Text

0 to Updated Final Safety Analysis Report, Chapter 14.1, Figures 14.1.0-1 to 14.1.12-2 (Unit 2)
	ML21125A488
Person / Time
Site:	Cook
Issue date:	04/19/2021
From:	; Indiana Michigan Power Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML21126A238	List: AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary; ML21125A456; ML21125A457; ML21125A472; ML21125A473; ML21125A475; ML21125A482; ML21125A486; ML21125A487; ML21125A488; ML21125A493; ML21125A498; ML21125A499; ML21125A500; ML21125A501; ML21125A502; ML21125A503; ML21125A505; ML21125A508; ML21125A509; ML21125A510; ML21125A512; ML21125A514; ML21125A517; ML21125A518; ML21125A520; ML21125A521; ML21125A522; ML21125A524; ML21125A525; ML21125A526; ML21125A527; ML21125A529; ML21125A533; ML21125A534; ML21125A535; ML21125A537; ML21125A538; ML21125A539; ML21125A540; ML21125A542; ML21125A543; ML21125A545; ML21125A546; ML21125A547; ML21125A548; ML21125A550; ML21125A554; ML21125A557; ML21125A558; ... further results
References
	AEP-NRC-2021-19
	Download: ML21125A488 (66)
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UNIT 2 Revision: 19.1 Change

Description:

UCR-1719 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.0-1 Sheet 1 of 1

Title:

Doppler Power Coefficient Used In Safety Analyses (where 100% power is 3588 MWt)

UFSAR Revision 30.0

n RCCA POSITION (FRACTION OF NOMINAL)

UFSAR Revision 30.0

s 0.3 N

3 f

0.2 2

0.1 RCCA POSITION (FRACTION VS. NOMINAL) 1 Figure 14.1.0-3 NORMALIZED RCCA REACTIVITY WORTH VS. RCCA POSITION UNIT 2

July, 1993 UFSAR Revision 30.0

3 N

1 0.9 0.8 0.7 0.8 0.1 0.4 0.3 0.2 0.1 0

0 1

2 3

TIME AFTER RCCA DROP BEGINS (SECONDS)

Figure 14.1.0-4 NORMALIZED RCCA REACTIVITY WORTH VS. TIME AFTER RCCA DROP BEGINS I

UNIT 2

July, 1993 UFSAR Revision 30.0

\\

8

\\

45 STEAM GENERATOR

'J

\\

SAFETY VALVES OPEN 2400 PSIA 40 S60 565 570 S7S 580 58s 5%

595 699 695 610 615 626 62S ion Lines

OTAT Protect Thermal Core Figure 14.1.0-s Safety Limits Overtemperature and Overpower AT Protection Core Conditions Transition Cycles Nominal Vessel Average Temperature

= 576'F Nominal Pressurizer Pressure

- 2250 psia UNIT 2

July, 1993 I

UFSAR Revision 30.0

65

?

I \\

\\ \\

\\

\\ \\

/ \\

\\ \\

PaA

\\

1

\\

\\ \\

\\ \\ \\

I/\\, \\ \\

\\ \\

LA

\\

2250

\\ PSIA \\

SAFETY VALVES OPEN 8

'5 589 SOS 690 695 619 615 629 625 654

OTAT Protection Lines Core Thermal Safety Limits Figure 14.1.0-6 Overtemperature and Overpower AT Protection Core Condi'tions:

Full VANTAGE 5 Core Nominal Vessel Average Temperature = 581.3.F Nominal Pressurizer Pressure - 2100 psia.

UNIT 2

July, 1993 I

UFSAR Revision 30.0

UNIT 2 Revision: 18.1 Change

Description:

UCR-1630 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.0-6A Sheet 1 of 1

Title:

Revised Overtemperature and Overpower T Protection Core Conditions: -Full VANTAGE 5 Fuel

-Nominal Vessel Average Temperature = 581.3°F

-Nominal Pressurizer Pressure = 2100 psia (see section 14.1.0.6-1 for discussion)

UFSAR Revision 30.0

101 figure 14.1.0-7 100 101 102 TIME AFTER SHUTDOWN (SECONDS) 1979 ANS Residual Decay Heat Used In Accident Analyses UNIT 2

July, 1993 UFSAR Revision 30.0

Unit 2 Revision: 18 Change

Description:

UCR-1611 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.1-1 Sheet 1 of 1

Title:

Rod Withdrawal from Subcritical Nuclear Power and Heat Flux Versus Time UFSAR Revision 30.0

Unit 2 Revision: 18 Change

Description:

UCR-1611 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.1-2 Sheet 1 of 1

Title:

Rod Withdrawal from Subcritical Fuel Average and Clad Temperatures Versus Time UFSAR Revision 30.0

0.

i 0

2 4

.6 a

10 12 14 16

a 2 0 TIrnE ISECI Figure 14.1.26-l Rod Withdrawal at Power Nuclear Power Versus Time for Full Power, 80 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UNIT 2

July 1991 UFSAR Revision 30.0

C Fi t3 hl 0

nl L

Q

-(CD ii P

ifl l-l c

fu L

ii Q) nJ 0

PRESSURIZER WlER VOLIJHf IF 131 L

l-u al 0

iii L

u In 0

0 0

0 c-2 0

0 PRE SSlJR I Zf R PRf SSWf I IS I II I 0

0 0

3 0

0 0

0 UFSAR Revision 30.0

600 560

4.

3.5

3.

2.S

2.

I.5 0

2 4

b 8

10 12

4 lb

3 20

1. *,

I 0

2 4

b.

a 10 12 14 16 18 20 TIN ISECI figure 14.1.28-3 Rod Withdrawal at Power Core Average Temperature and ONBR Versus Time for Full

Power, 80 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UNIT 2

July 1991 UFSAR Revision 30.0

1 0

2s so. 7S 100 12s IS0 17s 200 225 250 275 300 325 350 375 400 TIflE 1 SEC 1 figure 14.1.26-4 Rod Withdrawal at Power Nuclear Power Versus Time for Full Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UiJIT 2

July 1991 UFSAR Revision 30.0

1800. J

/

0.

so.

100.

lS0.

200.

250.

300.

350.

400.

2000.

1800.

600.

1400.

1200.

1000.

800.

l C

0.

so.

100.

150.

LOO.

tso.

300.

350.

400.

TIM cSEc)

Figure 14.1.28-5 Rod Withdrawal at Power Pressurizer Pressure and Water Volume Versus Time for Full Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UNIT 2

July 1991 UFSAR Revision 30.0

Figure 660 640 600 0

2s so 75 100 125 IS0 17s 200 225 2;O 27s 300 325 350 375 400

4.

3.5

3.

2.s

2.

I.5

1.

J 0

2s so 75 100 12s 150 175 200 22S 250 27s 300 325 350 37s 400 rIna (SEC) 14.1.28-6 Rod Withdrawal at Power Core Average Temperature and ONBR Versus Time for Full

Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UNIT 2

July 1991 UFSAR Revision 30.0

m--

r-

)--..-.-

.-e-e-I 1L /

CQ 4-ca cl d

oc I\\.-

a

---.-e--w----

--+q+y.--

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m-e I

[

I

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e--B f

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~

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r 1

\\

f T

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a..

. r.-.

r

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5 6

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,..m.:

1*.

1.-

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a I

L I

i m--w a-m (v

CI 0

m aD UFSAR Revision 30.0

T66~

Am 2 LINn m

0 b

io b

c h,

W i

1::::

/

..f I..:

-.m

.---_--me m

I L

m--

WV z

- I

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=

i\\

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s::

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m

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_a UFSAR Revision 30.0

- I _

7

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a--*.-

a m--

i ao

.+--

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f

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L b

=-

I*-

t:z.:

/

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I... --.

I I

i UNIT 2

July 1991 UFSAR Revision 30.0

1.2000 L 1.2000 L i i 8 8 g

~80000 l

g

~80000 l

i 70000

9.

60000 t

60000 +

i 70000 t

Figure 14.1.3-1 Dropped RCCA(s)

Nuclear Power and Core Heat Flux Versus Time for a Typical Response in Automatic,Control UNIT 2

July 1991 UFSAR Revision 30.0

ii

+

t 550.0 l

9 Y

9 I

530.0 l

w Y

s l

510.0 l

L 1900.0 s

i 1800.0 l.

1700.0 -9 4

c Q

8 4

8 r!

?

0 d

si s,

e g

ie s

nnt csatt Figure 14.1.3-2 Dropped RCCA(s)

Average Coolant Temperature and Pressurizer Pressure Versus Time for a Typical Response in Automatic Control I

UNIT 2

July 1991 UFSAR Revision 30.0

0 1

L 3

4 6

6 7

a 9

10 TIflE

[SEC 1

figure 14.1.6-l Complete Loss of Flow Core Flow Coastdown Versus Time UNIT 2

July 1991 UFSAR Revision 30.0

.8

.b

.4

.2

0.

2640.

2500.

2400.

2300.

2200.

2100.

2000.

1900.

1800.

0.

1.

2.

8.

0 1

2 3

4 5

b 7

8 9

10

4.

TlnL

6.

b.

(SEC1

7.

8.

9.

10.

Figure 14.1.6-2 Complete Loss of Flow Nuclear Power and Pressurizer'Pressure Versus Time UNIT 2

July 1991 UFSAR Revision 30.0

HOT CHANNEL ttEAT FLUX (FRAC OF NOMINAL) b-L 0

L l

OD z

b AVERAGE CHANNEL ttEAT FLUX (FRAC OF NOMINAI. )

0 kJ A

Q Iu UFSAR Revision 30.0

1.6 1.4 2.0 2.6.

1.8 0

1 2

3 4

5 6

7 8

9 10 TIME (SEC) figure 14.1.6-4 Complete Loss of Flow DNER Versus Time UNIT 2

July 199i UFSAR Revision 30.0

A.4 1.2

1.

.e

.6

.4

.2

0.

0 1

2 3

4 6

6 7

8 9

10 1.4 1.2

1.

.8

.6

-4

.2

0.

0 1

2 8

4 s

6 7

0 9

10 TIllE (SEC) figure 14.1.6-5 Partial Loss of Flow l/4 Faulted Loop and Core Flows Versus Time UNIT 2

July 1991 UFSAR Revision 30.0

3 P

0.

0 1

f 3

4 5

4 1

8 9

2bOO.

2500.

2400.

2300.

2200.

2100.

2000.

1900.

1.00.

L a

0.

r

1.

g.

3.

4.

5.

6.

7.

a.

9.

10.

TIM fSCCl 1

10 Figure 14.1.6-6 Partial Loss of Flow l/4 Nuclear Power and Pressurizer Pressure Versus Time UNIT 2

July 1991 UFSAR Revision 30.0

1.4 1.2 I.

l 8

b l 4

.2

0.

1.4 I.2

1.

.I

.b l 4

.2

8.

c Figure 14.1.6-7 Partial Loss of Flow I/4 Average Channel and Hot Channel Heat Flux Versus Time UNIT 2

July 1991 UFSAR Revision 30.0

5.0 4.5 4.0 3.5 a

s a

3.0 2.5 2.0 1.5 \\

0 I

2 3

b 5

5 7

8 9

10 TIME (SEC)

Figure 14.1.6-8 Partial Loss of Flow l/4 DNBR Versus Time UHIT 2

July 1991 UFSAR Revision 30.0

UNIT 2 Revision: 18.1 Change

Description:

UCR-1630 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.6-9 Sheet 1 of 1

Title:

Total Core Flow and Faulted Loop Flow vs. Time For The Locked Rotor Event UFSAR Revision 30.0

UNIT 2 Revision: 18.1 Change

Description:

UCR-1630 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.6-10 Sheet 1 of 1

Title:

Nuclear Power and RCS Pressure vs. Time For The Locked Rotor Event UFSAR Revision 30.0

.. G

~-----y

\\,

I

.3

5.

Figure 14.1.6-11 l/4 Locked Rotor Average Channel and Hot Channel Heat Flux Versus Time UNIT 2

Julv 1991 UFSAR Revision 30.0

ii?O.

T

/

I

,.f

tsi.

7 j ii

300.

-. i SOO.

Core Average and Loop 1 Temperature vs. Time For Loss of Load, Maximum Reactivity Feedback Without Pressurizer Spray and PORVs UFSAR Revision 30.0

I i

! I

.6 i

.A :

I

.2 j I

a.

.6 Figure 14.1.9-1 Loss of Normal Feedwater Nuclear Power and Core Heat Flux Versus Time UNIT 2

July, 1992 UFSAR Revision 30.0

UNIT 2 Revision: 20.2 Change

Description:

UCR-1815 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.9-2 Sheet 1 of 1

Title:

Loss of Normal Feedwater Loop Temperature Versus Time UFSAR Revision 30.0

tQ cbl w

4 x

l-l-W h,

rl l-l ii CM w

L w

cd w

W fu w

w w

UFSAR Revision 30.0

20 40 60 80 100 120 140 160 180 i

TIME (SEC) 540-p 520-u

=o 4

20 40 60 80 100 120 140 160 180 TIME (SEC)

L UNIT 2

DONALD C. COOK NUCLEAR PLANT UNIT ~(FULLVSCORE)

NUCLEAR POWER TFMNSIENT Kc CORE AVERAGE TEMPERATURE vs. TLME FOR THE SINOLE LOOP FEEDWATER MALFUNCIION WlTH AUTOMATIC ROD CONTROL AT FULL POWER Figure 14.l.lOB-1

July, 1993 UFSAR Revision 30.0

2700.

z 2600.

n 2500.

2 g

2400.

t z

n 2300.

I2 I

z 2200.

iz z

2100.'

E I

2000.

1900.

I 1800.1

0.

20.

40.

60.

80.

100.

120.

140.

160.

180.

21 TIME (SEC)

5.

4.5

4.

3.5 fs B

3.

2.5

2.

1.5

1.

, a-c 0

zo 40 60 80 100 120 140 180 160 i

TIME (SEC)

UNIT 2

DONALDC.COOK NUCLEARPLANT UNIT 2(FULL vs CORE)

PRESSURIZER PRESSURE k

DNBR

8. TIME FOR THE SINGLE LOOP FEEDWATER MALFUNCTION WlTH AUTOMATIC ROD CONTROL AT FULL POWER Figure 14.1. IOB-2

July, 1993 UFSAR Revision 30.0

680 680 G:

040 3

620 a

000 h e 520 t 500 0 20 40 60 80 100 120 140 160 160 2

TIME (SEC)

UNIT 2

DONALD C. COOK NUCLEAR PLANT UNIT 2(FULL v5 CORE)

NUCLEAR POWER

?RANSIENT

& CORE AVERAGE TEMPERATURE va. TIME FOR THE SINGLE LOOP FEEDWATER MALFUNCTION WITH MANUAL ROD CONTROL AT FULL POWER Figure 14.l.lOB-3

July, 1993 UFSAR Revision 30.0

2 2600.

h t

2500.-

2400.

2300.'.

2200.

21oo.q 2000.-

lQOO.*-

1800.

l

0.

20.

40.

60.

80.

100.

120.

140.

160.

180.

2 TIYE (SEC)

5.

1.4 0

20 40 60 80 100 120 140 180 180 2

TIME (SW UNIT 2

DONALD C. COOK NUCLEAR PLANT UNIT ~(FULLVSCORE)

PRESSURIZER PRESSURE

& DNBR VI. TIME FOR THE SINGLE LOOP FEEDWATER MALFUNCTION WITH MANUAL ROD CONTROL AT FULL WWER Figure 14.l.lOB-4

July, 1993 UFSAR Revision 30.0

1.4 1.2

1.

.a

.6

.4

.t

0.

0 20 40 60 80 100 120 140 160 700 660 660 640 620 600 580 560 540 520 500 u

60 10 100 120 TIRE (SEC) 140 160 110 200 DONALD C. COOK NUCLEAR PLANT UN-IT ~(FULL vs CORE)

NUCLEAR POWER TRANSIENT

& CORE AVERAGE TEMPERATURE VI. TIME FOR THE MULTI-LOOP FEEDWATEX MALFUNCTION WITH AUTOMATIC ROD CONTROL AT FULL POWER

, Figure 14.1.10B-5 UNIT 2

July, 1993 UFSAR Revision 30.0

2700.

2600.

2500.

2400.

2300.

2200.

2100.

2000.

1900.

1100, 1700.

5.

4.5

4.

3.5 2.5

20.

40.

60.

10.

100.

120.

140.

160.

110.

200.

TIWE (SEC) 0 20 40 60 10 100 120 140 160 110 200 TIM (SEC)

DONALDC.COOK NUCLEARPLANT UNIT ~~ULLVXORE)

PRESSURIZER PRESSURE

& DNBR VL. TIME FOR THE MULTI-LOOP FEEDWATER MALFUNCI-ION W-ITH AUTOMATIC ROD CONTROL AT FULL FOWER Figure 14.l.lOB-6 UNIT 2

July, 1993 UFSAR Revision 30.0

.b

.c

.2

0.

700 610 660 640 620 600 510 560 540 520 500 0

20 40 60 10 100 120 140 160 TIHE

'SEC) 0 LO 40 60 10 100 120 TIHE (SEC) 110 160 110 200 DONALD C. COOK NUCLEAR PLANT UNIT ~(FULLVSCORE)

NUCLEARPOWERTRANSIENT&CORE AVERAGETEh4PERATUREv~.TIMEFOR THEMULTI-LOOPFEEDWATER MALFUNCTIONWITHMANUALROD CONTROLATFULLPOWER Figure 14.1. IOB-7 UNIT 2

July, 1993 UFSAR Revision 30.0

2700.

2600.

zsoo.

2400.

2300.

2200.

2100.

2000.

1900.

1100.

1700.

5.

4.5

4.

3.5

0.

20.

40.

60.

80.

100.

120.

140.

160.

1ao.

200.

TIRE (SEC) 0 20 40 60 10 100 120 140 160 110 200 TIRE (SEC)

UNIT 2

July, 1993 DONALD C. COOK NUCLEAR PLANT UNIT SKULL vs CORE)

PRESSURIZER PRESSURE

& DNBR vs. TIME FOR THE MULTI-LOOP FEEDWATER MALFUNCI7ON WTH MANUAL ROD CONTROL AT FULL POWER Figure 14.1. IOB-8 1

UFSAR Revision 30.0

0 20 40 bO 80 100 120 140 1 CO 180 200 226 240 2bO 280 300 17fO.

1500.

I 12SO 1000.

750.

500.

aso.

azso.

A-2000.

+

i I

6

0.

t LOO.

0.

40.

80.

120.

1 co.

TlnE (SEC1 Figure 14.1.118-l Excessive Load Increase Nuclear Power and Pressurizer Minimum Reactivity Feedback w

Pressure ith Manua 1 240.

280.

Versus Time for Rod Control UNIT 2

July 1991 UFSAR Revision 30.0

so0 0

20 40 co a0 100

20 I40 I bO 180.

200 220 240 zb0 290 300 3.2.

3.

a.

- i i

s.;

0 -

2.b i

2.4 5

0 2.2 0

u

2.

3 u d 1.8 0

l.b 1.4 1.2

1.

C I

0 20 40 co 80 100 120

.I40 I co 180 200 220 240 Lb0 280 300 rlnc I SEC 1

Figure 14.1.118-2 Excessive Load Increase Core Average Temperature and ONBR Versus Time for Minimum Reactivity Feedback with Manual Rod Control UNIT 2 July 1991 UFSAR Revision 30.0

I. 4 F

r t

J.

0 20 40 bo 80 100 120 I40 I CO 180 200 220 240 2bO 2ao 300 tsoo.

czso. *-

I 3000.

1750.

1 1500.

LZSO.

1000.

7s 0..

SOO.

214-a

0. J 4

0.

40.

80.

120.

1 b0.

200.

240.

280.

TIRE (SEC1 Figure 14.1.118-3 Excessive Load Increase Nuclear Power and Pressurizer Versus Time for Maximum Reactivity feedback with Manual Control UNIT 2 July 1991 UFSAR Revision 30.0

0 20 40 LO 80 100 120 140 lb0 I80 200 220 240 260 280 300

1.

J 0

20 40 LO 80 100 120 140 lb.

18@

200 220 240 2bO 280 300 ttnc ISlCl Figure 14.1.118-4 Excessive Load Increase Core Average Temperature and ONBR Versus Time for Maximum Reactivity Feedback with Manual Control I

UNIT 2

July 1991 UFSAR Revision 30.0

2000.

+

IfSO.

LSOO.

1250.

1000.

tso.

500.

tso.

0.

I

0.

40.

80.

120.

1bO.

200.

240.

280.

trn2 I stc I

Figure 14.1.11B-5 Excessive Load Increase Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback with Automatic Rod Control UNIT 2

July 1991 UFSAR Revision 30.0

se0 LfO IL0 550 s40 530 520 510 500 2.L 2.4 2.2

2.

1.8 1. L 1.4 1.2

1.

0 20 40 co 80 100 f20 140 lb0 180 200 22c 240 260 280 300 0

20 48 co 80 100 120 148 lb0 18k 108 221 24I 2bO 2so

30) rlnc I see I

14.1.118-6 Excessive Load Increase Core Average Temperature and DNBR Versus Time for Minimum Reactivity Feedback with Automatic Rod Control UNIT 2

July 1991 I

UFSAR Revision 30.0

.b

.4

. 2

a.

!OOO*

17SO.

1500.

izso.

1000.

7so.

soo.

aso.

0.

0 20 40 b0 80 100 I20 I40 lb0 180 200 22'J 240 260 280 300

0.

40.

00.

120.

1 b0.

200.

240.

2IO.

TIRC I SEC I Figure 14.1.116-7 Excessive Load Increase Nuclear Power and Pressurizer Pressure Versus Time for Maximum Reactivity Feedback with Automatic Rod Control UNIT 2 July 1991 UFSAR Revision 30.0

sea c

570 SbO 550 s40 s30 520 510 SO0 i

0 20 40 LO 80 100 I20 140 I60 180 200 220 240 are 280 300 3.2 y

3.

3.3 i i

2.b 2.4 0

20 40 b0 a0 IO0

.t@

140 160 1.0 200 220 240 2bO 200 300 tint 1 stc I

Figure 14.1.118-8 Excessive Load Increase Core Average Temperature and ONBR Versus Time for Maximum Reactivity feedback with Automatic Rod Control UNIT 2

July 1991 UFSAR Revision 30.0

UNIT 2 Revision: 20.2 Change

Description:

UCR-1815 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.12-1 Sheet 1 of 1

Title:

Loss of Offsite Power to the Station Auxiliaries Nuclear Power and Core Flow Versus Time UFSAR Revision 30.0

rzo.

I

@DO. :

I THOT Figure 14.1.12-2 Loss of Offsite Power to the Station Auxiliaries Loop Temperature and Pressurizer Water Volume Versus Time UNIT 2

July, 1992 UFSAR Revision 30.0

ML21125A488

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