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*.--

- 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 _ _ _ _..,_

LU ,.....

0:::

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\

1 I

I I

I I

I r I I I I I I I I

~--~--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!

///// / // // / ~---~,---.,r- 7:::1

///////////

////,'//////

////////., M.-.1N PISTON/

////// DISC PRE LOAD

/// /

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

i i*I I c- i

!2 lg

()

I I

N  :)6~

I:=

I W I UJ  ::,:

D

....J u.

w I-a:

,:;i5 I

2 i II. 2i I

" )i i~ ~

l

.; L 2 g ~~

~ ~

1031~8 ~O lN3J 83dl le!!

ti:~

-=~

~~t=i

!!! J. i-i~~li il~r I

I

--u

-N*

ci_ N w

UJ LU

~ ~

UJ

c w

~

I- I-

---

'----'-'------....l...JW-L J....L...l...J...J...U:0

~ g ~ 0 103188 ~0 lN3J 83dl 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

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

--a- Core Intel Flow 150 300 60 1350 125 250

!l{,

'S 50 1300

~

100

• 200 &;

't!

e:, 'ti

!O >< 'l;; 40 a::  ::J Q:

/ i ii:

/

• 15 150 2 C

.fl:

¢

!l

z 30 1200 50 100 t I

20 I 1150 25 50 10 1100 0 0 0 0 2 4 5 6 7 8 9 0 2 3 4 5 6 g 8

Time(s) Tlme(s) 125 -,-----,----,----,---,-~----,.--e--=--__,,..,. e-s-se.,,.IL,-e-.v-,el---.-- 60 10 I . *** -e- Void Reactivit'I

~ Vessel Steam Flow Scram ReactMty

!--a-- Feectwater Flow

• Doppler Reactivitf

' Turbine sream Flow Total Reacllv1t; 100 0 75 40_ -10

~

~,,,,

ti

'O ,,,,

~

 ;;-

~ 50 30 ~ ~ -20

,c u

§,

er.:

25 20 ..J -30 0 -40

-25 0 0 2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

3 4 5 6 7 8 9 0 3 4 5 6 7 8 9 Time{s) Time(s)

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

~ 50 1300 (II 100 200 ~

'O s'-1l ~

X "Cl Q

0::  ::, io 40 0::

ii:

• 75 150 e C

z Q

1200 50 100 20 1150 25 50 10 1100 0 0 0 -l'----"'4'""-<""--'if'--J"'!--l""+i"'"""'~I-"-........+"---'"......,........_+""'...,....-+---+---+ 1050 0 2 4 5 6 a 9 5 6 9 Time (s) Time(s) 10 Vessel Steam Flow Feectwater Flow Turbme Steam Flow 75 40_ -10 t:

.2 Ql i:i

'O (I)

Ql ~

s'-1l (I) iS" 30 ~ ~ -20

..,,0::: .Q

'-1l <.l g

'-1l (II 0::

e (II 25 ..I

-25 +---+-t---+--+--+-+--+--+--+--<'--+ --+---+--!-+--+---+- 0 2 4 6 7 9 0 2 4 5 6 7 9 Time(s) Time(s)

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

a:

w

c a:

u w z

w 0

~

0 *** c.,

• • • c.,

-~ z w N *** a:

ll..

0::

....a:: ....

w 0  !:

c., Q.

n.. Q a::  ::, 0

c Ill w 0 a:

(.,l Ill <

w w

0 :c :i

.5 Vl

~

0 <{

a:

-l

..J LU

c Vl V) 0:

0 I-0:

0 ll..

ll..

(/)

l:

er ***

1 0

E ...

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

,-- -- - - - - - - - - - - i - - HI I Space Temp I

8 8 I Auto  :- - Hi Temp Non Regen Heat Exch.

RMS I--

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

l I r---,-./7J I 1--

__ / J

___ _ lI MO I ....-- --- I 15 I MO I 18 I -

-,- I (Closure)

- - -- - * -i-lr~

I~ ~nl From Reactor I I i Reel re I X-14 Elbow I Pumps I Flow I I Device I I I I

I I

I I I I L __ _ __ T ___ ___ __ ...JI I I

I Primar y I I 0

Cont a lnment I I I

I I I L-------7

<2>

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