|
---|
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
H G
F E
D C
B A
8 7
/AA' I-21l0-05 C7 6
5 FIGURE 1 NEUTRON MONITORING SYSTEM ROD \\./ITHDRA \\./ AL BLOCK
[PART OF ROD 1/ITHDRAIIAL SYSTEM SHO\\IN ON REF. DIIG. I-21l0-SERIESI I
1--------'~
y SRM CHANNELS I
REACl[F! SYSTEM lllDt S\\ltTCH PERMISSl\\lE
!RM CHANNELS A,CJ,G PERMISSM
\\JHCN AIJTD 20A SIOW. NOT 3 I D8 PRESENT
\\
MIXILIARY CR
/
ITT:7 IRM RANGE SI/ITCH NOT ~D£_V_IC_E -+---~
1:::r::JON RANGE 8 OR ABOVE IR M CHANNELS A,C.!...E,G I
1 4A I 31 7, QglRM RANGE SI/ITCH ON L VEST 1\\10 RANGES PERMISSM Ir/HEN AUTO SIGNAL HOT PRESENT AUXILIARY DEVICE CR I ft,l UPSCALE ALARM 1::+/-:J ON LEVEL 1147 ALARM ON INSTRUMENT 1:::r::J INOPERATIVE f"T67 DET NOT IN 'FULL -IN' l:::r:::I POSITION A,C
~AUTO
/
SIGNAL P£RHISSIV[
\\.IH£N AUm SJGNAL t{IT PRESENT g;juPSCALE AL~
ON LEVEL
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/
177 ALARM ON INSTRUMENT l:::r:::I INOPERATIVE SRM CHANNELS A,C 2A '
2 ID7, rn DO\\INSCALE ALARM ON LEVEL l'[RfflSSIV[
\\11£N AUTO SIGN/I. NOT PRESENT AIJXllIM:Y ll£VICE CR
,Tl DEl RET. PERMISSIVE ID/l¥/JS,CALEI t:+/-:J ALARM ON LEVEL, AND l::::'l::J DET. NOT IN 'START -UP' POSITION
!RM CHANNELS A,B,EJ -
3A I
1'£RHISSIVE Vl1EN AUTO SIGNAL MIT PRESENT
\\
3 ID7 AUXILIARY IlfVI!:E CR
/
L
)
I I
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'RUN' PSITmN 1-2110-0t;.§I PERMISSIVE WHEN AUID Slfl{AI.. t{)T PRESENT APRM C HANNELS 1,3 5C '
, 4 IDB, AUXIUARY CR I ~
NEUTRON FL OCVICE ux DOWNSCALE ALARM PERMISSIVE
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15A,
5 IDB I
\\
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/
DEVICE 1327 RBM
~--r--~ t:4::J D0\\/NSCALE ALARM RBM CHANNELS A
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!RM RANG£ SI/ITCH NOT IN LOIIEST RANGE POSITION 14A 5 E7 FIRNISS:IVE
~1£N A/JT SIGNAL NOT PRESENT AUXILIARY DtVlCE L
7 APRM CHANNELS 1,3 5A
, 4 IDS, I 22 c=UPSCALE ALARM
~
TRIP ON INSTRUMENT INPERA TIVE gg LPRM Lll\\l COUNT B
FLO\\/ FUNCTIDNS IN APRM CHANNELS l,3 AND RBM CHANNEL A 1 6A '
ni7 FLO\\/
I 5 E5, l:::r:::I UPSCALE ALARM 17n ALARM ON INSTRUMENT l:::r:::I INPERA TIVE I
I P£RMISS!vt
'JHEN AUTO SlOOL lllf PRESENT AUXlllARY CR DEVICE PERMISSIVE WHEN AUTO SIGIW. NOT OO[NT
\\ AUl(JLIJ\\RY OCVOCE CR
/
1377 GAIN ADJUST 1:::r:::1 IN PROGRESS RBM C HANNELS B
1 4B
,5 E6
.. rn GAIN ADJUST IN PROGRESS i
CR PERHISSIVE
\\Jl-[N AUTI1 SIGNAL HITT PRES£NT AUXll.lARY CR OCVJCE I-2110-03, ZONE E4 1-2110-04, ZONE CB RBM CHANNEL A -
I PERMISSIVE
\\il£N AUTO SIGNAL NOT PRESENT CONTROL ROD 1/ITHDRAIIAL PERMITTED BY THIS FUNCTION nnRBM l:::r:::I UPSCALE ALARM 13371NSTRUMENT l:::r:::I INOPERATIVE TRIP
!RH CHANNELS A,E,[B,FJ nn UPSCALE TRIP 1::+/-:J ON LEVEL 9A(9B) 3 C7( 2) 1147 TRIP ON INSTRUMENT l:::r:::I INOPERATIVE
/7A
\\5 DB PERNlSSJV[
VHEN AUTO SIGJAL tm PR[SENT AUXU.IAAY OCVICE I
IF SIGNAL IS PRESENT AT THIS POINT AUXILIARY IIVICE CR
/
tj,---CONTROL ROD 1/ITHDRAIIAL PERMITTED BY THESE FUNCTIONS (EE '
I-2110~0$
CR IF SIGNAL PRESENT AT THIS POINT 1-2156-03 ZONE E2 PERHl!!IVE
\\/HEN REACTII!
l.f!OC SVITCH IS IN 'RUN' FUSITJIJ{
FIGURE 2 NEUTRON MONITORING SYSTEM TRIP REACTOR PROTECTION SYSTEM TRIP SYSTEM A
[TYPICAL FOR TRIP SYSTEM Bl 2-UT-F -4 VDT APRM C HANNELS 2,4 5D
\\
I REACTCE SYSTEM lfJDE S'w'ITCH PERMISSIVE
\\JHEN SWITCH IS [N 4
\\
"R~' POSIT!N
~,,-----,
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\\i'HEN AUTO Slfl,li!l J[Jl PRESlliT (BB l-21l0-05 CS
-...v PERM!SS!VE Vf£N AUTO SIGNAL lt!T PRESENT
\\
AUXILIARY CR OCVICE PERMISSM
\\IH[N AUTO SIGNAL NOT PRESENT
\\2 El
!Tl UPSCALE
- ARM t:::t:::J ON LEVEL 147 ALARM ON INSTRUMENT 1:::r:::1 INOPERATIVE SRM CHANNELS B,D 2B 3
4 IDB 1
\\ AUXILlARY CR I
~NEU TRON FLUX DEVICE 2 DI
\\ A/JlalJ\\Rl CR
/ rn D01/NSCA[ -ALARM
~"-VIC[---+---~
ON LEVEL DOIi NSCALE ALARM RBM CHANNEL 167 DET. RET. PERMISSIVE [ljJ\\/,MS,CALEJ 1:::r:::1 ALARM ON LEVEL, AND t+/-:J DET. NT lN 'ST ART-UP' POSITION
!RM CHANNELS B
PERMISSIVE
\\/HEN AUTO 15B SIGIAL NOT I
'"" AUTO 38
?RESENT SilltAL NOT PRESENT 5 IE6
\\ AUX!LlARY CR I rnRBM ocvrcr DOIi NSCALE ALARM 3 D7,
\\~'_u:_~-~-' -+--CR-~/ rn ~~SE~~L,.ARM 7
I L
PERMISS[IJ£
\\/HEN AUTO SJGNAL "1T PRESOIT AUXILIARY l(VJCE CR
/
PERMISSIVE
\\l'HfN AUTO SIGNAL NOT PRESENT APRM CHANNELS 2,4 5B 4 DB 12 UP,cALc ALARM 1247 TRIP ON INSTRUMENT l:::r:::I INPERA TIVE gg LPRM LOIi COUNT FLO\\/ FUNCTIDNS IN APRM CHANNELS 2,4 AND RBM CHANNEL B 6B \\
5 lc.4 A/JXJU"'Y CR
/
l7i7 FLO\\/
~D_EV_~_E -+---~
1::+/-:J UPSCALE ALARM PERMISSIVE VIEN AUTO S1GIAL NOT PRES£NT 1721 ALARM ON INSTRUMENT 1:::r:::1 INPERA TIVE RBM CHANNEL 7B '
/
l'.itlRBM AUXJL~Rr CR 1::+/-:J UPSCALE ALARM ICVJCE
~--+-----' fn7 INSTRUMENT t::d INOPERATIVE TRIP CONTROL ROD 1/ITHDRA\\IAL----+
PERMITTED BY THESE FUNCTIONS IF SIGNAL PRESENT AT THIS POINT (FF '
1-2110-05 G2 PERMISSIVE
\\II-EN REACTIF tlIDE S\\j'IfCH lS IN 'Rt.II' POSJTDI I-2156-03 ZONE G2 PE:RNlSSlV[
\\llfN AUTO SIGNAi. IDT PR[SENT AUXILIAAY IEVOCE CR 1147 ALARM ON INSTRUMENT 1:::r::J INOPERATIVE 11ii7 DET N T IN 'FULL -IN' t:::t:::JPOSITION
~
D IINSCALE ALARM ON LEVEL,AND ~
!RM RANGE S\\IITCH NOT IN LOIJEST RANGE POSITION r
SEE CONTROL ROD DRIVE HYDRAULIC SYSTEM 612110
!RM CHANNELS C,GID,Hl nn UPSCALE TRIP l:::r:::I ON LEVEL nn TRIP ON INSTRUMENT l:::r:::I INOPERATIVE NNEL A2-X,
-Y L
PERMISSIVE
'wHEN Al.IT SIGNAL NOT PRESENT AU>:IUARY
]£VICE CR
&-- 1-2156-03 ZONE E2 A1rn1l 10AGOB) 4 C8
-X, B2-Yl
!OC(!OD) 1ei7 NEUTRON FLUX t:::t::I UPSCALE TRIP 4 CB 1241 TRIP ON INSTRUM£NT l:::r:::I INOPERATIVE
~
STP UPSCALE TRIP 28 PRM UPSCALE TRIP L
'----< B PERMISSIVE
\\JHEN AUTO SIGNAL NOT PRESENT AUXILIARY CR J
II:VIC[
I-2156-02 ZONE G2 I
PERMISSN[
\\/'HEN AUTO SIGNAL l(]l PR£SENT
\\
AUXD..IARY DEVICE CR
/
I PERMISSIVE
't'HEN AIJT!I Sl~AL NOT PRESEN!
. \\
AUX[UARY DEVICE CR 1-2156-03 ZONE Ht PERMISSIVE
\\/l£N AUTO Sl~l NOl PRESENT AUXILIARY DEVICE CR
!RM CHANNELS B1Df1H 20B' 3 ID2 7
rt,;:7 !RM RANGE SI/ITCH 1:::r:::1 NOT ON RANGE 8 DR ABOVE
!RM CHANNELS B,D,F,H 4B \\
3 ID2/
riii7 !RM RANGE SI/ITCH t:::t:::J ON LOI/EST T\\10 RANGES
_J AUTO SIGNAL
,Tl UPSCALE TRIP t:::t:::J ON LEVEL AUTO SIGNAL tii7 UPSCALE TRIP 1+/-:l ON LEVEL 2
NOTES:
- 1.
INPUTS TO COMPUTER ARE ISOLATED CLOSE TO ALARM CONTACTS.
- 2.
SEE 1-2140-07.
- 3.
SEE I-2140-07.
- 4.
THE ENTIRE NEUTRON MONITORING SYSTEM IS A FULLY AUTOMATIC SYSTEM EXCEPT FOR MANUAL OPERATED SI/ITCHES.
1
- 5.
UNLESS THER'w'ISE SH 'w'N, 0
ALL INSTRUMENT PIS NO.'S ARE PREFIXED C51 B
ALL VAL VE AND EQUIPMENT N.'S ARE PREFIXED CS!OO 6,
CHANNELS A,C,E & G ARE FOR TRIP SYSTEM A.
CHANNELS B,D,F & H ARE FDR TRIP SYSTEM B.
- 7.
FOR CONFIGURATION OF PANEL MOUNTED OPERATORS AND INDICATORS SEE DIIG I-2290-02, PUR SPECIFICATI N DATA SHEET SEC. 2.4.
(NOTES CONTINUED ON 1-2140-07)
.LEGEND:
!RM INTERMEDIATE RANGE MONITOR RBM ROD BLOCK MONITOR APRM -
AVERAGE POI/ER RANGE MONITOR SRM SOURCE RANGE MONITOR LPRM -
LOCAL POI/ER RANGE MONITOR APRM-ODA APRM OPERATOR DISPLAY ASSEMBLY RBM-ODA RBM OPERATOR DISPLAY ASSEMBLY OPRM OSCILLATION POI/ER RANGE MONITOR B
STP -
SIMULATED THERMAL PO'w'ER REFERENCE DOCUMENTS, I.
~EUTRN MONITORING SYSTEM !ED --------------------- I-2146-01,02
- 2.
CONTROL ROD DRIVE HYO SYS LOGIC DIAGRAM ---------- 1-2110 1 '--~...r
- 3.
NUCLEAR BOILER SYSTEM LOGIC DIAGRAM -------------
1-209 01
- 4.
REACTOR PROTECTION SYSTEM !ED ----------------------I-215"-6-;,,0.,..I,0"2",0,-3,,-04,---~-,,,
- 5.
PROCESS COMl'U;cR SYSTEM INPUT/
22A6058 (R!-3892)
OUTPUT REQUIREMENTS DESIGN SPEC. ------------------22e6058AC (Rl-3893)
- 6.
LOGIC SYMBOLS ------------------------------------209A47:56 <Rl-20)
- 7.
i<lUTRON MONITORING SYSTEM ARRANGEMENT ------------- 731E675; (Rl-29)
- 8.
GENERAL REQUIREMENTS FDR INSTRUMENTATION 21A1768 (Rl-446)
AND ELECTR[CAL EQUIPMENT --------------------------'21A!763AB (R!-4B3)
SRM CHANNELS A,C,B,D 11 1-2140-02 C7
!RM CHANNELS A,C,E,G,B,D,F,H 9A 9B,9C,9D 1-214 -03 Cl, 2
)BYPASS OF !RM CHANNELS
~,E,D & F IS NOT ALLO\\IED 1141 TRIP ON INSTRUMENT t::i:::J INPERA TIV[
2-0UT-OF-4 VOTER CHANNELS Al, Bl, A2, B2 B
1-2156-03---<a, ZONE HI NEUTRON MONITORING SYS NON-COINCIDENT TRIP.
[INITIAL LOADING NL Yl*
REACTOR PROTECTION SYS TRIP SYSTEM 'A'
[TYPICAL FDR SYSTEM 'B'l l1i7 NEUTRON FLUX t:::t:::J UPSCALE TRIP 1217 TRIP ON INSTRUMENT t:::t:::l INPERA TIVE rn STP UPSCALE TRIP rn OPRM UPSCALE TRIP JOA, JObr;I !OD
}NOT NEEDED FOR PROTECTIN-1-214 -04 CB
~OR CONVENIENCE ONLY FIGURE 3
'"--<. B TH1S DRAWING WAS REFORMATTED BY AllTOCAD AT REVISION A. AIL PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON YICROFrul IN DOCUMENT CONTROi..
INC.CODE TITLE u
61721-2140-01 LATEST REVISION B
NUCLEAR SAFETY RELATED THIS IS AN AUTOCAD PRODUCED DRAWING.
CHANGES OR REVISIONS MUST BE BROUGHT TO THE ATTENTION OF THE PLANT ENGINEERING DESIGN GROUP TO ENSURE THAT CONFIGURATION CONTROL IS 1v!AINTAINED.
Detroit Edison
- Fermi 2 B DCD'S INCORPORATED, EDP-289I6 REV ¢ A PORTION OF THIS DRAWING IS AFFECTED BY" THE FOLLOlfING:
PREPARED BY DAT!!:
LOGIC DIAGRAM NEUTRON MONITORING SYSTEM PART 1 TC CHANGE DOCUMENT H
G F
E D
C B
OTHER REVISIONS, REVISED NOTE 5 AND CORRECTED REFERENCE DOCUMENTS TD AGREE 'w'!TH ARMS FORMAT. THESE CHANGES MEET THE EXEMPT CRITERIA OF MLS07 4.1.7.3.b CHECKED BY DATE l-,.,,=... =T=u=,..:-:ccARD=-====---------------------1 A PRJ!:PARJl:O BY DATE DATE T. RIFFNER 7131100
'i?-ZI-APPROVED BY DATE 8
7 6
5 4
3 EDP POSTING ENTRIES REQUIRE THI ADDITION OF THE ARMS STATUS CODB:
~
"AF\\:" OR "ASJT
.APPROVED BY OTHER APPROVALS 2
LOGIC DIAG NM SYSTEM PART 1 PLANT JDENTIFICATlON SYSTEM NUMBER
.ARMS RECIPIENT#
C5100 DOCUMENT TYPE CODEDDDINC NUC OPS FILE NO.
DATE JSSUED TO IS 1601 DRAWING NUMBER 61721-2140-01 B
1