ML21125A456

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0 to Updated Final Safety Analysis Report, Chapter 3, Figures (Unit 1)
ML21125A456
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: ML21125A456 (50)
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Text

CORE BAFFLE -1 I

THERMAL SHIELD THERMAL SHIELD REACTORVESSEL REACTORVESSEL FUEL ASSEMBLY FUEL ASSEMBLY I93FUELASSEMBLlES CORE Ci?3SS SECJ-!<I?;

Figure 3.2.1-l

July, 1982

lHSTRUWE!4TATlOH PORTS UPPER SUPPORT ASSEMBLY OLD-DOWN SPRIHG CORE EfiRrtEL --"

l!PPE::

SUPPORT COLI!H&-'

OUTLET ROZZLE -A UPi'ER CORE PLATE---

IRRADIATIOH I.

'"--CONTROL RDD CLUSTER(Wl?tiDRA~:~

REACTOR VESSEL-

-FUEL ASSEHBL'IX

,.--LOVER CDRE PLATE RADIAL SUPP(qjT----,

THIMBLE GUIDES Reactor Vessel and Internals Figure 3.2.1-2

July, 1982

2 3

4 5

6 7

90" 8

9 10 11 12 13 1.4 i5 PNMLKJHGFEDCBA 180" I

ENRICHMENTS FUEL

~,flhl>T::~

,~FtRh:;f-~,:,:i,:ij Figure 3.2.1-3

July, 1982

COHTRDL ROD ASSEMBLY ROD ABSORBER TOP NOZZLE FUEL ROD GRID ASSEMBLY ABSOliREK ROD GUI DE SHEATHS GRID ASSEMBLY DASH POT REGION BOl-lWi NOZZLE TYPICAJ, ROD CLUSICX Ci)?!m:OL ASSEXBLY Figure 3.2.1-4

July, 1982

UNIT 1 Revision: 19.1 Change

Description:

UCR-1727 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2.1-5 Sheet 1 of 1

Title:

D. C. Cook Unit 1 Core Barrel Assembly

UNIT 1 Revision: 19.1 Change

Description:

UCR-1727 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2.1-6 Sheet 1 of 1

Title:

Upper Core Support Structure

B c

e c

r-I i_..

I

.-^...-

I

c.
July, 1982

I

- I I

FUEL ASSmSLY OVFLINE Figure 3.2.1-g

.TIB~V.

19fl2

/m I I li

=

I I II I-----,--

l--------

I----

L 3

.. -. )

c c.

0

BF3 l8Oo 90" 270" 0"

BF3 Bur1ubl.e PoFson (I 3)

Secordary Source (4)

Figure 3.2.1-11

July, 1982

g :

I I

I i

July, 1982 Figure 3.2.1-12

UNIT 1 Revision: 21 Change

Description:

UCR-1812, Rev. 1 UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2.1-13 Sheet 1 of 1

Title:

Control Rod Drive Mechanism Assembly

I

\\

i r!

I--:

I-.-

r-'---

LIFT COIL GUIDK TUBE VOVABLE GRIPPER POLE MOVABLE GRIPPER COIL MOVABLE LATCH SUPPORT TURI-

-MOVABLE LATCli LOCK PLlIKGER MOVABLE GRtPPER LAYCHfS STATIONARY GHIFPER POLE STATIONARY GRiPPER COIL PLUNGER HALF

,- 0.485" DIA Unit 1 Figure 3.2.1-15 Thimble Plug Assembly July 1996

Abaot'ber !'la Ag-In-Cd I

p teria.l:

D SC D

SA s,

SC SD A

I C

D PL SP N

H L

K J

C s...

D C

A SB SB SA B

A SP SP s,.,

so C

SI SA SP SP IS C

D SB s,

SP SP so C

A S?

SA S1' SA I

C A

SB s,

D SC o*

CONTIOL ROD PATTERN (UHIT 1}

(apare rod locations)

FIGURE 3.3.1-1 E

D C

8 A

I I

!)

A C

SA SP A

SD I I 0

83 SP SH I C

B SC s,.

SB SD D

I I

SP A

s,.

A i)

Nulllber of Rod Cl:..sters 8

8 4

4 a

4 8

9 0

82 12 July, 1982

l.116 1.023 1.099

1. 07.8 l.217 1.220 1.on 0.7:36 1.094 0.964 1.138 l.087 l.205 l.016 0.833 l.119 1.063 l.142 l.1S6
o. 978 l.197 1.168 1.108 O.SS9 1.057 l.009 o.asa
o. 710 0.611 V

AP - i.sSE'1BLY POWER l.01S 0.487 FiguM! 3..3.1-2 CYCLE l ASSEMBLYWISE WOWER (BOL)

Ju.ly, 1984

1.175 1.215 1.159 1.187 1.125 1.153 0.968 1.162 I

1 1.158 I

1.144 1

1.138 I

1.181

.l. 174 I

1.119 I

1.082 1.161 1.000 0.9f6 0.964 0.817 0.781 0.677 1.126 1.102 1.203 1.047 0.951 0.576 I

- ASSFfBLY POWER Fiqure 3.3.1-3 CYCLE 1 ASSMBLYWTSE POWER (MOL)

July, 1984

I 1.163 1.088 1.171 1.079 1.162 1.093 1.066 1.lu

/

1.o74

/

1.153 1.144 1.047 1.147 1.036 0.969 7qTqzl-I k

0.773 0.600 0.809 1

0.732 1.213

-1 1.051 I

1.028 0.855 0.557 AP

/

AP - ASSMBLY POWER Figure 3.3.1-4 CYCLE 1 ASSE~BLYWISE POWE?, (XL)

JOY, 1984

9 9

9 t

8 12 20 20 12 8

8 20 12 12 12 20 a

20 20 16 16 20 20 I

I lul I20 I

I 20 I II6 I I 20 I I 7n l I 121 I

a I IJ I l A

I.e I.L I --

IJ I-1 T

AL I LU I

IL0 A0 20 I

LL I

Y 20 16 16 16 16 16 I

I 20 1

9 12 16 16 16 16 12 9,

20 I Lb 16 16 I 16 16 I 20 I

9 12 20 16 16 20 12 9

L 12 20 20 16 20 20 12 I

20 20 16 16 29 I

20 I

8 20 l2 l2 l2 20 8

8 I

l2 I

to 20 12 I I

a I

9 9

9 Dlstribucioa of Eurnable Poise Rob liuder of 8. P. Rods per k8oPbly (1436 toeal)

Unit

1.

Cycle 1

figure 3.3.1-11 July.

1984

I I

1 t

L6 Rods Cot8 Ceat8r

,p Az%zqement of Burnable Poison Roda withfn an kmably Unit 1,

Cycle 1

Figure 3.3.1-12

-1.0 s-.-&,4

..~..........

+y:c-

~-::*.. (

1;: A...:

~~..,.

_.._.. L

,_.._... ::.i: f-1 Figure 3.3.1-13 JULY, 1984

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0

.+

T-4---.-

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1

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i_, i.I;::'.i

-ii-. -.,.. i.T,.-

J?A 1

L.I PPP PPm 100 200 300 MO0 500

,600 BOL, ALL WNTROL RODS IX5~15 Figure 3.3.1~-14 JULY, 1984

-1.0

-2.0

-3.0 E

. N 2

T

-4.0 0

S II (I u 3

-5.0 d

-6.0

-7.0

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T 1

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+

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)

i 200 300 400 500 600 HOD~R TEQEUTURE

\\(P)

July, 1984

~:j--~~j 1

1.
,,.:y

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-TV i..

. i Ffgure 3.3.1-16

July, 1984

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w..----.

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+,

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50 Percent Full Power Loo I

Figure 3.3.1-17:

Doppler Contributions to the Power

July, 1992 Coefficient vs.

Power Level UNIT 1

c.37 0.06 0.05 0.01) 0.03 0.02 0.01 LfGE)tD:

'PfRXKT ThfOCiTICA!.

OEXS!

?Y

\\

n GYLLAKDER 96.4 0

c A

gj AStdOTO 95.0 Q

f-J&

0 MDFREY 93.4 0

A STORA 92.2 e

0 A.C.

S!l.sH 34.4 8

ASMOTO 91.0 1l v

KRiJOER 93.7 v

i SEi REFERENCES FOR PCRCEkl THEOR'TtCAL DEWSllY I !

k0wA~D b

GuLvIN LUCKS DEE!,!

DANIEL El AL FflTH VOGT ET AL NlSHIJl\\!A WHEELER b

AIHSCOUGH THEIHAL-tiYCRAULIC SECTION

27 26 25 24 23 22 21 20 19 18 17 16 15 14 13 12 I I IO 9

8 7

(16) T SAXTOH OVER-POWER TEST a

(2)

L SAXTON Pu0yU02 EXTENDED BURNUP TESTS n

n 7170 7171 (50)

(50) 7 ASSEMBLIES POWER ESCALATION 2, l INTEsNTION-LLY.

DEFECTED)

LEGEND:

PRESSURIZED RODS ARE IHCiU DED IN THESE ASSEMBLIES (X)

NO.

OF RODS a

CVTR IRRADIATION PROGR4M SAXTO IR ADIATION GRAH LRD FROGRAM

't B

PRO-SAXTON

=

PROGRAM Pu02

+

U02 m

YANKEE CORE 5

T PROGRAM (DATE IS COMPLETION DA TE 0

IO 20 30 110 50 60 MAXIMUM EXPOSURE (IO3 MWDIHTM)

High Power Fuel Rod Exper-i~;cr~tal RoRrem Figure 3.4.1-2

July, 1982

3 Y

% I W

0 0

6-l 7

0

5 99.8 E 99.9 A POIWTS = 809

,-y 99.99-ob 0.7 0.8 0.9 I.

e WIWN DNBR)

W-3CORRELATlON PROBABILITY DISTRIBUTION CURVE

COUPLKHC SPIDER BODY d

\\! I! jl

/ I

, I

! I

! I Ld I J-TOP VIEU i

ROTI

CONTROF, CLWTF:R ASSEhil31,Y CjiJ::.l?t I.

Figure 3.4.1~4a

July, 1982

PRESSURE SOlmF WAPD-LYR-256 WCAP-PSIA 2956 PREDICTED DNB HEAT FLUX, IO6 BTUIHR-F-T*

+ 25%

/

00 A

Y DNBR=I 25%

o P = 1614 PSIA A P = 1814 PSIA 0 P = 2014 PSIA o

P = 2314 PSIA I

I I

I

.4

.5

.6

.7

.I YRk:DIC'l'ED DNI3 HEAT FLUX lo6 BTU/HR-FT2 Figure 3.4.1-6

July, 1982

I. I 1.0 0.6 FLUX DISTRIBUTION 0

COSltiE A

PEAK NEAR OUTLET

REFERENCES:

BAW 3238-7 EUR 21i90e AEEW-R 309 AEEW-R '479 0

.I

.2

.3

.4

.5

.6

.7

.8

.9 PREDICTED cjvnsR, IO6 BTU/HR FT2

lO(

9c 8C 70 60 50 30 20 IO 0

0 COSINE SINGLE DATA POINT 0

COSISE

- MULTIPLE DATA POINTS A

PEAK NEAR OUTLET -

SINGLE DATA PO!NT A

PEAK NEAR OUTLET - ::ULTIPLE DATA POINTS REFERENCES!

BAW 3238-7 EUR 2490 AEEW-R309 AEEW-R479

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I j.,

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.( !

i,:

i.1 I:

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t:.--

i,,

I Figure 3.4.1-9

July, 1982

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:

3 Sheet:

1 of 1 UFSAR Figure: 3.5.1-1 Change

Description:

UCR-2042, Rev. 0

Title:

Schematic of Westinghouse 15 x 15 Upgrade Fuel Unit: 1 Last Revised: Revision 25.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-2

Title:

Plan 9ieZ of Mid Grid to Guide ThimEle -oint (Bottom 9ieZ)

Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-3

Title:

Elevation 9ieZ of Mid-Grid to Guide ThimEle -oint Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-4

Title:

ToS Grid to Guide ThimEle and RemovaEle ToS Nozzle Attachment Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-5

Title:

USgrade Fuel Design Guide ThimEle to Bottom Grid and Nozzle -oint Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-

Title:

Bottom Nozzle to ThimEle TuEe Connection Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-

Title:

Wet Annular BurnaEle AEsorEer Rod Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-

Title:

ComSarison of Borosilicate Glass AEsorEer Rod Zith WABA Rod Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.2-1

Title:

E[amSle Core Loading Pattern Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

UNIT 1 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.2-2

Title:

K(Z) - Normalized Fq(Z) as a Function of Core Height Change

Description:

UCR-1990, Rev. 0 Sheet 1 of 1 Revision: 24.0

I

a 5

c FIGURE 3.5.3-2 0

3;

!a cfl 8

UNIT 1

July 1990

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