ML22340A172

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

ML22340A172
Person / Time
Site:	Cook
Issue date:	11/30/2022
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22340A137	List: AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) ML22340A128 ML22340A129 ML22340A131 ML22340A132 ML22340A133 ML22340A134 ML22340A135 ML22340A136 ML22340A138 ML22340A139 ML22340A141 ML22340A142 ML22340A143 ML22340A144 ML22340A145 ML22340A146 ML22340A147 ML22340A148 ML22340A149 ML22340A150 ML22340A151 ML22340A152 ML22340A153 ML22340A154 ML22340A155 ML22340A156 ML22340A157 ML22340A158 ML22340A159 ML22340A160 ML22340A161 ML22340A162 ML22340A163 ML22340A164 ML22340A165 ML22340A166 ML22340A167 ML22340A168 ML22340A169 ML22340A170 ML22340A171 ML22340A172 ML22340A173 ML22340A174 ML22340A175 ML22340A176 ML22340A177 ML22340A178 ML22340A179 ... further results
References
AEP-NRC-2022-62
Download: ML22340A172 (1)

Text

UFSAR Revision 31.0 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 31.0 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 31.0

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s-

UFSAR Revision 31.0 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 31.0 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:

St e a m Li n e B r e a k DER In s i d e Co n t a i n m e n t w i t h Po w e r Co r e Av e r a g e Te m p e r a t u r e , RCS Pr e s s u r e , a n d Pr e s s u r i z e r Wa t e r V o l u m e V e r s u s Ti m e

UFSAR Revision 31.0 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:

St e a m Li n e B r e a k DER In s i d e Co n t a i n m e n t w i t h Po w e r Re ac t i vi t y an d Cor e B o r o n Co n c e n t r a t i o n V e r s u s Ti m e

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 31.0

UFSAR Revision 31.0 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 31.0

/

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 31.0 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 31.0 700.

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 31.0 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 31.0 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 31.0

UFSAR Revision 31.0 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 31.0 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