|
---|
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
5 4 1 7 8 '7 6 3 2 NOTES:
REWE SHUT DOVN HPCI INITlA Tllli TRANSFER SELECTOR RESET PUSHBUTTON Sl(iNAL 1$ PRESENT SWITCH 1. THE HPCJ SYSTEM lS ARRANGED FDR TEST OF PUMP AT FULL FLOV &
REMOTE POSITl N ALL VALVES FOR OPEN AND CLOSE CAPACITY AT ANY TIME EXCEPT H PB CR AUXILIARY CR TRAf!SFER RSP
\/HEN INITIATION SIGNAL OR AUTO ISOLATION SIGNAL IS ACTIVATED.
IN EVENT THE lN[TlA TIDN SIGNAL OCCURS \/HILE TEST IS UNDER\/ AY H
D£1/ICE WITCH THE SYSTEM AUTDMATlCALLY RETURNS TO START-UP MODE.
- 2. ALL PDVER FOR OPERA TlON OF DC VAL VE MOTORS SHALL OR!GlNATE
,-------------------------------------------------7 FROM A PLANT DC BUS. PD\/ER FOR AC MOTOR OPERATED VALVES I I SHALL ORIGINATE FROM ANY EMERGENCY AC BUS.
I I REMOTE SHUTDOVN ISOLATION REACTOR VESSEL REACTOR VESSEL HJG, ORYVELL Hllll DRYVELL lRANSFER SELECTOR LEVEL 1 TRIP LEVEL 2 TRIP PRESSURE PRESSURE I SVITCH IS IN 'ON' PUSHBUTTON UNLESS DTHER\IJSE SHD\IN, I SWITCH DEPRESSED I POSITION ALL INSTRUMENT PIS NUMBERS ARE PREFIXED E41.
I Pl PS I ALL .VAL VE AND EQUIPMENT PIS NUMBERS ARE PREFIXED E4100, E4150 (AS APPUCABLD.
LIi LIS TRANSFER I LP B21N692B LP B21N694E LP B21N694F LP I WITCH RSP PB CR B21N692A I I 4. DELETED I REF 1 REF. 3 I I I SEE NOTE 7 5. AUXILIARY RELAYS i DEVICES NOT SHOIIN ON LOG[C DlAGRAMS EXCEPT VHERE I I ,---------7 REQUIRED TD CLAR[FY FUNCTION.
I I I I I ll'CI START SEAL-IN PERHISSIVE VHEN I HPCI STEAM 6. DELETED REACTOR VESSEL REACTOR VESIEL HIGH ORYVELL HIGH llRnJELL '- CR / SUPPLY I LEVEL 1 TRIP LEVEL 2 TRIP PRESSURE PRESSURE I PUSHBUTTON AUTO UHTIATION SIGNAL SELECTOR COLLAR II I OEPRESSEIJ UNTIL RESET IN ARMED POSITIIli PRESSURE LOV I I \I I } I 7. JSOLATl N SIGNAL SVITCHES SHALL BE OF THE TYPE THAT CLOSE I I CONT ACTS FOR THE SPECIFIED ISOLA TIDN EVENT. VHERE AUXILIARY RELAYS I
I LIS B21N692C LP LIS B2IN692D LP PS B21N694G LP PS B21N694H LP I PB RIP AUXILIARY DEVICE CR / " \ PB ZONE H4 / I I
PIS N658B LP ARE USED IN, THE ISOLATIDN CHANNELS, THEY SHALL BE PO\/ERED FROM THE STATION BATTERIES <REF.14)
G I
L ___ _ ____ _J I
I G
I 8. FOR LOCA TJON AND IDENTIFICATlDN OF INSTRUMENTS S E E ~
HPCJ INITIATED ON LOIi I l 1 t::.:...J'v REACTOR \/ATER DR HIGH PERMISSIVE VHEN I
I HPCI STEAM
- 9. DELETED _<;>_
/ DRYVELL PRESSURE !NITJATION SllllAL I SUPPLY 10. AN ALTERNATE SCOURCE OF EMERGENCY AC PO\/ER SHALL BE PRO-IS PRESENT I PRESSURE LOW VIDED TD THE JNSfDE JSOLATIDN VALVE MD F002.
r------------------------------,
EMER(iENCY
\
AUXILIARY DEVICE LP /
I I
PIS N658D LP 11. THE HPCJ SYSTEM SHALL BE DESIGNED IN ACCORDANCE 111TH THE GENERAL I CRITER[A FDR NUCLEAR PO\/ER PLANT PRDTECTJDN SYSTEM IEEE 279.
AREA COOLER HIGH TEMF'ERTURE L ________ _J TS 12. FOR CONFIGURA Tl N OF PANEL MOUNTED OPERA TORS AND INDICATORS N602B CR SEE DECO DIIG. M-2290 SH 2, REF 15, PURCHASE SPECJFICATJDN DATA SHEET SECTl N 2.4.
AC } X \
HPCJ
/ B ' JN[TIA TIDN 0 /
~ 13. ALL MOTORS SHALL BE PROTECTED BY THERMAL OVERLOAD TRIPS AND BREAKER SHORT ClRCUIT CURRENT PROTECTIVE TRIPS.
SIGNAL F 3 H7 ,---- KEYLDCK SI/ITCH
/ PERMISSIVE UNLESS TEST SlJITCH
,6 G7 SEE NOTE 7 2 POSITION NORMAL D I IN 'TEST' ,---------, RESET. KEY REMOVE -
6 D7 I ~ ACTUATES AFTER I ABLE IN NORMAL F \~_R_Ms_-+-_cR_~/
I 3 SEC. DELAY I I
P SlTI N F I
I STEAM UNE I ISOLATION SIGNAL HliJ-1 TURBINE I
I Hllll DIFFERENTIAL PRESSURE OR INSTRUMENT I
I LOGIC 'B' RESET SWITCH IN 'NORMAL' EXHOOST DllffiRAM PRESSURE REFERENCE DOCUMENTS E LINE BREAK I I 1. NUCLEAR BOILER P&JD............................ . M-2089, M-2090, M-5538 I dPISIN1~ I PIS OR LP RMS CR LP N655B 2. NUCLEAR BOILER SYSTEM LOGIC DIAGRAM......... .. 1-2090 I d'S N660B I I I 3. RHR SYSTEM P&!D ........................... M-2083, M-2084 I I [-2200 I I 4. RHR SYSTEM LOGIC DIAGRAM .................... .
'OP£N PUSHBUTTili I I I 5. CORE SPRAY SYSTEM LOGIC DIAGRAM ................ . [-2210 SEAL-IN svnrn 1s DEPRESSED I I I 6. HPCI SYSTEM P&JD ................................ M-2035, M-2043 I I I AUX. CONT t I I I
- 7. RCIC SYSTEM LOGIC DIAGRAM ................ . [-2230 72
- L-4 PB CR PERMISSIVE IJl,EN I I I 8. HPCI TURBINE CONT SYSTEM....................... TERRY TURBINE MANUAL~MR4-2 SERlES REMOTE SHUT JOVN TRANSFER I I I SEAL-IN 9. DELETED SVITCH IS IN 'ON' POSIT~ HIGH TURBINE I I I 'AUTO' SIGNAL EXHAUST I 10. LOGIC SYMBOLS ......................... .. 209A47-56; Rl-20 I I UNTIL RESET DJAP!,RAH PRESSURE PERMISSIVE UNLESS TRANIFER S\JITCH RSP I I I
I I
I I AUXILIARY DEVICE ER PIS N655D LP 11 REACTOR \JATER CLEANUP SYSTEM P&JD .......... ..
- 12. LEAK DETECTION SYSTEM DESIGN SPECIFICA TIDN ......
M-2046, M-204 7 22Al441, Rl-138 REMOTE SHUT D'IN I I I TRANSFER SWITCH 13. RCIC SYSTEM P&JD................................ M-2044, M-2045 I I I E IS IN 'ON' POSITION }
/ PERMISSIVE UNLESS STEAM LEAK ~NS[R BYPASS I
I I I 14. ELECTRICAL EQUIPMENT SEPARATION FDR SAFEGUARD SYSTEM ...................................... 22A3777; Rl-1410 I
I I
\ TRANSFER SV!TCH RSP I SELECTOR S'w'ITCH IS IN 'BYPASS' POSITION I I
I I
I I
- 15. GENERAL REQUIREMENTS FOR INSTRUMENT ATIDN
& ELECTRICAL EQUlPMENT ....................... .. 21Al 768; Rl -446 AUXILIARY DEVICE CR I I I
I I
I I 16.HPCJ SCHEMATIC DIAGRAMS ...................... I-2225-01 THRU 15 I IL_ _ _ _ _ _ _ _ _ __!I I-2221-01 THRU 12 L------* -----------------------~ 17.LDGJC DIAGRAM-GROUP 6-HPCJ !SOL. VALVE MIMIC DISPLAY ......................................................................... 1-2220-07 JSDLATlN 18.LDGJC DIAGRAM-GROUP 7-HPCI !SOL VALVE MIM[C DISPLAY,,,,,,,.,,,,,..,,.,.,,.,,...,,,,, ......... ,.,,.,......... ,..,.,., .. ,, ..... [-2220-08 1-----
AUTO SIGNAL _ / ,.) IC7 (NOTE D ELECTRONIC TRIP UNITS CT /U) ~ - - - - ELECTRONIC TRIP UNlTS (T /U) N662B i D ~ GROUP f, ]SOL. VAL VE LEGEND N661B~D SHALL BE FAIL SAFE TYPE CDE-ENERGIZE RELAY ON LO\/ LEVEU CONDENSATE STORAGE TANK LOW LEVEL SHALL BE TYPE THAT CAUSES RELAY TO ENERGIZE ON HIGH LEVEL EITHER T/U REACHING SETP INT SHALL CAUSE \
MIMIC DISPLAY
/ AA AUTO
- = SVITCHGEAR DEVICE FUNCTION NO.ANS[ SPEC. C37.2.
!EITHER T" ,HALL E
LIS LP MD F04 l, AND F042 TO OPEN. ,J B4 > ISOLATION SIGNAL
+- = FURNISHED 111TH TURBINE (SEE REF DRA\JING 8)
CAUSE MO F041 ~ F042 TO 1+56IB CMC = COORDINATED MANUAL CONTROL SVITCH OPEN ON TANK L O \ / ~ E ' PB = PUSHBUTTON SVITCH OR POI/ER F A I L U R E . ~
AM = AMMETER RSP = REMOTE SHUTDO\/N PANEL D 'll'EN' RMS= REMOTE MANUAL SVJTCH D
CONDENSATE SIPPRESSION SUPPRESS!Ili PUSHBUTTON STORAGE TAM< CHAMBER CHAHIER S\JITCH IS SEAL-IN CR = CONTROL ROOM DR RELAY ROOM LDV LEVEL HIGH LEVEL H[GH LEV[L DEPRESSED LP = LOCAL LIS LIS LIS PB CR AUX. CONT 1+56ID LP N662B LP N6611 LP 72 * 'CLOSE' PUSHBUTTON LETTER DESIGNATION SVITCH IS SHEET NO. OR REFERENCE DRA\/JNG NO.
DEPRESSED ZONE DESIGNATION PB CR MATCH CIRCLE NOT PERMISSIVE SEAL-IN VHEN AUTO ISOLATION SIGIIAL IS PRESENT AUX. Cllil. Zl}IE/i,i"'
I L!.'_71:.__-l---~T'I E
\
AUXILIARY DEVICE LP I 'CLOSE' PUSHBUTTON NOT P£RMISSIVE VHEN AUT PERMISSIVE ltll.ESS SEAL-IN 'CLOSE' PB S'JITCH SVITCH IS DEPRESSED ISOLA TIN SIGNAL IS DEPRESSED IS PRESENT PERMISSIVE VHEN PB CR AUX. C[tlT.
72
- ZONE A7 AllXIXILARY DEVICE LP I \ PB ZIINE@) / I PERMISSIVE UNLESS VALVE IS I PER~SSIV[ UNI..ESS
'OPEN' PB. SVITCH 0
/ P£RMISSIVE UNLESS FlLL Y CLDSED IS DEPRESSED I VALVE F601l <
'CLOSE' PUSHBUTTIJI IS DEPRESSED Fl.ll'f OP£N C LIMIT \ LIMIT SVITrn Iii VALVE I PB ZIK D5 / C PB ZONE C6 / \ ON /
SVJTCH VALVE PERMISSIVE UNLESS VALVE I P£RMISSIVE VHEN VALVE IS FULLY CLOSED < 1001/4 OPEN
\
LIMIT SV!TCH \ LIMIT SVITCH ON VALVE I I PERMISSIVE Wl£N VALVE IS PERMISSIVE UNLESS
'JP[N' PUSHBUTTON IS DEPRESSED --
< !OOY. [l'[N
' I LIMIT Sw'HCH ON VAf.. VE
/ \ PB ZlliE EB / I PERMISSIVE ltlLESS OVER TORQUED VHILE OPENING PERMISSIVE UNLESS VAL VE >951/4 OPEN PERMISSIVE l}ILESS I PERMISSIVE 161721-2220-01 LATEST REVISION OVERT Rat£D VHILE CLOSING UNLESS VALVE
)951/4 CLOSED E
\ TRlll SVITCH ON VALVE I \ LIMIT SVITCH ON VALVE I TROOE
\
LIMIT ON /
\ WITCH SWITCH VALVE PERMISSIVE UNLESS / PERlflSSIVE UNLESS OVERT~ffiJED VHILE VALVE )957. CLOSED B
CLDSING I B
I PERMISSIVE UNLESS VALVE
)951/4 OPEN ,
PERMISSIVE UNLESS OVER TORQUED IJHILE OPENING \ TORIIIJE SVITCH Iii VALVE I \
LIMIT S'w'ITCH ON VALVE
/ VAL VE LIMIT S'wlTCH VALVE NUCLEAR SAFETY RELATED FlLLY CLOSED OPEN CLOSE
\ LIMIT SVITCH ON VALVE I \ TROQUE SVITCH ON VALVE I LIMIT SVITCH ON VALVE D.C. REVERSING ClliTACTR 72
- 4--- GROUP 6 THIS IS AN AUTOCAD PRODUCED DRAWING.
!SOL. VALVE PUMP SUCTl N FROM SUPPRESSION CHAMBER VALVE MD F041 CHANGES OR REVISIONS MUST BE BROUGHT MIMIC DISPLAY SEE NOTES 2 & 5 TO THE ATTENTION OF THE PLANT ENGINEERING DESIGN GROUP TO ENSURE THAT CONFIGURATION AB CONTROL IS MAINTAINED.
7 D4 fl'EN CLOSE THIS DRAWING WAS REFORMA'ITED BY
.AUTOCAD AT REVISION C . ALL INC.CODE Detroit Edison Fermi 2 nc. REVERSING ClliT ACTOR 72 STEAM SUPPLY LINE lSOLATl N VAL VE MO F003 E ncn*s INCORPORATED, PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON MICROFILM lN DOCUMENT CONTROL PREPARED BY u
DATE TITLE HIGH PRESSURE COOLANT INJECTION LOGIC DIAGRAM A PORTION OF 'nllS DRAWING SEE NOTES 2,5, ~ 10 IS AFFECTED BY THE FOLL01'1NG:
TSR 29443 REV ~ SYSTEM TC CHANGE DOCUMENT CHECKED "BY DATE l - - - - - - - - - - - - - - - - l - - - - l - - - - - - - - - t - ~ = ~ ~ t - = APERTURE 1 - -CARD - -TITLE -------------------aA A OTHER REVISIONS:
UPDATED MIL TO CECO, LOGIC DIAG HPCI SYSTEM PLANT IDEN'tlFICATION SYSTEM NUMBER ARMS RECIPIENT #
ADDED REFERENCE D\/G. INFO IN ZONE E-IJ APPROVED BY UPDATED PIS i*s T CECO FORMAT. E4100 PREP~fll.~,., IDATE,7 ICHECKED~~Y;ii ,, DATE NUC OPS FILE NO. DATE [$SUED TO IS C. PulcIFER l=-10 1 97 ° ~!!,;Vl;t'c,,e~~,-- OTHER APPROVALS DAT~:
DOCUMENT TYPE CODEDDDINC 1801 7-tll-97 APPROVED BY EDP POSTING ENTRIES REQUJRll THE DRAWING NUMBER REV.
ADOlTlON OF THE ARMS STATUS CODE:
~ r , ,t,t'...- EITHER "AFCH OR "ASB' 61721-2220-01 E 8 '7 6 5 4 3 2 1