPEED CONTROL I "B' GE'!ERATOR SPEED CONTROL I I B31ACB1B I I I I I I I I I I I I 27 7 HIS SPEED Ll,~ITER LI,'!ITS RECIRC. PUMP SPEED ON LOSS OF HE.I\ TER DRAIN PUMP FLO\.' INTO 7HE FEEDVATER SYSTEM.
MG SET "A' DR:VE MOTOR I I I I I I I I I ! I I I I I I I I MG SET 'B' BREAKER I I I I I I I I I I I I PEN/CLOSED ~l I I I I I I I I i -
DRiVE MOTOR BREAKER 28. AFTER C,.EAR!IJG THE LIMITER !fi!T,ATI N C ND:TIDN. TPE OPERATOR I I I I I I I I I I I I MUST RESET THE UMITER :JRCUIT IN ORDER - INCREASE 65G PJS. G3 I I I I I I I I I I I I OPEfJ/CLOSED PUMP SPEED.
I I I I I I I I I I I I 65G ::,OS. G5 i I I I I I I I I I i I I I I I I
..I J I I Ale SETPOINT INFORMATION IS FOR REFERENCE NL Y SEE CECO & ,EACTOR
J 29.
.1 - 1 L _______ ! -
I L 1 ..! -
I E I LOSS OF NRFP --
' ..I ' ' '
I
' ' ' - *- f._ I- I ENGINEE,ING DATA BOCK FOR ACTUAL SETP INTS, E:,FORCE LIMITER 2 L -- ~J LOSS OF SRFP E,FORCE
- 30. LIMITER 2/3 L.OGIC IS 5YPASSED \.'PEN DEEEAT SVITCH IS IN DEFEAT P SITinN.
E
\;// LVL 4 - - -- -
RI:;;SC D,~(;'
LIM'TER 2 Jl. RRCS DCS SYSTEM CCMP'USES CF 9E~ *E 1/0*RR (B31K4!1) Alm REMOTE SPEEJ UM:TER ~, . l SPEEI LIMITER NO. 2 CN21:M8~4A HGH LIMIT 30%. S 0 EED HIGH LIMIT L -....:: SYSTE~J SPEED LIMITER ND. 3 HIGH :. !MIT SPEED L,l~FER NO, 4 H1GH U~IT
'vi/ l VL 4 res CABLES.
RR (B3POC4). B31K413 AND B31POO< C t-fMUN,Cf\TE VIA FIBER OPTIC
<NOTE 29) (SEE NOTES 20, 27, 29) (NOTE 31) (N2DM824B
<SEE NOTES 20, 27, 29) <NOTE 29l
- 32. SEE DRAVING ,*2105*21 ,OR COfiF!GURt,T; N DETALS.
- T - - - -I - - -
- 33. FLAT PANEL DISPLAY IS CCMM N TO f"'dCS AND RRSC, I I T T I
7 I
7 7 I
-I I
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DC$ CONSOLE I (N[TE 32)
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.SPEED SETP lNT RR "/\
I TO s* ART REC I DCS LOSS LIMITER A RRS 'B' RR uB" 1 B. THIS DRA'w'ING ALCNG \.'ITH 1-2!06*01 AND M-2833 , RMS THc LIMITING WcR I
Pi'~L HllP91:l POINT 'r97 I
7RDUBLE I y, ~~1i~: (Vc I 213 DCS TROUBLE ,
I\.
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SYSTEM PIPING AND INS"RUMcNT DIAGRAM FOR THE REACTOR RECIRCULATI=N SYSTEM.
CR I
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1 C. SEE .CRt\\Jil'-1G M-2833 FOR REFERENCES, D I ENGAGED ENGAGED /. I I SPEEC DEMAl,D 'A" TO SCOOP T JBE DRIVE TC STARTREC PNL HIIP91~ J MG SET "A*
SPEED S!GNAc TO STARTREC PNL :-111r1 919 ..._
_J I
i /
LIM-IA LIM* 1B 1"-._j
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MG SET fiBd SPEED S:E"'."POIN f TD STARTREC PNL. H!P919 __ j I
I I
L l '""" "'"'"" . .
TO SCOOP TUBE DRIVE TD STARTREC F'.AT PANEL DISPLAY FV & RR (NOTE 33)
CR C32k8-16 D. LELETED D
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PCINT #101 C *2042*14) l~1 WAPMED
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LIM*2A ARMED U~*2B ~
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I I SCOOP TL;BE PDS!T;JNER 'A' TD ST/\RTREC PNL H11P919 ~---,,.
P INT #107
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/CR'-,
ARMED LIM*3A ARMED '
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/CR'-,
MG SET 'B' SPEED SIGNAL TO STARTREC Pl'-JL HU.P919 . -
P !NT #102
_ _J I I I L __
SC JP TUBE POSiTIONER 'B' TO STAF2TREC PNL H11P919 I
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(1-2042-lA)
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',"-.__./"l .' IM-4A F/ECIRC I PUMPS G!GAGED L:M-4B
) ,- I 0 (1-2042-17)
MG SET A SCOOP TUBE I
0 SPEEJ DEMAND FROM B31K81SA B3103COJ3f>-
c P TUBE POSITI NE? I
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I C
STOPS THE SCOOP TUBE W ITS ~AST POSITl N BEFORE l..OSS OF SIG,~Ac TO RELAY k14A STOPS THE SCOOP TUBE IN 1TS LAST P'lS!TI N BEFORE LOSS OF SIGNAL TJ RELAY 1(14B SPEED CONTROL SYSTEM BLOCK DIAGRAM @721-2106-02
<SHOWN FOR BOTH SYSTEMS A & Bl LATEST RE\1SIC ..
"' N B
B NON-NUCLE1\R NON R SAFETY RELATED i THIS IS A MICROSTATION PRODUCED DRAW"ING CHANGES OR REVISIONS lv!UST BE BROUGHT TO THE ATTENTION OF THE PLANT EKGINEERING DESIGN GROUP TO ENSURE THAT CONFIGURATION a CONTROL JS MAI\'TAINED.
THJS DRAWING- W./\S REFORMATTED BY MICROS'l'ATION AT REVISION "N". ALL me.CODE Detroit Edison Fermi 2 u
PRE'I/IOUS APPROVAL SIGNATt;RES ARE TITI.E CN FILE ON MICROJi'JLM IN DOCUMENT CONTROL. INSTRUJ\1ENT DIAGRA.tvf N DCD'S INCOHPORATED:
A PORTION OF THIS DRAl'llNG IS AF'FEC'TED BY THE FOLLOWING:
PREPARED BY DATE REACTOR RECIRCUL.4TION EDP-32559.B024, REV. :ti ECR *32559*2 REV A SPEED CONTROL BLOCK DI.4GR1\l\1 A -
TC I*..CHANGE DOGUMENT CHIOCI<ED BY DATE
' OTHER REVISIONS: 'i APER'tCRE CARD TITLE .4.
.. APPROVED BY
INST DIAG RRS SPEED CONTROL A PLANT IDENTIFICATION SYSTEM NUMBER ARMS RECIP!ENT #
PREPARED BY IDATE CHE£KE . _fY /L--------- I DATE ..
'w' .I ADLER 8/03/09 '( ~
- :el1il"'1 _ OTHER APPROVAJ..S DOCUMENT TYPE CODED DD INC NUC OPS FILE NO . DATE ISSUED TO LS APP.ROVE:D BY ..;T'l:w.v ,.,_ <>S,G;'.~~ DATE !<:DP POSTING ENTRIES REQUIRE THE
_p_AT8 1801 6-17-0'l
, i',_,t, Jin~ &tl,.#AY;R; A
-~ 'G c,9... ~ l 8 &-/41.q ADDITION OF THE ARMS STA'rDS CODE:
EITHF.R "AFC" OR "AS.B" i
DRAWJNG NUMBER 61721-2106-02 REV.
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