ML21130A079
Text
DRIVING FLO*.--
- JET PUMPS---+.
RECIRCULATION INLET RECIRCULATIO~
OUTLET MANIFOLD
--+-t-RECIRCULATION ELEVATION PUMP ISOMETRIC Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Recirculation System
-Elevation, Isometric Figure IV-3-1 07/22/87
THROAT OR MIXING SECTION DRIVING FLOW DRIVING DRIVING FLOW fj, P FLOW LU 0::: SUCTION
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0.. SUCTION FLOW Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Jet Pump
-Operatin g Principle Figure IV-3-4
STEAM SEPARATORS NORMAL WATER "- r----iH---t=ie==~ =-=--...J LEVEL STEAM SEPARATION DISTRIBUTION PLENUM WATER LEVEL r---------- AFTFR BREf 1\
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~--~--j Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Recirculation System Core Flooding Capability Figure IV-3-5
Div. I Div. II I.OW LEVEL HI PRESS LOW LEVEL HI PRESS LOW LEVEL HI PRESS I.OW LEVEL HI PRESS RECIRC RECIRC M-G M-G SETA SETS LOGIC 2/2 FIELD BKR FIELD BKR TRIP COILS TRIP COILS REACTOR VESSEL Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Recirculation Pump Trip (RPT)
Logic Configuration Figure IV-3-6 07/22/90
SOLENOID VALVE ASSEMBLY AIR OPERATOR ASSEIVl!ll Y IONNET/
Sfl'RING SUIASSEM !ll Y fl'ILOT DISC OUTLET !HA TEDI STABILIZER DISC IUNSEATEDI INTERNAL PORTING CONNECTIN G UPST"1EAM
'SIDE or STABILIZER TO SYSTEM rRESSURE AT VALVE INLET INLl!T
[*-,:r:*J SYSTEM PRESSURE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANA!LYSIS REPORT (USAR)
Nuclea r System Relief Valve Closed Positio n Figure IV-4-2 07/22/9 5
SOLENOID VALVE ASSEMBLY AIR OPERATOR ASSEMBLY PILOT BONNET/
DISCHARGE SPRING PORTING SUBASSEMBLY MAIN PISTON CHAMBER TO PILOT VENT PORT' "ILOT DISC (UNSEAT EDI
//,, "."////// STABILIZER
/ / / / ,,.* / / / / / / DISC OUTLET ////////:~.------- !SEATED!
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////////., M.-.1N PISTON/
////// DISC PRE LOAD
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S"RING MAIN DISC INTERNAL PORTING CONNECTING UPSTREAM SIDE OF STABILIZER TO SYSTEM PRESSURE AT VALVE INLET INL!T l: :~.;:* -: ~ i SYSTEM (HIGH! PRESSURE
~ DISCHARGE (LOVVI PRESSURE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED' SAFETY ANALYSIS REPORT (USAR)
Nuclear System Relief Valve Open Position Figure IV-4-3 07/22/95
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Safety Valve Sizing Transient:
MSIV Closure with Flux Scram Figure IV-4-4a 07/22/96
MSIVF/OPP/1S RVOS for HP1 CYCLE 32 MEL_TN - E00000 POWER: 100.4% RATED FLOW: 76.8% RATED 175 -.----,--,---.----,---.... ,......--.~-e-~--_--,-N -el~,tr-o-n=F!-UX--- -~ 35o
- &..- Average Surt .ice Heat Flux
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' Turbine sream Flow Total Reacllv1t; 100 0 75 40_ -10
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PIO 6C865 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
MSIV Closure Transient (Flux Scram)
(Cycle 32, 1 SRV OOS,+3% SRV Setpoints)
Figure IV-4-4b 02/22/21
MSIVF/OPP/1 SRVOS for HP1 CYCLE 32 MEL_TN - E00000 POWER: 100.4% RATED FLOW: 76.8% RATED 175 -r-----.---.-.-----,--~-.-----,,---->--,=.,-"'"'"Ne_u. .,..tr-on.....,F,,,..lu-x------.- 350 A*,;erage Surface Heat Flux
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
MSIV Closure Transient (Flux Scram)
(Cycle 32, 1 SRV OOS, Max SRV Setpoints)
Figure IV-4-4d 02/22/21
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Mark IT-Quencher Discharge Device Figure IV-4-5
SPP.lSCi YOKE ASSE.'!!t.Y SPRISG SEAT PILOT DISK Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Main Steam Line Isolation Valve*
Figure IV-6-1 07/22/89
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I 0 0 I I Nebrask a Public Power District COOPE R NUCLE AR STATIO N UPDAT ED SAFETY ANALY SIS REPORT !USA IO RWCU LEAK DETECTION AND ISOLATION 07/22/ 87 FIGURE :BI 4