ML21125A456

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0 to Updated Final Safety Analysis Report, Chapter 3, Figures (Unit 1)
ML21125A456
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Site: Cook  American Electric Power icon.png
Issue date: 04/19/2021
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
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References
AEP-NRC-2021-19
Download: ML21125A456 (50)


Text

CORE BAFFLE-1 I THERMAL SHIELD FUEL ASSEMBLY REACTORVESSEL I93FUELASSEMBLlES CORE Ci?3SS SECJ-!<I?;

Figure 3.2.1-l July, 1982

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

l!PPE::

SUPPORT COLI!H&-'

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

UPi'ER CORE PLATE---

IRRADIATIOH REACTOR VESSEL-

-FUEL ASSEHBL'IX

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

THIMBLE GUIDES Reactor Vessel and Internals Figure 3.2.1-2 July, 1982

PNMLKJHGFEDCBA 180" 2

3 4

5 6

7 90" 8 9

10 11 12 13 1.4 i5 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

Revision: 19.1 Change

Description:

UCR-1727

Title:

D. C. Cook Unit 1 AMERICAN ELECTRIC POWER Core Barrel Assembly COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2.1-5 Sheet 1 of 1 UNIT 1

Revision: 19.1 Change

Description:

UCR-1727

Title:

Upper Core Support Structure AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2.1-6 Sheet 1 of 1 UNIT 1

I i_.. - I -- .-^...-

B c

e I

c r-

c. _--...

July, 1982

I

-I I

FUEL ASSmSLY OVFLINE Figure 3.2.1-g

.TIB~V. 19fl2

-:/m = IliIII ---

I-----,-- l-------- I----

II L3 -.)

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

Revision: 21 Change

Description:

UCR-1812, Rev. 1 UNIT 1

Title:

Control Rod Drive Mechanism Assembly AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2.1-13 Sheet 1 of 1 UNIT 1

r! :

I--: -

I-.-

r-'---

I LIFT COIL GUIDK TUBE VOVABLE GRIPPER POLE

\ _ MOVABLE GRIPPER COIL i

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

I p N H L K J C , E D C 8 A Abaot'ber !'la teria.l:

Ag-In-Cd I D

s ...... I

!)

C A SB S B A

! C S B S A A A SP SP s,., SP A I

I 83 D so C S

D 0 SI SA SP SP SP S H I SC IS C D C B SC S s, SP SP s,. S B

B D so C SD D

I A S? SA S1' SP A I SA I s ,.

C A SB s, A D SC i) o*

!!.!!! Nulllber of Rod Cl:..sters SA 8 s, 8 SC 4 S 4 D

A a I CONTIOL ROD PATTERN 4 (UHIT 1}

C 8 D 9 PL 0 82 SP (apare rod locations) 12 July, 1982 FIGURE 3.3.1-1

l.116 1.023 1.094 1.099 0.964 l.119 1.07.8 1.138 1.063 l.142 l.21 7 l.087 l.1S6 o. 978 l.197 1.220 l.205 1.168 1.108 O.SS9 l.01S 1.on l.016 1.057 l.009 o.asa 0.487 0.7:36 0.833 o. 710 0.611 AP - i.sSE'1BLY POWER FiguM! 3..3.1-2 CYCLE l ASSEMBLYWISE OWER (BOL) Ju.ly, 1984

1.175 1.215 1.162 I

1 1.159 1.158 1.144 I

1 1.187 1.138 1.181 1.126 I

1.125 .l. 174 1.119 1.102 1.203 II 1.153 1.082 1.161 1.047 0.951 0.968 1.000 0.9f6 0.964 0.817 0.781 0.677 0.576 I

- ASSFfBLY POWER Fiqure 3.3.1- 3 CYCLE 1 ASSMBLYWTSEPOWER(MOL) July, 1984

I 1.163 1.088 1.171 1.079 1.162 1.093 1.066 1.lu / 1.o74 / 1.153 1.213

-1 1.144 1.047 1.147 1.036 1.051 1.028 I

0.969 7qTqzl- 0.855 0.557 I k 0.773 0.809 1 0.732 0.600 AP AP - ASSMBLY POWER

/

Figure 3.3.1-4 CYCLE 1 ASSE~BLYWISEPOWE?, (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 aT I IJAL II LU l A I

IIL0.e I .L A0 I --

20 IJ I LL ,

I-1 I Y 20 16 16 16 16 16 I I 20 1

9 12 16 16 16 16 12 9, I 20 I Lb 16 16 I 16 16 I 20  !

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

t 1 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 ..~... . .. .~~..,.

.. . ~-::*.._.._..L 1;:A. ..: +y:c- ,_ ,_.._...( :: .i: f-1 Figure 3.3.1- 13 JULY, 1984

. .! ..:./ ,i ..+ ,/. ..j . ..i. .,..-. 1.

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I __-L , ,.,

0 T-4---.- I : L 1

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

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J?A 1

-3.0 j7i ,.. j i i_, i .I;::' PPP

..! ..'.i '

PPm 100 200 300 MO0 500 ,600 BOL, ALL WNTROL RODSIX5~15 Figure 3.3.1~-14 JULY, 1984

-1.0

-2.0

-3.0 E

N 2

T -4.0 0

S II (I

u -5.0 3 :I..; . :.. .:::.-. 7 .-.--. __..

z?-,!. .I 1 p:: ,, ,

d I ..::. T.I j .,1: i..:.

. . . -.-.-. i,. . . .,1.,_,I1 ..

.:*..  :. .~~:!-ee~E:m

,fi-,i.. ,I!. .I j  ; i- .:!iTTi-- .- :+ -_-.. :_.-.

-6.0 .j.q.L j j

.+.-:: . . . i  : .i I. )

i

-7.0 200 300 400 500 , 600 HOD~R TEQEUTURE \(P)

July, 1984

~:j--~~j .; 1 .:., 1. .:- $ . .. .  ; _;

- -a-.. -:i.- ---. -. _.__

..:.  :,,.:y I ,

i i

-TV .:: . . . .; . . . . . ..-... I . . - i.. .,. _ . .

Ffgure 3.3.1- 16 July, 1984

I I

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,. 1 i. '-'

i .I  : . . I B... " -a.--. -___ -...- w..----. . ..-

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1 Wplu $...~~u4& +,  :

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50 Loo Percent Full Power Figure 3.3.1-17: Doppler Contributions to the Power July, 1992 Coefficient vs. Power Level UNIT 1

c.37 LfGE)tD:

'PfRXKT PCRCEkl ThfOCiTICA!. THEOR'TtCAL DEWSllY I OEXS! ?Y  !

0.06 - \ n GYLLAKDER 96.4 0 k0wA~D b GuLvIN c

A gj AStdOTO 95.0 Q LUCKS & DEE!,!

DANIEL El AL f-J& .. 0 MDFREY 93.4 0

- A STORA 92.2 e FflTH 0.05 0 A.C. S!l.sH 34.4 8 VOGT ET AL

@ ASMOTO 91.0 ' 1l NlSHIJl\!A v KRiJOER 93.7 v WHEELER b AIHSCOUGH 0.01) SEi REFERENCES FOR THEIHAL-tiYCRAULIC SECTION 0.03 0.02 -

0.01 i

T 27 26 SAXTOH OVER-(16) POWER TEST 25 L

a SAXTON Pu0yU02 (2) EXTENDED BURNUP TESTS 24 n n 7170 7171 23 (50) (50) 22 7 ASSEMBLIES 21 20 19 18 POWER ESCALATION 17 16 LEGEND:

15

  • PRESSURIZED RODS ARE IHCiU DED IN THESE ASSEMBLIES 14 (X) NO. OF RODS a CVTR IRRADIATION PROGR4M 13 SAXTO IR ADIATION PRO-2, l INTEsNTION- GRAH 't LRD B FROGRAM LLY. DEFECTED) 12 SAXTON Pu02 + U02

= PROGRAM I I m YANKEE CORE 5 IO T PROGRAM (DATE IS COMPLETION DA TE 9

8 7

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

0 0

6-l 3

Y I

W 7 -

0

A POIWTS = 809 5 99.8 E 99.9

,-y 99.99- ob e . 0.7 0.8 0.9 I.

WIWN DNBR)

W-3CORRELATlONPROBABILITY DISTRIBUTIONCURVE

COUPLKHC SPIDER BODY d

\!I!

jl

/ I

, I

! I

! I Ld I

TOP VIEU i J-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 PREDICTEDDNB HEATFLUX, IO6BTUIHR-F-T*

+ 25%

/

A 00 Y DNBR=I 25%

o P = 1614PSIA A P = 1814PSIA 0 P = 2014PSIA o P = 2314PSIA 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 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 30 REFERENCES!

BAW 3238-7 20 EUR 2490 AEEW-R309 AEEW-R479 IO 0

i,i  ; ,-

4 A:.:. 1

/ II /

T .; -1.. _. .i ._i.._..  ; ..- ..__.. .

I , i m I :. i

! ,. i . 1.

/ I  :,A  : __. 72 , i:.-._

.. . __.. 1 _

, /:__ ,1  ;  : _.. ..-  ;. .

. . ..I ,-- r-i

II

,:I 1.: I ,

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)! . -1. 1-1:.._ /_.: / ___. I

,i  :  : 1

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g t

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1 I

. j ,I_. , , .
! i
.,:;.*

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w .-  : I .( !  !

i,:  !

i.1 _, I:

__ . I t:.-- ..

I  ! i,, I Figure 3.4.1-9 July, 1982

INDIANA AND MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Chapter: 3 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1 Change

Description:

UFSAR Figure: 3.5.1-1 UCR-2042, Rev. 0 Unit: 1

Title:

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

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

Plan ie of Mid Grid to Guide COOK NUCLAR PLANT Thim le oint (Bottom ie )

NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-2 Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

Elevation ie of COOK NUCLAR PLANT Mid-Grid to Guide Thim le oint NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-3 Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

To Grid to Guide Thim le and COOK NUCLAR PLANT Remova le To Nozzle Attachment NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-4 Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

U grade Fuel Design Guide Thim le COOK NUCLAR PLANT to Bottom Grid and Nozzle oint NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1-5 Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

Bottom Nozzle to COOK NUCLAR PLANT Thim le Tu e Connection NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1- Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

Wet Annular Burna le COOK NUCLAR PLANT A sor er Rod NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1- Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

Com arison of Borosilicate Glass COOK NUCLAR PLANT A sor er Rod ith WABA Rod NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.1- Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

E am le Core Loading Pattern COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.2-1 Sheet 1 of 1 UNIT 1

Revision: 24.0 Change

Description:

UCR-1990, Rev. 0 AMERICAN ELECTRIC POWER

Title:

K(Z) - Normalized Fq(Z)

COOK NUCLAR PLANT as a Function of Core Height NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.5.2-2 Sheet 1 of 1 UNIT 1

I a

5 0

3;

!a cfl 8

c FIGURE 3.5.3-2 UNIT 1 July 1990