ML21125A546

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0 to Updated Final Safety Analysis Report, Chapter 14.2, Figures 14.2.5-1 to 14.2.8-8 (Unit 2)
ML21125A546
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: ML21125A546 (16)


Text

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1 UFSAR Figure: 14.2.5-1 Unit: 2

Title:

V ariation of R eactiv ity with C ore T emperatu re at 1 0 5 0 ps la for th e E nd of Life R odded C ore with O ne C ontrol R od A s s embly Stu ck ( A s s u mes Z ero Power)

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1 UFSAR Figure: 14.2.5-2 Unit: 2

Title:

Doppler Power Feedback for Steam Line Break

n RCS PRESSURE (PSIA) 2.

=i tc3 ~1II0lJSAN0S)

5 m

N e

P

. o-N ln A

7 Lra Es-z

?l 2

W

/

--UFSAR Revision 30.0

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s-

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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 30.0 INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1 UFSAR Figure: 14.2.5-5 Unit: 2

Title:

Steam Line Break DER Inside Containment with Power Core Averag e Temp erature, RCS Pressure, and Pressuriz er Water Vol ume Versus Time

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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

4.

2 FM1 AN0 CLAO TEHPERATURE (f) 2 NUCLEAR POWER (f. 0. N.)

w I\ ,

P L\ 1

. . . 111 N c.J m

I w

04 P

I Z cn UFSAR Revision 30.0

UFSAR Revision 30.0 I.J --/

.3 1. 1.5 2. 2.; 3. j.; 4%

3.

Fuel Centerli ne Fuel Average Clad Average

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 July 1991 UNIT 2

UFSAR Revision 30.0

/

3. J*

IO0 101 102 103 IO' r 1 nc ISCCI 10 102 103 trnc ISCCl figure 14.2.8-1 Feedline Break with Power Nuclear Power and Core Heat Flux Versus Time UNIT 2 July 1991

UFSAR Revision 30.0 1600.

100 LO' 102 102 10 rrnt 1 SEC 1 Figure 14.2.8-2 Feedline Break with Power Pressurizer Pressure and Pressurizer Water Volume Versus Time UNIT 2 July 1991

UFSAR Revision 30.0 700.

b80.

boo. t TSAT CIQ, THOT 620.

coo.

500.

SLO.

540.

szo.

500. I 100 IO' 102 103 10 INTACT COO. -

b40.

b20.

102 IO' trnc IS2Cl Figure 14.2.8-3 Feedline Break with Power Faulted and Non-Faulted Loop Temperatures Versus Time UNIT 2 July 1991

UFSAR Revision 30.0 IbOO. l 1400.

t 1200. 9 INTACT 1000. --

aoo.

LOO. *-

400. -9 200. .

w1

0. l 100 1 10 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 30.0 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

PRESSURIZCR Vf-iICR VOLUtlf lCUBlC FCEI) PRCSSURIZCR PRCSSURE IPSIfkI UFSAR Revision 30.0

UFSAR Revision 30.0 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 30.0 INTACT 5 IbOO.

1400.

1200. INTACT 1000.

000.

coo.

400.

ZOO.

0.

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