ML21130A079

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0 to Updated Final Safety Analysis Report,Section IV, Figures
ML21130A079
Person / Time
Site: Cooper Entergy icon.png
Issue date: 04/21/2021
From:
Nebraska Public Power District (NPPD)
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21130A114 List: ... further results
References
NLS2021013
Download: ML21130A079 (12)


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

, FLOW & P t1 _ _ _ _..,_

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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

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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

---8-- Core Inlet Flow 150 300 60 1350 125 250

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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 Isolation Signal r - Stand By LI quid Control Sys AC I I  : Low Reactor Water Level I I I I

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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