ML19137A133
| ML19137A133 | |
| Person / Time | |
|---|---|
| Site: | Cooper |
| Issue date: | 04/24/2019 |
| From: | Nebraska Public Power District (NPPD) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19137A206 | List:
|
| References | |
| NLS2019023 | |
| Download: ML19137A133 (13) | |
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----------
1 I
I I
I I
I r
I I
I I
I I
I I
~--~--j SEPARATION DISTRIBUTION PLENUM WATER LEVEL AFTFR BREf 1\\
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
////////:~.-------
STABILIZER DISC
!SEATED!
/ / / / / / / / / / /
~---~,---.,r-7:::1
///////////
////,'//////
////////.,
//////
/// /
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
150
-e-eu on lux {right axis)
-),I:- Ave Surface Heat Flux
~-:- Core lniet flow 125
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100
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0 2
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7 El Time (sec}
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~
Vessel Steam F!cw T rni:}ine Steam Flow 200
~
Feemvate, Flow 150 100
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re 0::
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8 Time (sec}
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2
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Bypass Valve Flow 3
4 5
Time (sec) 360 320 280 7
B
,.....,..........,,.....,.....,.....,..........,,.....~~~~~~~,.....~,.....,.....~ 4.0
-e-Void eacthnty 0
-,<;- Doppler Reactivity
-r-Scrarn Reactivity
~
Total Reactivity
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2 3
4 5
6 7
Time (sec)
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
MSIV Closure Transient (Flux Scram)
Figure IV-4-4b 01/21/19 3.5 3.U 2.5
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-i.5 8
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150,-,--~~~~--~--*--~~e-u--t~o-n~~,u~x-(~ri-g~. =t _a_x~is~1~ 750
-l'I:- Ave Surface Heat Flux 125 100 75 50 25 250 200 150
!00 50 I'
-50
~- Core Inlet Flow 625 I
I 125 0
2 3
4 5
6 7
3 Time (sec)
~--~~---~~~~~-~~--~-~
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evel (rig!1t ax,g) 0 2
~
Vessel Steam F!ow
--11!- Turbine Steam flrn.v Feectwater Flow 3
4 5
6 7
Time (sec)
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---;)z-90
--;i(r-360
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Bypass Valve Fiow 80 320 70 60 40 3()
20 8C 40 a
0 2
3 4
5 6
7 Time {sec) 4.G ~-~-----------~~~~~~--~ 4.G
-a-Void,eactivity 3.D 2.5 0
-'>I:-- Doppler Reactivrry
-r-Scram Reactivity
-.- T otai Reactivity 2
3 4
5 Time (sec)
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
MSIV Closure Transient (Flux Scram)
Figure IV 4c O 1 /21119 15 3.0 2.5 8
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0:
- ft.
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0:
MSlVFIOPP/1SRVOS for HP1 CYCLE 31 MEL_TN - EOOOOO POWER: 100.4% RATED FLOW: 76.8% RATED 175 --------------.,----~-le-u-trc_n_F-iu-x ---~ 350
-ts-Average Surface Heat Fiux 150 125 100 75 50 25 0
0 2
3 4
5 Tin;e (s)
- Core inlet Flow 300 250
'o 200~
100
-50 0
6 7
g 125 ----------------"'-------v-:&s-s0-.!-L.e-,.-
.. e-i -~ ?!}
75 50
- '0, 25 0
0 2
3
tr-VesseJ Steam Fla:.'.,
-a-FeedivatBr Flow
-$- Tmtme Steam Roe.-;
r~ ~-~
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Time (s) 6 7
/
8 g
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z;.
60 t350 50 1300 30 i200 20 1150 Time {sl 10.-----------,--------.,-c-cT,~o,~d~Ra~a~w~,.-~,4-----i
-tr-Ser.ax R~a:t*i1t:.,
-a-Doppler Reactr'llt1
-s-- Tota! F,ea,:I~'iiti 0
-10
~ -20
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0:
-30
-40
-50 +---1---t-+--t-----+---t-+--+--a--+---t---1 0
2 3
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Time {s) 6 8
9 PIO 095C0 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
MSIV Closure Transient (Flux Scram)
(MELLLA, 1 SRV OOS, Max SRV Setpoints)
Figure IV-4-4d O 1/21 /19
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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
I
i-- HI Space Temp I
8 I
Auto RMS I-- Isolation I
Signal I
I 8
Hi Temp Non Regen Heat Exch.
r - Stand By LI quid Control Sys AC Low Reactor Water Level From Reactor I
I l
J r---,-./7 MO 15 I
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Primary Cont a lnment X-14 I
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(Closure)
- - -- - -i-lr~~nl I
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