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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 H H CR CR CR CR CR CR A A A A A A H
BAROMETRIC [SIJLAT][JN RCIC TURB. GDV. RCIC TURB CDUP RCIC TURBINE RCIC STEAM RCIC VALVES PUSHBUTTON S£LECT!lR COOENSER VACWM VALVES NUT H TDR ERG IL TEMP BRG IL TEMP TRIPPED TANK HIGH Cll.LAR IN ARMED
'HIGH' 'HIGH' (LIMIT S1JITCHl FULLY PEN OVERLOAD PilSITI!JN LEVEL SEE SEE LIMIT THR TTLE SEE LIMIT N DVERLDAD DN PS TS-N2Q2 TS-N103 NOTE 7 SVITCH VALVE LSH NOTE 7 SVITCH VALVE DEVICE VALVE NOTE 7 SEE NOTE 7 D07 AND ES! 008)
D G G TIME DELAY PERMISSIVE CR CR CR AFTER INITJA TIDN CR CR CR CR A A A A A A A H
AUXILIARY CR Il:VIC[
TURBINE TRIP KEYLDCK RCIC PUHP RCIC PUHP INVERTED VACLIUM BREAKER RCIC SYSTEM IL FILTER HIGH DIFFERENTIAL PUSHBUTffiN SELECTOR SELECHE SWITCH SUCTION SUCTION RCIC IN K603 VALVES NOT ACTUATID~
COLLAR IN ARMED IN DEFEATED TEST STATUS FULLY OPEN PRESSURE PRESSURE HIGH PRESSIJ<E LIii/ FAILURE PSITlN PSITJ N dPS SEE NOTE 7 PB 0 RMS
-1130-01 0 PS-N030 LP PS-IIJ06 LP AUXILIAAY DEVICE LP AUXILIARY DEVICE LP LIMIT SVITCH PIS K821 CR
~ - - - - - - - - - ~ - - - - INDICATING LIGHTS ARE PART OF RESPECTIVE PUSHBUTTON F
INDICATING LIGHTS ARE PART OF
<TYPICAL FDR ALL MDV'S)
SPECTIVE PUSH
~ - - - - - - - - - ~ - - INDICATING LIGHT MDV E515 F059, E R
F045.
INDICATING LIGHTS ARE PART OF RESPECTIVE PUSHBUTTON.
VALVE E5150F008 HAS ADDITIONAL 0 F INDICATING LIGHTS L CA T T A A INDICATING LIGHTS (NOT AS A PART OF P B > - - - ~
DI ES 5150F007,E5 50FOIO,E5150F012, D ~~~i1TING LIGHTS LOCATED AT ISOLATION STATUS E5150F013 ,E5!50F 029 ,E 5150F031,E5150F04 5 AND E5150F059 NL Y. ~
"en ~ y MIMIC-VALVE E5150F008 ~
CR CR '-- CR / '-- / '--CR/-(/ '-- CR / / '--CR/ / '-- CR / / '-- CR / / '-- CR / , / '-- CR / - ( /
A A H R R CR G G CR G G CR R R CR G G RSP R R RSP R R CR G G CR
/ /
/ /
" / /
" / /
' / /
" / /
" " / / / /
BAROMETRIC RCIC TURBINE INLET ISLATHlN TRIP VALVE LIMIT VALVE LIMIT VALVE PilSITI[tl S'wlTCH VALVE POSITION SVITCH VALVE LIMIT VALVE LIMIT VALV£ LIMIT VAL VE LIMIT CIJ<DENSER VACUUM STEAM LINE SIG'lAL LOGIC 'A' SIJITCH VALVE NOT S'w!TCH VAL VE NOT VALVE NDT VALVE NOT SVITCH, VALVE WITCH. VALVE SVITCH VAL VE NOT SVITCH VALVE NOT TANK l V WATER DRAJN INITIATED FIJ..LY CLOSED FULLY PEN FULLY PEN FULLY CLOSED NOT FULLY OPEN NOT FULLY CLIJS[D FULLY G_ClSED 80t. PEN LEVEL PT HIGH LEVEL SIT AUXILARY LIMIT ON LIMIT DN VALVE LOCAL VALVE LOCAL LIMIT LOCAL LIMIT LOCAL Lll1IT ON LDHT N LSl NDTE 7 LSH-NOIO LOCAL DEVICE LP SI/ITCH VALVE SVITCH VAi.VE P s. svnrn PS. SVITCH SVITCH SWITCH SIJ[TCH VALVE svmH VALVE (TYPICAL FDR TRIP LOGIC 'B')
TYPICAL FDR MOTOR OPERATED VALVES TYPICAL VA~~* 04,E515 FOOS, FOR VALVE E5150F008 5 025 0 E5150 054 E D D D E CR CR A CR H A AH H
I I STEAM LINE STEAM LINE RCJC TURBINE RCIC TURBINE TURBINE EXHAUST TURBINE EXHAUST TURBINE EXHAUST TURBINE EXHAUST HIGH of DR HIGH clP DR EXHAUST EXHAUST DIAPll<AM D!APHRAM DIAPHRAM DIAPHRAM INST~ENT INSTRUl£NT LINE DISCHARGE LINE DISCHARGE PRESSURE HIGH PRESSIJ<[ HIGH PRESSURE HIGH PRESSURE HIGH LINE BREAK LINE BREAK PRESSURE H[GH PRESSURE 1-HGH PIS-1,155] I LP PIS-N655B I LP PIS-N655C LP PIS-N655A LP dPIS-lts57A LP dPIS-N657B LP PS-N009A LP PS-N009] LP OR ciPS OR ciPS N660A N660B D D TURBINE SUPERVISORY INSTRUMENTATION ALARM & VALVE INDICATIONS
~
NOTE, SEE I-2230-01 FDR NOTES,REFERENCES AND LEGEND.
CR CR CR CR CR CR A AH A AL AL AH LOGIC 'A' (TYPICAL FDR B) RCIC TIJ<BINE RCIC TURBINE RCIC TUREii,£ RCIC CNDR LOGIC BUS BRG Oil DISCHARGE VACUUM TK ISIJLATIN SHUTTIDVN RPV PVER FAIL~[ FUJI{ Lffi/ PRESSURE Hllll RESET LEVEL #8 PRESSURE LIii/
AUXILIAAY AUXILIARY PS-N201 LP AUXIUARY CR PS-M800 LP CR CR C
RMS CR DEVICE DEVICE AUX.DEVICE CR DEVICE C
RCIC ISOLA TI N LOGIC RESET ALARM 61721-2230-06 LATEST REVISION D
B 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 MAINTAINED.
THIS DRAWING W.AS REFORMATTED BY AUTOCAD AT REVISION ~CH. ALl..
INC.CODE Detroit Edison Fermi 2 D DCD'S INCORPORATED, PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON MICROFILM IN DOCUMENT CONTROL.
PREPARED BY u
DATE TITLE LOGIC DIAGRAM REACTOR CORE ISOLATION COOLING A PORTION OF THIS DRAWING EDP 32365.BOOS REV.¢ IS AFFECTED BY THE FOLLO'WING:
SYSTEM TC CHANGE DOCUMENT CHECKED EY DATE 1----------=--=--,--,,,,,,-,,,-,---=,---+--+-------i--~=~-r-~=-,f--_-----------------;A A OTHER REVISIONS: ADDED COMPLETE PIS NO'S FDR VALVES TD AGREE 'w'ITH CECO & REV'D D'w'GS APERTURE CARD TITLE LOGIC DIAG RCIC SYSTEM TD AGREE 'w'ITH ARMS FORMAT. THESE ADMIN. CHANGES~==t========t=~~~:ff:::+/-= #
PER PEPS 0019 FALL v/ITHIN THE SCOPE OF MES09, I- APPROVED BY PLANT IDENTIFICATION SYSTEM NUMBER ARMS RECIPIENT STEP 3.1.2 ('w' /NDTD. E5100 PREPARED BY DATE ~~ ~~~-a.5 oocuMENT TYPE conEDDDINC NUC o;: t1LE: NO. n4TE p;UED TO rs D.S-TEFFKE 4-6-05 C:'. NICl-!OL.5' OTHER APPROVALS DA 0
- -05 APPROVED B / r' ,1 , /" DATE EDP POSTING ENTRl&S REQUIRE THE REV.
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