ML23129A281
Text
DRIVING FLO*.--
ELEVATION JET PUMPS---+.
RECIRCULATION INLET MANIFOLD RECIRCULATIO~
OUTLET
--+-t-RECIRCULATION 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
DRIVING FLOW LU 0:::
t1 LU THROAT OR MIXING SECTION DRIVING FLOW 0:::
0..
SUCTION FLOW DRIVING FLOW fj, P SUCTION FLOW & P Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Jet Pump
-Operating Principle Figure IV-3-4
NORMAL STEAM SEPARATORS WATER "- r----iH---t=ie==~=-=--...J LEVEL STEAM r----------
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Recirculation System Core Flooding Capability Figure IV-3-5
RECIRC M-G SETA Div. I I.OW LEVEL LOW LEVEL FIELD BKR TRIP COILS HI PRESS HI PRESS Div. II LOW LEVEL HI PRESS I.OW LEVEL HI PRESS LOGIC 2/2 REACTOR VESSEL FIELD BKR TRIP COILS RECIRC M-G SETS 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
OUTLET INTERNAL PORTING CONNECTING UPST"1EAM
'SIDE or STABILIZER TO SYSTEM rRESSURE AT VALVE INLET SOLENOID VALVE ASSEMBLY INLl!T AIR OPERATOR ASSEIVl!ll Y
[*-,:r:*J SYSTEM PRESSURE IONNET/
Sfl'RING SUIASSEM!ll Y fl'ILOT DISC
!HA TEDI STABILIZER DISC IUNSEATEDI Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANA!LYSIS REPORT (USAR)
Nuclear System Relief Valve Closed Position Figure IV-4-2 07/22/95
OUTLET INTERNAL PORTING CONNECTING UPSTREAM SIDE OF STABILIZER TO SYSTEM PRESSURE AT VALVE INLET PILOT DISCHARGE PORTING
//,, "."//////
/ / / /,,.* / / / / / /
SOLENOID VALVE ASSEMBLY AIR OPERATOR ASSEMBLY MAIN PISTON CHAMBER TO PILOT VENT PORT' BONNET/
SPRING SUBASSEMBLY "ILOT DISC (UNSEAT EDI
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STABILIZER DISC
!SEATED!
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INL!T MAIN DISC M.-.1N PISTON/
DISC PRE LOAD S"RING 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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I-Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT lUSAR)
Safety Valve Sizing Transient:
MSIV Closure with Flux Scram Figure IV-4-4a 07/22/96
MSIV Closure Flux Scram - MELLLA BBB 200
-&- Neutron Flux
-tr-Average Surface Heat Flux
s-- Core Inlet Flow 175 150 125
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8 Time (s) 80
-&- Vessel Dome Pressure 1450
-tr-Safety Valve Flow
B-- Relief Valve Flow
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Turbine Bypass Steam Flow 70
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QI i 40 1250 f
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0 2
3 4
Time(s}
5 6
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
MSIV Closure Transient (Flux Scram)
(Cycle 33, 1 SRV OOS,+ 3% SRV Setpoints)
Figure IV-4-4b 02/17 /23 8
'O GI 1il rx:
150 75 25 0
0 2
MSIVF/OPP/1 SRVOS for HP1 CYCLE 33 MEL_TN - E00000 POWER: 100.4% RATED FLOW: 76.8% RATED
. -B-Neutron Flux 350
- -tr-Average Surface Heat Flux
-B-Core Inlet Flow 300 250
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-a-Relief Valve Flow J/s-El~ea.
m Flow
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6 Time (s)
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Time(s) 6 7
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5 Time(s) 6 7
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
MSIV Closure Transient (Flux Scram)
(Cycle 33, 1 SRV OOS, Max SRV Setpoints)
Figure IV-4-4d 02/17 /23 8
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0 I-Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Mark IT-Quencher Discharge Device Figure IV-4-5
PILOT DISK SPP.lSCi YOKE ASSE.'!!t.Y SPRISG SEAT 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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Signal I
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Hi Temp Non Regen Heat Exch.
r - Stand By LI quid Control Sys AC Low Reactor Water Level From Reactor I
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(Closure)
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Elbow Flow Device
- I~
I Reel re Pumps
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT !USA IO RWCU LEAK DETECTION AND ISOLATION 07/22/87 FIGURE :BI 4