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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 5 4 3 2 1 r-----------------------7 r
I ~----- .----- I REQUIRES COINCIJENT TRIP OF I
I REACTOR VESSEL LEVEL 2 TRIP I I REACTOR VESSEL LEVEL 2 T'1P I I SI/ITCH B21N692A DR B21N692B AND B2IN692C OR B21N692D TO MANUAL INlllATIO" or RClC RCIC AUTO MTtAN SlGNAL II lSQLATl N
_::it;$HBUTTDN I
I START SYSTEM SYSTEM lS PRESENT I I SVlTCH DEPRESSED I LIS B21 N692A LP ciS B11 LP I SVlTCH I RSP I I AUXlllARY I CR I PB I CR HI I I REF l N691B I
I lEVlCE H
I I I
I I
I I
I REACTOR VESSEL LEVEL 2 TRIP REACTOR VESStl LEVEL 1 TRlP I
I I
I I
r- PERMISSIVE VHEN TRANSFER S\rliTCH IS
'ON' P SlTl N \ RESET PUSH BUTTON SEAL-TN AUTO INITIA TIN SlGNAL UNTll RESH
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CR VI PERMISSIVE VHEN SELECTOR COLLAR IS IN ARMED POSlTION I AUXILIARY / \___/"
I i
US B11 N692C LP LIS B11 N692D LP SVlTCH I RSP I I RMS I CR I DEVICE CR PB ZONE HS NOTES:
~----~-------------~----J I. THE RCIC SYSTEM IS ARRANGED FOR TEST OF PUMP AT FULL FLO\./ & ALL VALVES FOR OPEN &
CLOSE CAPABILITY AT ANY TIME EXCEPT
/ PERMISSIVE VHEN \/HEN INITIATION SIGNAL OR AUTO ISOLATION lNlllATWN SiGNAf.
~,
1-' lS RESENT SIGNAL IS ACTIVATED IN EVENT THE INITIATION SIGNAL OCCURS VHILE TEST IS UNDERVAY, I
"AUTO INITIATION SIGNAL (NOTE I)
SEE NOTE 4
\
AUXILIARY DEVlCE LP 7 ~ SEE NOTE 4 2.
THE SYSTEM AUTOMATICALLY RETURNS TO STARTUP MODE.
ALL POI/ER FOR OPERATION OF DC. VALVE G ' ,--------7 MOTORS SHALL ORIGINATE FROM A PLANT D.C.
G "4v~ I I E>ERGENCY I
I I r------- T I
--- 7 I
BUS. PDVER FOR AC OPERATED SHALL ORIGINATE FROM AN EMERGENCY A.C. BUS.
/F, I AREA COil.ER HIGH TEMPERATURE I I I REACTOR I
I HlGH TURBINE EXHAUST
- 3. 'UNLESS OTHER\/ISE SH VN, ALL INSTRUMENT PIS NOs. ARE PREFIXED ES!
G I I 4 f7/ I PRESSURE LOV I DIAfHRAM PRESSURE I ALL VALVE AND EQUIPMENT PIS NOs. ARE PREFIXED E5l00 I TS I I N601A CR I I I 4. ISOLATION SIGNAL SVITCHES SHALL BE OF THE L _ _ _ _ _ _ _ _ .J I I PIS I
/c' II PIS N6511A LP I N6<5A
- LP I TYPE THAT CLOSE CONTACTS FOR THE SPECIFIED 2 POSITION KEYLOCK S\IITCH ISOLATION EVENT. VHERE AUXILARY RELAYS ARE 31G5
/B'
- NORMAL-RESET KEY REMOVABLE IN NORMAL POSITION SEE NOTE 4 r--------7 I
I I
I I
I I I
I USED IN THE ISOLA TIDN CHANNELS THEY SHALL BE PO\IERED FROM THE STATION BATTERY SO THAT THE LOSS OF AC POVER DOES NOT CAUSE AN PERMlSSlVE UNLESS PERMlSSIVE SHEN I STEAM LIN£ HlGH DP I ISOLATION SIGNAL TEST SVlTCH 1N RSP TRANSFER SVlTCH I I : II ISOLA fl N TRIP R
"21G6 LUCIC 'A' RESET S'JITCl-1 1N t,mMAL
'TEST' IS 'ON' POS!TIGN I
I lNSTRUM[,il llNE BREAK ACHVATED tflER I
I I I
REACTOR PRESSlRE LO\.I I
I HlGH TURBlNE EXHAUST Il!AP!--:RAH PRESSURE 5. AUXILARY RELAYS & DEVICES NOT SHO\IN ON
( D' \ RMS CR /
TRANSFER RSP /
I 3 SECDND DELAY I
I FUNCTIONAL CONTROL DIAGRAMS EXCEPT \,/HERE
\ SVITCH I ciP1S-N657A I I REQUIRES TO CLARIFY FUNCTION.
1 4 lc4 RMS CR I dPIS-N660A LP I *'i PIS N&S8C LP I PlS N655C I LP L _ _ _ _ _ _ _ _ .J 6. DELETED I I
- 7. FLRNISHED \,IITH TURBINE.
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L---- ----- ...L -----~----...J
- 8. DELETED
~
CR
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SEAL-IN AUTO IrnLATIJN S!G:IAl.
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. LEAK DETECTlON BY'ASS
( SVITCH IN 'BYPASS' POSlllN .
\\
- 9. THE RCIC SYSTEM SHALL BE DESIGNED IN ACCORDANCE \JITH PROPOSED CRITERIA FOR t!UCLEAR POVER PLANT PROTECT:ON SYSTEM IEEE -279 INSCFAR AS PRACTICABLE.
F 2 POSITION KEYLOCK SVITCH LOCK-OPERATED KEY REMOVABLE
/
,_/
r ,- - ~ ~ -
Ii AUXIUARY D£VICE CR i \
SELEC-DR WITCH 1 I RSP /
\
SELECTOR SWlTCH I RSP / 10. FOR LOCATION, IDENTIFICATION AND SET POINTS _[;7
\ IN 'LOCK" POSITION oc INSTRUMENTS SEE THE MASTER INSTRUMENT LIST.
AUTO ISOLATION 11 FOR CONFIGURA TI N OF PANEL MOUNTED SIG. (NOTE 1) OPERA TORS AND INDICATORS SEE D\,IG, CCNTRQL SVITC~
IN 'rlPERAiE' ~. ,, 1 t 6M-2290 SH2, REF 12 PURCHASE SPECIFICATION AUTO ISOLATION SIGNAL j
-',/
' +--- AUTO. !SOL SIGNAL '\
T AUTO ISOLATION SIGNAL DATA SHEET SECT, 2.4.
RMS CR GROUP 8-ISOL. VALVE 12 ALL MOTORS SHALL BE PROTECTED BY THERMAL SEE NOTE I MIMIC DISPLAY 2 POSITION KEYLOCK SI/ITCH SEE NOTE 1 C\/ERLOAD TRIPS AND BREAKER SHORT CIRCUIT
/ L '* 'NORMAL"RESET' KEY REMOVABLE CURRENT PROTECTIVE TRIPS.
G1EJ "7 1B4 IN 'NORMAL' POSITION lS LA HON SlGNAL LOGIC B RESET svnrn IN ,--------
NORMAL 1 I i EMERGENCY AREA Cc LER RMS CR SEAL .. IN
'CPEN' PUSf-lBUTTON SVlTCH lS DEPRESSED
'CLOSE' PUSHBUHDN S'i.11Tot IS DEPRESSED 11,;;--.--__J I
~
HIGH TEMPERA TUR[
NiO~B I CR SEAL-1" SEAL -lN
'f '----~----~--....;
j AUXILIARY ZCNE C7 PB CR PB CR E CJNT. 721 AJXILIARY ZONE C7 AUXlllARY ZONE CJ SEIII.-IN ___________ T __________ E CGNT. 721 cNi. 721 AUTO SIGNAL -7 "CR / UNTIL RESET REFERENCE DOCUMENTS:
19
'*- " AUXILIARY i CR I PERMISSIVE muss TE"ST S'JlTCH IN I PERMISSIVE 'JHnl RSP TRANSf"ER S>lTCH I
\I REAC10R PRESSURE LDV I
I HIGH TURBINE EXHAlJST I
I 1 NUCLEAR BOILER P&ID--------------- M-2089, M--2090, M-5538
/ DEVICE
( 'TEST' IS 'CW POSIT!DN ! I DIAPHRA~ ?RESSURE I
\
( NOT PcRMlSSlVE
\/JTH AUTO TSOLATl N SIGNAL \~ - - - - ' - - - , - - - - - - - ' /
/ PERHlSSlSVE UNLESS
'JPEN' PUSHBUTTON \ RMS CR __ }
TRANSFER SVl'CH RSP ___/
I I
I PIS N658B LP I
I I
PlS N655B LP I
I I
- 2. NUCLEAR BOILER MISC. SYSTEM LOGIC DIAGRAM- -- -I -2090-01
- 3. RHR S~STEM LJGIC DIAGRAM-------------- - ------ 1-2200-01
'-I-\ LIMlT MITT ..VALVE ~.N"'
ON / .4UXIUARY LP 1 SVITCH JS DEPRESSED I I I 4. CORE SPRAY SYSTEM LOGIC DIAGRAM--------------1-2210-01 WITCH DEVICE I I 5. HPCI SYSTEM LOGIC D!AGRAM---------------------1-2220-01 PB ZCNE E8 I
,--------7 I 6. RCIC SYSTEM P&ID--------- -----------M-2044, M-2045 PERMlSSlVE I STEAM c.rnE HIGH DP I I ! I 7. LOGIC SYMBOLS-----------------------209A4756J R!-20 UNLESS VAL VE PERMlSSlVE UNLESS FULLY CLOSED BYPASSED AT REMJTE
/ F'ERMlSSIVE UNLESS LEAK DEJECTION BYPASS I '.NSTRIJMENTDRLINE EREAl< I I REACTOR I :.tIGH TURBINE I 8. TURBINE CONT. SYS & ELEC V!RfNG-------------- TERRY "URBINE PRESSURE LCV EXJ'AUST SHUTDDVN PANEL SViTCH lN 'BYPASS' POSliTCN I AC'IVATED AflER I I I DIAPHRAM PRESSURE I VENDOR MANUAL #E51-0l-C-002-J4-002 L!Mll ON I 3 SECOND DELAY I I I I PERMISSIVE VHEN v,1vE lS S\*JITCH VALVE SELECTOR WllCH RSP SELECl R SV11CH RSP I dPIS-N657B dPIS-N660B LP I I PIS Ii LP I PIS LP I 9 REACTOR \/ATER CLEANUP SYS P&IO-----M-2046, M-2047
< SOY. llPEN I!_______ I IL _ _ KS53D I N655D I 10. LEAK DETECTION SYSTEM DESIGN SPACE---------22A1441; Rl-138
____ _j _ _ , _ _ _ _ _ _ J__ ______
--- _ j 11. ELEC EQUIP SEPERATIDN ,- R LIMIT SVITCH ON VALi/[
! SAFEGUARD SYS.------------- --------22A3777, Rl-1410
~ 12 GENERAL R:QUIREMENTS FOR INSTRU-D 'i MENTATION & ELEC EQUlP.------------21A1768; Rl-446, 448 D
\. AUTO ISOLATION SIG:*JAL 13 RCIC SCHEMATICS --------------------- -- l-2231-01 THRU IO AUTO. !SOL. SIGNAL---~. ' ( x\.... AUTO ISOLATION SIGNAL 2 POSITION KEYLOCK SVITCH SEE NOTE 1 I-2235-0l THRU 11 GROUP 8-ISDL. VAL VE / E
- SEE NOTE l CONTROL SVlTCH LOCK-OPERATED KEY REMOVABLE 14LOGIC DIAGRAM-GROUP 8-RCIC MIMIC DISPLAY lN 'OPERATE'
,3 E2 IN 'LOCK' POSITION ISOLATION VAL VE MIMIC DISPLAY-------------------1-2230-07
, K 15LOGIC DIAGRAM-GROUP 9-RCIC 7 _, RMS CR ISOLATION VAL VE MIMIC DISPLAY-------------------! -2230-08 PERMISSIVE UNLESS VALVE lS )75). OPEN
\
\
PERMISSlVE UNLESS VALVE QVERTDRQIJ£D
'\ PERMISSlVE UNLESS VALVE CVERTORQIJ£D \ A~ E PERMISSIVE UNLESS VALVE EULLY CLOSED VAL VE UMIT WITCH VALVE LEGEND:
VHiLE OPENlNG VhILE CLOSING FULLY CLOSED CMC COORDINATED MANUAL CONTROL S\,IITCH PB PUSHBUTTON S\IITCH llMIT 011 TORQUE CN TORG~E I< LIMlT ON ON S',ITCH VALVE SVlTCH VIII. VE SWJTCH VALVE \ S1JITCH VALVE LIMIT S'wlTCH VALVE 'OPEN' 'CLOSE' AM AMMETER 4--GROUP 8 PUSHDUTT N WITCH IS rEPRESSED PUSHBUTTON SVJTCH IS DEPRESSED SEAL-111 (BY AD
- SVITCHGEAR DEVICE FUNCTION NUMBERS ANS] SPEC C37.2 IS L. VA LVE RSP REMOTE SHUTD0 1JN PANEL MIMIC RMS REMOTE MANUAL SVITCH PB CR CR AUX DISPLAY PB i CONT. 42t ZCNE Bo cP LOCAL PANEL M CR CONTROL ROOM &RELAY ROOM C 7 ID4 *--*-**~
PERMISSIVE UNLESS VALVE C
>951/. CLOSED OPEN
~----------------------..J Il.C, REVERSING cmn f'tCTOR 721 CLOSE I PERMISSIVE 'JH(N VALVE IS:
\
\.
NOT PERMlSSIVE
\./ITH AUTCJ SEAL **tN
~ * -llMIT SVITCH i ON VALVE
/ PERMISSISVE UNLESS
'OPEN' PUSHBUTTON SVlTCH 11 DEPRcSSED
---~-
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< 10oz OPEN i STE.AM SUPPLY UNE ISOLA TI N VAL VE MO E5150F008 ISOLATION SJGNAL
\ PB ZDNE C6 AUXlUARY SEE NOTES 2 &5 CONT. 42¥ ZC:<E BS UMlT S~lTCH ON VALVE
\__'ux1u,RY DEVISE LP I
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01 PERMISSIVE UNLESS VAL' '[ / PERMISSIVE UNLESS VALVE I
I PE~MISSIVE UNLESS WL VE OVERT RQU[D I PERMlSSlVE UNLESS VAL VE VALVE UM]' SVITCH VALVE YERTQRQUE ) IS >95% OPEN \./HILE CLIJSlNG / 95% I IJHILE OPDll G I FLLL Y CLOSED HJRQUE S\.IITCI-I ON VALVE V
I \ LIMIT SIJITCH vZ:vE /
\ TORQUED SWITCH ON VALVE
/ LIMlT SVITCH ON VALVE
/ LIMIT SVlTCH ON VALVE THIS DRAWING SUPERSEDES EDISON'S SITE MASTER GROUP 8 B -~--~--**-* !SOL. VOLVE (VENDOR DRAWING 729E622AB SHT 1 REV S) OF B
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- MIMIC DISPLAY EDISON Fil_E NO.Rl -151
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'"-*-- I ii \2__lD4-AC RE:VERS[NG Cl)ITACTOR ~21 THIS IS A lv!ICROSTATIO'f PRODUCED DRAWING.
... ,~~***
STEA~ SUPP~ Y LINE ISOLI\Tl N V,~LVE MO E5150F007 NUCLEAR SAFETY RELATED CHANGES OR REVISIONS MUST BE BROUGHT TO THE ATTENTION OF THE PLANT ENGINEERING SEE NOTES 2 &5 DESIGN GROUP TO ENSURE THAT CONFIGURATION CONTROL rs MAINTAINED.
THIS DRAWING WAS REFORMAITED BY MtCROSTATION AT REVISION "E. AIL INC.CODE Detroit Edison
--- --**----t=,.--------------------------1 Fermi 2 E IDCD'S INCORPORATED PREVIOUS APPROVAL SIGNATURES .ARE ON FILE ON MICROFILM IN DOCUMENT COl'ITROL PREPARED BY u
DATE TITLE LOGIC DI_A.GRA1'I REACTOR CORE ISOLATION COOLING A PORTION OF THIS DRAVl1NG lS AFTECTED BY THE FOLLOWING:
EDP-34041.B003, REV. ¢ SYSTE1'1 TC CRANCE DOCUMENT A OTHER REVISIONS:
CHE;CKE;J:;J_)c!Y DATE:
I APERTURE CARO TITLE !A
- - - + - - - - - - - - - - - - - - - - ;.. __ .. Af>PRtivt:D- BY LOGIC DIAG RCIC SYSTEM PLANT ID~NTH'lCATIO:N SYSTEM NUMBER ARMS RECIPlEN'l' #
IcHtcfSeyi E5100 PREPARED DY DATE 4/27/'.)9 /J/l. ~
ijY ti.ATE DOCUMEN1' TYPE CODED D D INC NUC Of'S Fn.E NO. DATE ISSUED TO IS 1,1 J ADLER <f/U:/o'f l OTHER APPROVALS PATE 1801 5 \.
APPROVED BY ,_T1b/l"µ ,l,/'o$G$ fal'- DATE EDP POSTlNG ENTRIES REQUIRE THE DRAWING NUMBER _ _
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ADDITION OF THE ARMS STATES CODE:
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