ML24159A172

Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 3, Figures (Unit 1)

ML24159A172
Person / Time
Site:	Cook
Issue date:	05/30/2024
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
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ML24159A261	List: AEP-NRC-2024-20, Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 3, Reactor (Unit 2) ML24159A163 ML24159A164 ML24159A165 ML24159A166 ML24159A167 ML24159A168 ML24159A169 ML24159A170 ML24159A171 ML24159A172 ML24159A173 ML24159A174 ML24159A175 ML24159A176 ML24159A177 ML24159A178 ML24159A179 ML24159A180 ML24159A181 ML24159A182 ML24159A183 ML24159A184 ML24159A185 ML24159A186 ML24159A187 ML24159A188 ML24159A189 ML24159A190 ML24159A191 ML24159A192 ML24159A193 ML24159A194 ML24159A195 ML24159A196 ML24159A198 ML24159A199 ML24159A200 ML24159A201 ML24159A202 ML24159A203 ML24159A204 ML24159A205 ML24159A206 ML24159A207 ML24159A208 ML24159A209 ML24159A210 ML24159A211 ML24159A212 ... further results
References
AEP-NRC-2024-20
Download: ML24159A172 (1)

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

B c

e c

r-I i_..

I

.-^...-

I

c.

July, 1982 UFSAR Revision 32.0

UFSAR Revision 32.0

I

- I I

FUEL ASSmSLY OVFLINE Figure 3.2.1-g

.TIB~V.

19fl2 UFSAR Revision 32.0

/m I I li

=

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

l--------

I----

L 3

.. -. )

UFSAR Revision 32.0

c c.

UFSAR Revision 32.0

0 UFSAR Revision 32.0

BF3 l8Oo 90" 270" 0"

BF3 Bur1ubl.e PoFson (I 3)

Secordary Source (4)

Figure 3.2.1-11

July, 1982 UFSAR Revision 32.0

g :

I I

I i

July, 1982 Figure 3.2.1-12 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

,- 0.485" DIA Unit 1 Figure 3.2.1-15 Thimble Plug Assembly July 1996 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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

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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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

-1.0 s-.-&,4

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

+y:c-

~-::*.. (

1;: A...:

~~..,.

_.._.. L

,_.._... ::.i: f-1 Figure 3.3.1-13 JULY, 1984 UFSAR Revision 32.0

I

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0

.+

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-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 UFSAR Revision 32.0

-1.0

-2.0

-3.0 E

. N 2

T

-4.0 0

S II (I u 3

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-7.0

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)

i 200 300 400 500 600 HOD~R TEQEUTURE

\\(P)

July, 1984 UFSAR Revision 32.0

~:j--~~j 1

1.

,,.:y

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. i Ffgure 3.3.1-16

July, 1984 UFSAR Revision 32.0

.i..

i

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1

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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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

3 Y

% I W

0 0

6-l 7

0 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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

UFSAR Revision 32.0

+ 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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

i,i 4

A:.:.

1 T

-1..

_..i

/

._i.._..

II

/

I m

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i,:

i.1 I:

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t:.--

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I Figure 3.4.1-9

July, 1982 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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-2303, Rev. 0 Sheet 1 of 1 Revision: 32.0 UNIT 1 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

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 UFSAR Revision 32.0

I UFSAR Revision 32.0

a 5

c FIGURE 3.5.3-2 0

3;

!a cfl 8

UNIT 1

July 1990 UFSAR Revision 32.0