ML24159A200
| ML24159A200 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/30/2024 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24159A261 | List:
|
| References | |
| AEP-NRC-2024-20 | |
| Download: ML24159A200 (1) | |
Text
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.2.5-1 Unit: 2
Title:
Variation of Reactivity with Core Temperature at 1050 psla for the End of Life Rodded Core with One Control Rod Assembly Stuck (Assumes Zero Power)
UFSAR Revision 32.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.2.5-2 Unit: 2
Title:
Doppler Power Feedback for Steam Line Break UFSAR Revision 32.0
=i n
- 2.
tc3 5
N m
e P
N ln A
o-RCS PRESSURE (PSIA)
~1II0lJSAN0S)
L ra z
Es-
?l 2
W is-s-
/
7 UFSAR Revision 32.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.2.5-4 Unit: 2
Title:
Steam Line Break DER Inside Containment with Power Nuclear Power and Core Heat Flux Versus Time UFSAR Revision 32.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.2.5-5 Unit: 2
Title:
Steam Line Break DER Inside Containment with Power Core Average Temperature, RCS Pressure, and Pressurizer Water Volume Versus Time UFSAR Revision 32.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.2.5-6 Unit: 2
Title:
Steam Line Break DER Inside Containment with Power Reactivity and Core Boron Concentration Versus Time UFSAR Revision 32.0
- 4.
2 2
w P
N m
I w c.J 04 P
I Z
cn FM1 AN0 CLAO TEHPERATURE (f)
NUCLEAR POWER (f.
- 0.
N.)
L\\ 1 I\\,
111 UFSAR Revision 32.0
I --/
.J
- 3.
.3
- 1.
1.5
- 2.
2.;
- 3.
j.;
4%
Fuel Centerli Fuel Average Clad Average ne
- 0. 1
- 2.
- 4.
- 2.
- 3.
C,
- 5.
- 6.
- 7.
- 6.
- 4.
i00 Figure 14.2.6-2 Rod Ejection Nuclear Power and Fuel and Clad Temperatures Versus Time for Hot Zero Power at Beginning of Life UNIT 2 July 1991 UFSAR Revision 32.0
/
- 3.
J*
IO0 101 102 103 IO' r 1 nc ISCCI figure 14.2.8-1 10 102 103 trnc ISCCl Feedline Break with Power Nuclear Power and Core Heat Flux Versus Time UNIT 2
July 1991 UFSAR Revision 32.0
1600.
100 LO' 102 rrnt 1 SEC 1
102 10 Figure 14.2.8-2 Feedline Break with Power Pressurizer Pressure and Pressurizer Water Volume Versus Time UNIT 2
July 1991 UFSAR Revision 32.0
700.
b80.
boo.
- CIQ, 620.
coo.
500.
SLO.
540.
szo.
500.
10 INTACT COO. -
b40.
b20.
102 trnc IS2Cl IO' Figure 14.2.8-3 Feedline Break with Power Faulted and Non-Faulted Loop Temperatures Versus Time UNIT 2 July 1991 UFSAR Revision 32.0
IbOO.
l 1400.
t 1200.
9 INTACT 1000.
aoo.
LOO.
400.
-9 200.
w1
- 0.
l 10 100 1
I.3 IO Figure 14.2.8-4 Feedline Break with Power Steam Generator Mass and Steam Generator Pressure Versus Time UNIT 2
July 1991 UFSAR Revision 32.0
1.4 I.8 1.
. m
.c
.4
.2
- 0.
100 IO 100 IO' 102 103 IO' TlR@
csttt 14.2.8-5 Feedline Break without Power Nuclear Power and Care Heat Flux Versus lime UNIT 2 July 1991 UFSAR Revision 32.0
PRESSURIZCR Vf-iICR VOLUtlf lCUBlC FCEI)
PRCSSURIZCR PRCSSURE IPSIfkI UFSAR Revision 32.0
bb0.
b40.
420.
LOO.
510.
sea.
520. 1 I
500.
IO0 10' 102 103 10' 700.
INTACT rao.
b40.
b20.
COO.
sao.
560.
540.
c-20.
500.
Figure 14.2.8-7 Feedline Break without Power Faulted and Non-faulted Loop Temperatures Versus Time UNIT 2
UFSAR Revision 32.0
INTACT 5
IbOO.
1400.
1200.
1000.
000.
coo.
400.
ZOO.
- 0.
INTACT 100 101 102 103 IO txne 1sct1 Figure 14.2.8-8 Feedline Break without Power Steam Generator Mass and Steam Generator Pressure Versus Time UNIT 2 July 1991 UFSAR Revision 32.0