ML21130A104

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0 to Updated Final Safety Analysis Report, Section Xiv, Figures
ML21130A104
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: ML21130A104 (59)
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Text

CADD Fl LE: C0048885 NUCLEAR SYSTEM PARAMETER VARIATION EVENT OPEN/CLOSE ANY VALVE STOP/START ANY COMPONENT ELECTRICAL FAILURE MANIPULATE ANY CONTROL DEVICE SINGLE OPERATOR ERROR TYPES EVENT APPLJCATJON EVALUATION OF DAMAGE OF RADIOACTIVE MATERIAL BARRIERS FUEL BARRIER REACTOR COOLANT PRESSURE BOUNDARY Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

STATION SAFETY ANALYSIS-METHOD FOR IDENTIFYING AND EVALUATING ABNORMAL OPERATIONAL TRANSIENTS FIGURE XIV-4-1 08/01/03

CATEGORY OF RADIOACTIVE MATERIAL RELEASE DD FILE: C0048886 ACCIDENT TYPE COMPONENT MECHANICAL FAlLURE FUEL OVER-HEATING PIPE BREAK COMPONENT MECHANICAL FAILURE FUEL OVER-HEATING PIPE BREAK COMPONENT MECHANICAL FAILURE FUEL OVER-HEATING PIPE BREAK COMPONENT MECHANICAL FAILURE FUEL OVER-HEATING PIPE BREAK COMPONENT MECHANICAL FAILURE FUEL OVER-HEATING ACCIDENT APPLICATION EVALUATION OF DAMAGE TO RADIOACTIVE MATERlAL BARRIERS SEC-ONDARY RELEASE OF RADJOACTIVE MATERIAL RADIOLOGICAL EFFECTS OFFSITE AND ONSITE DOSE OFFSITE AND ONSITE DOSE OFFSITE AND ONSITE DOSE i2i~= 1---------t-"'1 OFFSITE AND ONSJTE DOSE MENT OFFSJTE AND ONSITE DOSE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

STATION SAFETY ANALYSIS-METHOD FOR IDENTIFYING AND EVALUATING ACCIDENTS FIGURE XIV-4-2 08/01/03

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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

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I' Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

ATWS - Inadvertent Opening of a Relief Valve - with ARI Figure XIV-5-23 07/22i96

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(J)

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o.~

0.8 TIME <SECl 1.2 1.6*10' Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Transient Response ofIORV at MELLL and EOC Figure XIV-5-23a 09/19/00

1-w w

LL ACTUAL l(l'Q ********* fl 1-.R 9'.NSED LEVEL. ***** ft

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<SECJ I.6*10' Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Transient Response ofIORV at MELLL and EOC Figure XIV-5-23b 09/19/00

0 lO-u w Ill -

w

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"::1' Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT fHSAR' ATWS - Pressure Regulator Failure open - with ARI Figure XIV-5-24 07/22/96

275 Neutron Flux/% Rated}

0-- Average Surf ace Heat Flux rtYv Rated)

~

Core Inlet Flow(% Rated) 250 -e-Core Inlet Subcooling (Etu/lbm}

225 200 175

.., 150 i

<? 125 100 75 50 25 0

200 175 150 125 100

~

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50 25 0

-25 0

5 10 15 20 25 30 50 Time(sJ

-e-- le-*.:B fin.ma,,-e Sep Slrtrt;:*

~

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is-Tuffifule Sti?:am Ff.il",;,li f% Raw;t."J,

-e-Fee@~Rmvn-::.F~;.

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450 -

400 350 300

" 250 2l "'

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<$- Safety vatve Flow (% Rated}

r

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0 10 20 30 40 50 60 90 100 Tm>e(s)

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5 10 15 20 25

31) 35 40 45 50 Time{s)

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

ATWS - Pressure Regulator Failure BOC, 76.8% Flow, 3 SRVOOS,

+70 PSI SRV Setpoint Figure XIV-5-24a 02/08/16

jbl)()

1Mi!i 1400

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1300

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'.l anuo WJOO Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

ATWS - Pressure Regulator Failure BOC, 76.8% Flow, 3 SRVOOS,

+70 PSI SRV Setpoint Figure XIV-5-24b 02/08/16

w L

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D D co Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT <USAR)

ATWS -

Loss of Normal Feedwater

- with ARI Figure XIV-5-25 07/22/96

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rr,--

1

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---+------------- :::1' 0

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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT <USAR' ATWS -

Loss of Normal AC Power

- with ARI Figure XIV-5-26 07/22/96

1-l.UTRON rLUX **,......

  • 1.

AVG SU1f f£AT FL X,...,1.

IN...ET S,llCCQ l

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0 u.J f--<

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°"

(0()2£1 102299 ono.3 o.~

b I

o.~

0.8 TIME <SEC) k.

0.8 TIME (SEC>

~

l 1.2 1.6*10' Cm£ PR£5SU,( *** H.psia OCH: PR£ssu,[ ***.... psi<1

  • STEN1...INE PRES ~ D l,psio
  • STEN1...lt£ PRES t h 6.psio t~rRO,CUMPQ<

io llu 1.2 J.6*10' Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Transient Response ofLOAP at MELLL and EOC Figure XIV-5-26a 09/19/00

ACTUAL LEVEL ********* ft 1-R SENSED LEVEL. ***** ft hll 9::~0 LEVEL ****** ft Core 8oN>n Cone

  • ppm/ l 00 is. 1 -------t-------t--------+---------l-----
s. 1 -----t-----7f-------+;,c==~~""=J....----

1-w w

LL Oil C002£1 102299 0330.3 o.~

0.8 TIME CSECl 1.2 1.6*!0' Vf.S!B_ STEN1 fl.****

  • r.
  • TWBINE FLOO.,. *....... 1.

RV fl'.. *******...... 1.

fN FUJII............... 1.

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0 w I-<

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l 0.8 TIME (SEC>

1.2 t.6*10 1 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Transient Response ofLOAP at MELLL and EOC Figure XIV-5-26b 09/19/00

"'" ----------,---~-,----,----,

TIME,HR

"' 1 I

~

35 -'/.,-----+----t------t-----i---~-4

/'

w J ll j

5 +;-----+----+-----1----*i-----,

i

!J 1.

TIME,HR

~1----4----+----~---~----

j

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v+---__ _,_,,__, ___ __,_ __ ~-c+-~~-.:--~--c-<

Nebraska Public Power District COOPER NUCLEAR ST A TION UPDATED SAFETY ANALYSIS REPORT (USAR)

Station Blackout Figure XIV-5-27 02/12/15

150 ~----,--~--,---...---,----.,,---B--

N_eu...,.tr_o_n =Fi-ux----~ 3oo

-,.tr** A.eraoe Surtace Heat Flux

-,,a-Core :ntet Flow 125 250 100 200 S'

(I.)

~

11'

~

150 ~

50 25 0

0 5

10 15 20 25 Time(s) 30 35 u::

0

~

,:., z 100 50 0

40 45 50 150 ~~--.-~---,---..---,--..--.---,,.~-,,---.--::r-..,,:~-.,.,,ve-s-se...,.,.,..L-es,-,e,-l ---,- 70 Vessel Steam Flow 125 75 50 25 0

-25 0

5 10 15 20 25 30 Time(s)

-S-Feedwater Flow

-**"1-* Turbine Steam Flow HPCI Flow(% of FA1 35 40 45 50 60 50 40 ci.

VI 0

.Q 11:1 30 :§.

20 Q

Q>

...J

'0 Q)

'1i; Cr!

';;ft lO ~---,-----,.--,---...,.......-~--.-_---s,-."""*

_'-'..,..e-ss-e""'I D""*o_m_e--,P,,...re-s-su-re-, --r 1200

  • -t.-- Safety Valve Flow 60 50 40 30 20 10 0

0 5

10 15 20 10 0

-30

-B-** Relier 1/alve Flow

......,_, Turtnne Bypass Steam flow 25 Time(s) 30 35 1150 1100 950 900 850 40 45 50

--&- VOIO Reactivity Scram Reacti*1ty

-s-Doppfer ReactMty

          • Total React1v1ty

,ft""'":,--..**,,..,,~.-

/'

/

"~/,A'.;*--t:r--,"'.,.,, ~,.~-~*****~;.,, __ ;t(

!\\

/ /,

"t... i.;,,~ ** _/

')~\\'-*,H</ lit -----+--+---+-+---t--+-\\-,.--1'._/ ______

---i __

-!--+---i 0

5 10 15 20 25 30 35 40 45 Time{s)

Nebraska Public Power District COOPER NUCLEAR ST A TION UPDATED SAFETY ANALYSIS REPORT (USAR)

Inadvertent HPCI/LS Turbine Trip 50 Most Limiting during Cycle 32 with all TBV in Service Figure XIV-5-28a 02/22/21

150 ~--~-------~-~*-*--N-eu-tr_o_n=Fl-ux----~ 3oo

,.,,~. Averat;ie Surface Heat Ftux 125 100

.. e,--t1*

,;-....,~-R------++--8-*8--

-e-- Core Inlet Ftow 250 200 6'

¢>

'iii QC

~

150 ~

50 25 0

0 5

10 15 20 25 Time(s)

Li:

C: e =

<P z 100 50 0

30 35 40 45 50 150 -~~~~---~-~~~-~---&--~-~le-ss_e_l L-.e-ve~I--~ 60 125 100 75 50 25 0

-25

"'-6 Vessel Steam Flow

-B-Feedwater flow Turbine Steam flow HPCI Flow[% o( FW')

50 40 E

ii:

30 ci.

> 0 .Q ~ 20 :§. Q> Q ..J 10 0 +--+---+-........... -+--<-+----+---+--+--+--t-,--+--+--+--1---+---+--+ -10 0 5 15 20 25 30 Tlme(s) 35 40 45 50 '0

> 0:: -30 -40 l, i 10 15 20 25 30 Time(s) 35 40 45 1050 1000 950 900 50 --e-Void Reactivity Scram Reactiv,t., -&- Doppler Reactivity --~---* Total Reactr,,ty -50 +---+--+---+--+--+-+--+--+---+-+--+-~--+-+---+--.....--i-+--l 0 5 10 15 20 25 30 35 40 45 Time(s) Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Inadvertent HPCI/L8 Turbine Trip Most Limiting during Cycle 32 with one TBVOOS Figure XIV-5-28b 02/22/21 50 1200 ~ 1000 C. w a: w 800 a: ri. w w > 600 50 40

  • -~

e UJ a::: V) V) UJ 30 a::: 0... _, uJ 3::: a::: 0 20 10 0 0 2 3 Ae = 0.0147 H = 6 FT TEST OATA CALCULATED x-- X 0

  • o Tm= 184° F, CARRYOVER ::::95%

Tm= 70° F, CARRYOVER::::-77% X To;= 64° F,CARRYOVER:::;30% 0 To;= lOJO F, CARRYOVER:::: 8% CALCULATED HOMOGENEOUS CARRYOVER - - - CALCULATED ZERO CARRYOVER

  • --CALCULATED ZERO CARRYOVER AND CONDENSATION 4

5 6 7 8 TIME (SECONDS) Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Loss of Coolant Accident Humboldt Primary Containment Pressure Response FigureXIV-6-1 03/27/00 1200 As" 0.0573 sq. ft. 1200 To= 1500f 1000 1000 U) ~ w a: ~ 800 v., 800 w a: Q.. w v., v., ~ 600 600 0 TEST DATA CALCULATED HDMOGENEDUSCARRYOVER 60 60 50 50 0-ZERO CARRYOVER ~ 40 40 v., ~ w a: v.,.,, w 30 30 a: Q.. w s: Ag=AREA OF THE BREAK a: 20 20 0 To=ORYWQL TEMPERATURE 10 10 o.__ ______ __.1...-______ -'--------"-------...A 0 0 2.0 4.0 6.0 8.0 TIME (SECONDS) Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Loss of Coolant Accident Bodega Bay Primary Containment Pressure Response Figure XIV-6-2 03/27/00 1200 ~ .e w a: 1000 Cl) Cl) w a: 0.. w Cl) 800 Cl) w > 600 50 40 .e w a: Cl) Cl) 30 w a: 0.. w s: 20 a: 0 10 0 0 2 4 6 8 TIME (SECONDS) As= 0.021s n2 To= 65 Of 0 TESTOATA CALCULATED HOMOGENEOUS CARRYOVER ZERO CARRYOVER As= AREA OF THE BREAK TD= DRYWELL TEMPERATURE 10 12 14 16 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Loss of Coolant Accident Bodega Bay Primary Containment Pressure Response Figure XIV-6-3 03/27 /00 ~o r--r----,r---.---.---,---r---.--....--....--,---,---r---r----,---r--,

  • e e

140 120 ~ 100 0:: ~ w 0:: 0..

j 80 w

0:: 0 ~

E x 60
E 20 t AT 184 psia AH-33

\\ \\ t,. \\ \\t-* HUMBOLDT BAY TEST DATA BODEGA BAY TEST !WITH DEFLECTORI DATA FLAG I / 1 IN01CATES CALCULATED POINTS ,_,,k~,':;:~!:'----------t B-26 B-17.30 H-22

----- -,fl,.

0,.__..__..__..__.,..,__.,..,__.,..,__.,..,__..__..__...__.,..,__...__...__...__...___,

10 20 30 40

. 50 60 70 80 90 100 llu 17, 1 IO

!AO 150 160

.VENT ARF'- BRf.'-1< ARf'- flATIC A_. ~

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Loss of Coolant Accident Comparison of Calculated and Measured Peak Drywell Pressure for Bodega Bay and Humboldt Tests Figure XIV-6-4 03/27/00

CClOPEn cnm>ER CClNT

RESPONSE

CllNl RE51'llN5t USRR CASE A

60.

1 ORYHELL PRESStjHE i

WETWELL PRESStnE USAR CASE A 300.

, ORYHELL TEMPEi HllJIIE 1 SUP. POOL TEM.RATI IRE l!Q, I 1

l.'.)

If

\\ I I

  • -*(

(.()

Q_

I'-

I

20.

w a:

J CJ)

CJ)

LJJ a:

CL

o. Lw....1-1
0.

1.25 2.5 LCIG TIME - SEC 1216') 1101,11 Cue A NOTE:

I 200.

LI..

(..'.)

I I w 0

I I

w a:

> I 00.

I-a:

cc w

CL

~

w I-I l

I

'>I' 3.75

5.

O F 1 1 1 1 I 1 1 1 1 I

b.

1.2s 2.5 3.75

5.

U*G TIME 121Hl l'IOU Operation of both RHRS coollng loopa-4 RHRS pumps, 4 RHR Service Wuer Booster pumps, 3 Service Water pwnp1, and 2 RHRS heat exc:hangen - with containment spray *.

The short term response curves (i.e., prior to 600 seconds) have been shown on this figure for information_ only. Refer to Section 6.3. 7.1 and Figures XIV-6-1 s" and XIV-6-19 for the short term analysis.

- SEC This case has not been reanalyzed.

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Loss of Coolant Accident Primary Containment Pressure and Temperature Response Case A Figure XIV-6-5 03/14/02

6U.r*-------,

40.

(.'.)

(Ji Q_

I

20.

w a:

en

([)

I.I.I a:

Q_

w am, 111'8l nto.11 1.25 2.5 LOG TI ME - SEC CaseB NOTE:

COOPER COOPEf{

CONT

RESPONSE

USAR CASE B CONT RE°SPONSE USAR CASE B 1 0RYHELL PRESStjRE 1 WETHELL PRESSl flE 300.

, 0RYHELL TEMPE r11ns 1 SUP. POOi. TEM 'RRTURI:

/"\\ ___ _

200; l.J..

<.!)

w 0

I llJ a:

> 100.

I-a:

a:

LI.I (L

E LLJ I-3.75
5.
0. o.

1.25 2.5 3.75

s.

3"11 CIOTII LOG TIME

- SEC lllCU 1110.*

Opentlon of one RHRS coollDg loopwlth2 RHRS pumps, 2 RHR SeIVlce Water Booster pumps, 2 SeIVlce Water pumps, and I RHRS heat exchangen - with cont.1:lnment spray.

Tlie short term response curves (i.e., prior to 600 seconds) have been shown on this figure for information only. Refer to Section 6.3. 7.1 and Figures XIV-6-18 and XIV-6* l 9 for the short term analysis.

This case has not been reanalyzed.

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Loss of Coolant Accident Primary Containment Pressure and Temperature Response Case B Figure XIV-6-6 03/14/02

60.,

I I

40.

l.'.)

II v I I

U1 Q_

20.

l.1j a:

)

en

<n w

a:

0..

O.LLI..

o.
t. 25
  • 2,5 LOG TIME - SEC 216t) l'1l,lll CaseC NOTE; COOPER CCICIPER CONT

RESPONSE

CONT

RESPONSE

USAA CASE C USRR CASE C I ' ORYWELL PRESSl1AE 2 HETHELL PRESS! RE 300.,

~\\ I I

I* OA'l'HEU. TEHPE~llJIIE 2 SUP. POOL TEHI 'RRTllRE.

1*-

200.

u..

<.!)

I I

w Cl w

a:

)

I-a:

a:

w 0..

k w I-I I

I 3.75

5.

O E, 1 1 1 I 1 1 1 1 I

b.

1.2s 2.5 3.75

s.

~ cmt LOG TIME IZIMS nu **

Operatlon of one RHRS cooling loop with 1 RHRS pump, 2 RHR Service WtU/l Booster pumps. 2 ~ervice Water pumps, and 1 RHRS heat exchangers - with containment llpt'ly.

The short tenn response curves (i.e., prior to 600 seconds) have been shown on this figure for infonnation only, Refer to Section 6.3. 7.1 and Figures XIV-6-18 and XIV-6, I 9 for the short tenn analysis, This case has not been reanalyzed.

- SEC Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Loss of Coolant Accident Primary Containment Pressure and Temperature Response Case C Figure XIV-6-7 03/14/02

GO.

40.

~ -

(f)

CL I

20.

LJ.J a:

)

(f)

(n w

a:

a..

"' 00111 21u,11u.,

1.25 2.5 LCJG TI ME *- SEC CaseD NOTE:

COCJPER COOPER CONT

RESPONSE

CONT

RESPONSE

USAA CASE 0 300.,

USAR CASE 0 I DA'l'I-IELL PREsswir

/\\. I I

I I DRYHELL TEHPEiTUAE a HETHELL PRESSl RE 2 SUP. POOL TEH RAT! IRE 200.

l.1..

c.::,

w 0

I L!J a:

J 100.

I-a:

a:

LJJ o_

E w,-
o.

[__~~

3.75

5.
o.

1.25 2.5 3.75

5.

ll<ft 00111 LCJG TIME *- *SEC 12161) 1112,1 Operation o( one RHRS cooling loop with I RHRS pump, 2 RHR Servli:4 Water Booster pumps, 2 Service Water pumps, and I RHRS heat exchangers - no containment spray.

The short term response curves (i.e., prior to 600 seconds) have been shown on this figure forinformation only. Refer to Section 6.3. 7.1 and Figures XIV-6-18 and XIV-6-19 for the short term analysis.

This case has not been reanalyzed.

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Loss of Coolant Accident Primary Containment Pressure and Temperature Response CaseD Figure XIV-6-8 03/14/02

COOPER CONT TEMP RESPONSE TO l.OCA FOR CASE.£_ ASE

'100

' /')

300 -u t

I

§

',I 5 200

\\

I-<

0::

~

I:!

~

I lOO I,

2, 3,

AAS 00210 0)121 J91l,&

LOG TIME - SEC COOPER CONT PRESS. RESl'ONSa TO LOCA FOR CASE.E-~ASE ss. ~

~~

1, 1

O\\.I AIRSPACE TEM' I

ll.J PRESSURE 1-1-1 PRESSURE.

s,

~o. r----1-~~=--+----+-----+----

~

I

~

~

2s,L I

~I.

l 10.................._..................... _______ __. _____ __. _____ __. ____

I, 2,

'5.

q,

s.

~

1 00210 191M LOG TIME - SEC COOPER I

SP TEMP CCM' iEHP RESl'CNSE 1-1-1 AIRSPACE TEI'?,

TO LOCA FOR CASE-dASE 300, l-------+-------+-------1-..:.-------+-----

200, LI..

,,<.!) \\~'

~

I

~ lOO, I-<

0::

~

w.J I-0, I,

MS 00220 0'11<1 1912.0 CaseE NOTE:

2,

3.
s.

LOG TIME - SEC Operation of one RHRS cooling loop with 1 RHRS pump, 1 RHR Service Water Booster pmnp, I Service Water Pump, and l RHRS heat exchanger - with containment spray.

The short term response curves (i.e., prior to 600 seconds) have been shown on this figure for information only. Refer to Section 6.3.7.1 and Figures XIV-6-18 and XIV-6-19 for the short term analysis.

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Loss of Coolant Accident Primary Containment Pressure and Temperature Response CaseE Figure XIV-6-9 03/14/02

'100, 300. 1--J

<.!)

,,~

I

~ 200.

I-&

~

I-I-....

I-

100, I,

~2 l OOJSa 17-'\\7,91 1 8-:

ss,

' !\\*

I I

COOPER t

Cl-l AIRSPACE TEl1' CONT TEHP RESPCNSE TO LOCA FOR CASE.F. ASE-

~

2,

3.

'I'

s.

LOG TIME - SEC

  • COOPER 1

Cl-l PflESSURE CCNT PflESS RESPOOSE 1.£.1 PRESSURE TO LOCA FOR C~SE.F JASE I

25, t---------------1--------------------

~

~*

10, I.

2, li.

  • -1.
s.
2 t OOISl 17<1,; I

)

LOG TIME - SEC 300 200 w..

I I

§ ~

', ~ 100 I -

0, I,

R.IS 00l8I 0~21 J7*7.9 I

COOPER SP TEMP CCNT TEHP RESPa-&

lol4 AIRSPACE IDP TO LOCA FOR CASE.F

  • ASE

~

I I

2.
3.

'I, 5,

LOG TIME - SEC Case F Operation of one RHRS cooling loop with 1 RHRS pump, I RHR Service Water Booster pump, I Service Water pump, and 1 RHRS heat exchanger - with suppression pool cooling.

NOTE:

The short term response curves (i.e., prior to 600 seconds) have been shown on this figure for information only. Refer to Section 6.3.7.1 and Figures XIV-6-18 and XIV-6-19 for the short term analysis.

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Loss of Coolant Accident Primary Containment Pressure and Temperature Response CaseF Figure XIV-6-9A 03/14/02

C, C, -

M C, N

0 -

C, 0

S!

7

.,.,~------...

M_.__ ______

N,.___ ______

___.O

~

0 ci O

ci 0

(Aep Jad %) 3l'v'H )l'v'37.LN3IAINl'v'.LNO::l Nebraska Public Power District 0

(I)

~

I-z LiJ Cl

(..)

(..)

<(

a::

LiJ I-lL

<(

LiJ

~

I-COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Primary Containment Leak Rate Figure XIV-6-10

0 N

~ -

00 ci c.o ci N

0

..c w

en ct w

_J w

a::

LL 0

z 0

j::

ct a::

=>

0

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0 c.o 0

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0..,.

N0l.l:)V3l:I %

0 M

0 N

0 0

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Primary Containment Capability Index for Metal Water Reaction Figure XIV-6-11

DD FILE: C0048887 w

z p:)

IX I-D I-

<[

IX w

z w l'J A

z D u

.0

~.----+-----t----.-------...__ __ _,_ __ _,

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1-(,f)

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2_J Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

MAIN STEAM LINE BREAK ACCIDENT BREAK LOCATION FIGURE XIV-6-12 08/01/03

,------"T"------,,------...... -.

03S070 A77.:I S3A1'vA NOll.'v70SI ---

0

<D 0

'1)

Cl) w o.r,

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z g Q

~

IX!

N.

L-____

....... :--____ __,o o.r, 0

0 N

o.r, BREAK FLOW RATE (lb /sec x 103) 0.....

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Main Steam Line Break Accident Mass of Coolant Through Break (10 Second MSIV Closure)

Figure XIV-6-13a 09/29/98

u LIJ (f)

L co

_j uJ I-<

a:::

3:

0 _j LL.

COOPER NS OBA STMO BRK BATTERY FAILURE 1 BREAK 1 t

BREAK 2 a BREAK 3

  • 1 TOTAL BREAK FLOW II I

~

1*SRY I

1

  • 5 - *
1. ir---------+---------1---------'I.

O, 5 H-1-S-*, s 1 5

  • t..s...LL1.t-..._s.l-1...L~~l..s-s.t.Lli-Sj.1~1-1..!..LLL&**'--'..s-SJ.~-s....s..s..i4 -1/4..1:..LL1.4l---\\~-1---------

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I I I s It e a o.s 1.5

2. XI O 4

LIP 022EO TIME

1.

(SECOND) 11189&

0~~1.a Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Steamline (Outside Containment) -

DC Power Source Failure (Nominal)

Break and SRV Flow Rates (5 Second MSIV Closure)

Figure XIV-6-13b 03/27/00

O> ]

w a:

(I)

(I) w a:

Q.

I-z w

E z ci:

I-z 0 u 50,-----------------------------------------

50 40 30 20 10

~WETWELL

'NED0-10;n9 BLOWDOWN FLOW RATE o----------'----------i....--------...&.----"----""'

0 2

4 6

8 TIME (sec) 10 12 14 16 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Containment Pressure FigureXIV-6-16 03/27/00

~

0 it 0

0 co

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(I)

L.

n.

Q)

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........ **. -... "~.....

~

0 it 0

0

~

0 0 it 0

0 d 0

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l!)

N 0 N l!)

~

0

~

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0 0

Cl) 1/) -

Cl)

E r:

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Containment Pressure Response Figure XIV-6-16a 09/19/00

--I I

~

'?

~

L--

c,,

"ill C.

I w

a::

(I)

~

a::

a.

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0

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r-....

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j

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c:,,

C.

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PRESSURE (pslg)

\\

\\

\\

I

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i'-...

r

..... r-,....

r-,... i...... -

0

'It 0 ro Q

0 0

Nebraska.Pub)jc_,Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

DBA Containment Pressure Response Mark I Containment Program Figure XIV-6-18 09/19/00

~

N.

' ")I 0

0 fQ i

IL.

0 I

ILi 0::

<(

0::

ILi

0.
e w...

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II,_ -~~--

TEMPERATURE (°F)

N c

~

IL.

0 I

w 0::

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w

0.
e

~

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..J w

3:...

w 3:

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0 0

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

DBA Containment Temperature Response Mark I Containment Program Figure XIV-6-19 09/19/00

l DRYWELL PRESSURE 2 WETWELL PRESSURE 60.r------,------.--

itO.

(.!) -

(fl a..

20.

w a:

en en w

a:

a..

0;2,

o.
2.

LOG CTI HE/SEC) 1 DRYWELL PRESSURE 2 WETWELL PRESSURE 300.i-------1-------1----l i 200.

a:

LI..

(.!)

w 0 --'

w a:

I-a:

a:

w a..

~

w I-

-;2.

0.-----

2, LOGCTIHE/SECl Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Original Short-Term Primary Containment Pressure and Temperature Response Following a Loss of Coolant Accident FigureXIV-6-20 03/27/00

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