ML21130A079

0 to Updated Final Safety Analysis Report,Section IV, Figures

ML21130A079
Person / Time
Site:	Cooper
Issue date:	04/21/2021
From:	Nebraska Public Power District (NPPD)
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21130A114	List: ML21130A062 ML21130A063 ML21130A064 ML21130A065 ML21130A066 ML21130A067 ML21130A068 ML21130A069 ML21130A070 ML21130A071 ML21130A072 ML21130A073 ML21130A074 ML21130A075 ML21130A076 ML21130A077 ML21130A078 ML21130A079 ML21130A080 ML21130A081 ML21130A082 ML21130A083 ML21130A084 ML21130A085 ML21130A086 ML21130A087 ML21130A088 ML21130A089 ML21130A090 ML21130A091 ML21130A092 ML21130A094 ML21130A095 ML21130A096 ML21130A097 ML21130A098 ML21130A099 ML21130A100 ML21130A101 ML21130A102 ML21130A103 ML21130A104 ML21130A105 ML21130A106 ML21130A107 ML21130A108 ML21130A110 ML21130A117 ML21130A118 ML21130A119 ... further results
References
NLS2021013
Download: ML21130A079 (12)

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:::

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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

//,, "."//////

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SOLENOID VALVE ASSEMBLY AIR OPERATOR ASSEMBLY MAIN PISTON CHAMBER TO PILOT VENT PORT' BONNET/

SPRING SUBASSEMBLY "ILOT DISC (UNSEAT EDI

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INL!T MAIN DISC M.-.1N PISTON/

DISC PRE LOAD S"RING l: :~.;:* -:-~ i SYSTEM (HIGH! PRESSURE

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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

175 150 125 MSIVF/OPP/1SRVOS for HP1 CYCLE 32 MEL_TN - E00000 POWER: 100.4% RATED FLOW: 76.8% RATED

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8 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 9

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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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7 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)

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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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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT !USA IO RWCU LEAK DETECTION AND ISOLATION 07/22/87 FIGURE :BI 4