ML21125A525

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0 to Updated Final Safety Analysis Report, Chapter 14.2, Figures 14.2.5-1 to 14.2.7-6 (Unit 1)
ML21125A525
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/19/2021
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21126A238 List: ... further results
References
AEP-NRC-2021-19
Download: ML21125A525 (21)
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Text

Revision: 23 Change

Description:

UCR-1969 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.2.5-1 Sheet 1 of 1

Title:

Variation of Reactivity with Core Temperature at 1050 psia for the End of Life Rodded Core with One Control Rod Assembly Stuck (Zero Power) for the Steamline Break Double Ended Rupture Event UFSAR Revision 30.0 1.04D 1.030 1.-(}20 Q

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Revision: 23 Change

Description:

UCR-1969 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.2.5-2 Sheet 1 of 1

Title:

Doppler Power Feedback for the Steamline Break Double Ended Rupture Event UFSAR Revision 30.0

.-. ~w------------------------~

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5 10 15 20 25 30 J5 Core Power [% of nominal]

45 5D

UFSAR Revision 30.0 2,400..-------------------------.

2,000

.!!! a 1.600 e

~ 1,200

~

a.

~ 800 cc 400 *

  • 0 ------------------------------____,j 10 15 20 25 30 35 40 45 50 0

5 Cold Leg Safety Injection [lbm/sec]

DONALD C. COOK NUCLEAR PLANT UNITl FIGURE 14.2.5*3 Safety Injection Flow Supplied By One Charging Pump For Toe Steamline Break Double Ended Rupture Event JULY 1997

Revision: 23 Change

Description:

UCR-1969 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.2.5-4 Sheet 1 of 1

Title:

Nuclear Power and Core Heat Flux vs. Time for the Steamline Break Double Ended Rupture Event

[Downstream of the Flow Restrictor with Offsite Power Available]

UFSAR Revision 30.0

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200 250 300

Revision: 23 Change

Description:

UCR-1969 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.2.5-5 Sheet 1 of 1

Title:

Core Average Temperature and RCS Pressure vs. Time for the Steamline Break Double Ended Rupture Event

[Downstream of the Flow Restrictor with Offsite Power Available]

UFSAR Revision 30.0 500....--------- ---------------~

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50 100 150 Time [s]

200 250

Revision: 23 Change

Description:

UCR-1969 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.2.5-6 Sheet 1 of 1

Title:

Pressurizer Water Volume vs. Time for the Steamline Break Double Ended Rupture Event

[Downstream of the Flow Restrictor with Offsite Power Available]

UFSAR Revision 30.0 "l,.....

ll

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<to

e::::

-1000

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50 HlO 150 Time [s]

200 250 300

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:

14 Sheet:

1 of 1 UFSAR Figure: 14.2.5-8 Change

Description:

UCR-2054, Rev. 0 Unit 1

Title:

Nuclear Power and Core Heat Flux vs Time for the Rupture of a Steam Pipe from Hot Full Power Event -

(0.89 ft2 Break, Largest Break Size to Trip on OPT)

UFSAR Revision 30.0 UFSAR Revision 30.0 INDIANA MICHIGAN j

POWER.

An AEP Company u C I ~ Cr po r, e r u

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INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:

14 Sheet:

1 of 1 UFSAR Figure: 14.2.5-9 Change

Description:

UCR-2054, Rev. 0 Unit 1

Title:

Pressurizer Pressure and Mixture Volume vs Time for the Rupture of a Steam Pipe from Hot Full Power Event - (0.89 ft2 Break, Largest Break Size to Trip on OPT)

UFSAR Revision 30.0 UFSAR Revision 30.0 INDIANA MICHIGAN j POWER.

An AEP Company Pr es riz t pr

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INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:

14 Sheet:

1 of 1 UFSAR Figure: 14.2.5-10 Change

Description:

UCR-2054, Rev. 0 Unit 1

Title:

Vessel Inlet Temperature and SG Pressure vs Time for the Rupture of a Steam Pipe from Hot Full Power Event - (0.89 ft2 Break, Largest Break Size to Trip on OPT)

UFSAR Revision 30.0 UFSAR Revision 30.0 I

INDIANA MICHIGAN j POWER" An AIP Company r u l t ed l oo I n o, t loo p s 545...-------------------------.

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INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:

14 Sheet:

1 of 1 UFSAR Figure: 14.2.5-11 Change

Description:

UCR-2054, Rev. 0 Unit 1

Title:

Loop Steam Flow and T Signal vs Time for the Rupture of a Steam Pipe from Hot Full Power Event -

(0.89 ft2 Break, Largest Break Size to Trip on OPT)

UFSAR Revision 30.0 UFSAR Revision 30.0 INDIANA MICHIGAN j POWER.

An AEP Company r u lt ed l oo s1 e om l o*

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DONALD C. COOK NUCLEAR PLANT UNITl FIGURE 14.2.6-1 Nuclear Power vs.Tune For The Rod Ejection Event.

Hot Zero Power, End Of Life JULY 1997

UFSAR Revision 30.0 4000 u:

! 3000 i

L~

"O Ill 0 I 1000

~

LL 0

0 2

4 Fuel Centerline 6

Time [s]

8 10 DONALD C. COOK NUCLEAR PLANT UNrrl AGURE l~.2.6-2 Fuel Centerline, Fuel Average, and Cad Outer Surface Temperature vs.Tune For The Rod Ejection EYeDt. Hot aro Power. End Of Life JULY 1997

UFSAR Revision 30.0 1i

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  • 0 a....

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DONALD C. COOK NUCLEAR PLANT UNITI FIGURE 14.2.6--3 Nuclear Power vs.Tune For The Rod Ejection Event.

Hot Full Power, End Of Life JULY 1997

UFSAR Revision 30.0 6000 U::- 5000 L

Q)...

I 'i 4000 Looo 0 I 2000 l 1000 u..

0 0

2 Fuel Centerline 4

6 T1rne [s) 8 lO DONALD C. COOi:

NUO EAR PLANT UNITl FIGURE 14.2.6-4 Fuel~, Fuel Avenge. and Clad Outer Surface T~

vs.Tune For The Rod Ejection Evmt. Hot Full Power. End Of Life JULY 1997

UFSAR Revision 30.0 UNIT 1 Cycle 8 FIGURE 14.2.7-1 ANt-.1.lAL 01'c'.N\\1';oNAL Tll'(l:O)fJ f'JOSES Al' SITE llOllNOARY l! DEFECTIVE l'IJt:1.

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UFSAR Revision 30.0 UNI7 1 Cycle 8 i:i " '

FlGURE 14.2.7-2 ANNt:1.::.. 0PS?..i\\:;o:1AL, '*1l0LE AT sr:c: I\\OL'~:lAR~

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UFSAR Revision 30.0

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GPM July, 1982

UFSAR Revision 30.0

=IGURE 14.2.7-6 LOSS OF A.C. !'O\\."ER TD T!!i: ?LA.. 'IT At:X:LlARii::S fil

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