ML24159A225: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:INDIANA AND MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Chapter: 3 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
{{#Wiki_filter:INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised:
 
26.0 Chapter:
UFSAR Figure: 3.2-1 Change
3 Sheet:
1 of 1 UFSAR Figure: 3.2-1 Change


== Description:==
== Description:==
UCR-2052, Rev. 0 Unit:2
UCR-2052, Rev. 0 Unit: 2


==Title:==
==Title:==
Fuel Assembly Cross Section 17 x 17 Vantage 5 Update UFSAR Figure: 3.2-2 Change
Fuel Assembly Cross Section 17 x 17 Vantage 5 Update UFSAR Revision 32.0
 
UFSAR Figure: 3.2-2 Change


== Description:==
== Description:==
UCR-2116, Rev. 0 Unit:2
UCR-2116, Rev. 0 Unit: 2


==Title:==
==Title:==
Vantage 5 Fuel Assembly INDIANA AND MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Chapter: 3 UPDATED FINAL SAFETYANALYSIS REPORT Sheet: 1 of 1
Vantage 5 Fuel Assembly UFSAR Revision 32.0


UFSAR Figure: 3.2-3 Change
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised:
26.0 Chapter:
3 Sheet:
1 of 1 UFSAR Figure: 3.2-3 Change


== Description:==
== Description:==
UCR-2052, Rev. 0 Unit:2
UCR-2052, Rev. 0 Unit: 2


==Title:==
==Title:==
17 X 17 Fuel Rod Assembly Revision: 19.0 Change
17 X 17 Fuel Rod Assembly UFSAR Revision 32.0
 
Unit 2 Revision: 19.0 Change


== Description:==
== Description:==
UCR-1703
UCR-1703 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-4 Sheet 1 of 1


==Title:==
==Title:==
D.C. Cook Unit 2 AMERICAN ELECTRIC POWER Plan View COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-4 Sheet 1 of 1
D.C. Cook Unit 2 Plan View UFSAR Revision 32.0
 
Unit 2
-3 I- ?
 
0.C. C3OK UNIT 2
 
Tap GRID TO THIMBLE ATTACHMENT I FIGURE 3.2-5 I GUIDE THIMBLE TUBE GUIDE THIMBLE TUBE
 
d.-----., d.-----.,
-7 iFM GRID GRID )
 
i i..-----,I..-----,I..--w-., +..--w-., + !2
 
11% GRID SLEEVE 4 WELD 11% GRID SLEEVE 4 WELD
 
EXPANSiON LOBE EXPANSiON LOBE
 
GUIDE THiMBLE -i;BE I 1 GUIDE THiMBLE -i;BE


Ml0 GRID GRID -
-3 I-
?
0.C.
C3OK UNIT 2
I Tap GRID TO THIMBLE ATTACHMENT FIGURE 3.2-5 I
UFSAR Revision 32.0


1
iFM Ml0 GUIDE THIMBLE TUBE GUIDE THIMBLE TUBE d.-----.,
d.-----.,
-7 GRID GRID
)
i i
..-----,I..-----,I
..--w-.,
+
..--w-.,
+
!2 11%
GRID SLEEVE 4
11%
GRID SLEEVE 4
WELD WELD EXPANSiON LOBE EXPANSiON LOBE GUIDE THiMBLE
-i;BE GUIDE THiMBLE
-i;BE I
1 GRID GRID -
1
\\
\\
MID GRIO SLEEVE EXPANSiON LOBE
---fit EXPANSiON LOBE OlMtNSlONS ARE IN INCHES (MOWN&)
UFSAR Revision 32.0


\\
Unit 2 Revision: 19.0 Change
\\..
 
MID GRIO SLEEVE
 
EXPANSiON LOBE EXPANSiON LOBE
---fit
 
OlMtNSlONS ARE IN INCHES (MOWN&)
Revision: 19.0 Change


== Description:==
== Description:==
UCR-1703
UCR-1703 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-6 Sheet 1 of 1


==Title:==
==Title:==
D. C. Cook Unit 2 AMERICAN ELECTRIC POWER Top Nozzle to Thimble Attachment COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-6 Sheet 1 of 1
D. C. Cook Unit 2 Top Nozzle to Thimble Attachment UFSAR Revision 32.0
 
Unit 2 UFSAR Revision 32.0


UFSAR Figure: 3.2-6A Change
UFSAR Figure: 3.2-6A Change


== Description:==
== Description:==
2 UCR-2330,. Rev. 0 Unit:
UCR-2330,. Rev. 0 Unit: 2


==Title:==
==Title:==
Line 97: Line 104:


There is a double top grid bulge configuration starting with the Unit 2 fresh fuel in Cycle 24, where a triple top grid bulge configuration was the previous configuration.
There is a double top grid bulge configuration starting with the Unit 2 fresh fuel in Cycle 24, where a triple top grid bulge configuration was the previous configuration.
Revision: 19.0 Change
UFSAR Revision 32.0
 
Unit 2 Revision: 19.0 Change


== Description:==
== Description:==
UCR-1703
UCR-1703 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-7 Sheet 1 of 1


==Title:==
==Title:==
D.C. Cook Unit 2 AMERICAN ELECTRIC POWER Guide Thimble to Bottom Nozzle Joint COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-7 Sheet 1 of 1
D.C. Cook Unit 2 Guide Thimble to Bottom Nozzle Joint UFSAR Revision 32.0
 
Unit 2 UFSAR Revision 32.0


UFSAR Figure: 3.2-8 Change
UFSAR Figure: 3.2-8 Change
Line 113: Line 120:


==Title:==
==Title:==
Typical Core Barrel Assembly Revision: 19.1 Change
Typical Core Barrel Assembly UFSAR Revision 32.0
 
UNIT 2 Revision: 19.1 Change


== Description:==
== Description:==
UCR-1727
UCR-1727 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-9 Sheet 1 of 1


==Title:==
==Title:==
Upper Core Support Structure AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-9 Sheet 1 of 1
Upper Core Support Structure UFSAR Revision 32.0


UNIT 2 6 I6U-2
6 I6U-2 HEAD AND VESSEL ALIGNMENT PIN LOCATION Figure 3.2-10 Plan View of Upper Core Support Structure UNIT 2
: July, 1982 UFSAR Revision 32.0


HEAD AND VESSEL ALIGNMENT PIN LOCATION
16.4 REVISED PER 99-UFSAR-1243 TYPICAL FULL LENGTH ROD CLUSTER CONTROL AND DRIVE ROD ASSEMBLY WITH INTERFACING COMPONENTS FSAR FIG. 3.2-11 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


Figure 3.2-10 Plan View of Upper Core Support Structure
16.4 REVISED PER 99-UFSAR-1243 FULL LENGTH ROD CLUSTER CONTROL ASSEMBLY OUTLINE FSAR FIG. 3.2-12 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 160.949 1.838 Dia.
Max.
0.362 Dia. Max.
1.470 Dia. Max.
UFSAR Revision 32.0


UNIT 2 July, 1982 UNIT 2
16.4 REVISED PER 99-UFSAR-1243 FULL LENGTH ABSORBER ROD FSAR FIG. 3.2-13 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 171.845 for groups 08, 09, & 14 151.885 for groups 11-13 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1243
16.4 REVISED PER 99-UFSAR-1243 TYPICAL BURNABLE POISON ASSEMBLY FSAR FIG. 3.2 - 15A SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL FULL LENGTH ROD CLUSTER CONTROL AND DRIVE COOK NUCLEAR PLANT ROD ASSEMBLY WITH INTERFACING COMPONENTS NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2-11 SH 1 of 1 UNIT 2
CWAE3A) ASSEMBLY 1EF. DWGS:
I A
UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1243
16.4 REVISED PER 99-UFSAR-1243 TYPICAL BURNABLE POISON ROD CROSS SECTION FSAR FIG. 3.2-16A SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE FULL LENGTH ROD CLUSTER CONTROL COOK NUCLEAR PLANT ASSEMBLY OUTLINE NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2-12 SH 1 of 1 UNIT 2
UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1243
16.4 REVISED PER 99-UFSAR-1243 PRIMARY SOURCE ASSEMBLY FSAR FIG. 3.2-17 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 HISTORICAL UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE FULL LENGTH ABSORBER ROD COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2-13 SH 1 of 1 UNIT 2
16.4 REVISED PER 99-UFSAR-1243 SECONDARY SOURCE ASSEMBLY FSAR FIG. 3.2 - 18 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 NOTE: ALL DIMENSIONS ARE IN INCHES 97.0 SECONDARY SOURCE 0.426 DIA.
0.338 DIA.
UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1243
16.4 REVISED PER 99-UFSAR-1243 THIMBLE PLUG ASSEMBLY FSAR FIG. 3.2-19 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 0.426 DIA.
UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLETYPICAL BURNABLE POISON ASSEMBLY COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2 - 15A SH 1 of 1 CWAE3A) ASSEMBLY 1EF. DWGS:
==Title:==
I A UNIT 2
Full Length Control Rod Drive Mechanism Sheet 1 of 1 UFSAR Figure: 3.2-20 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Change
 
16.4 REVISED PER 99-UFSAR-1243
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL BURNABLE POISON ROD CROSS COOK NUCLEAR PLANT SECTION NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2-16A SH 1 of 1
 
UNIT 2
 
16.4 REVISED PER 99-UFSAR-1243
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE PRIMARY SOURCE ASSEMBLY COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2-17 SH 1 of 1 UNIT 2
 
16.4 REVISED PER 99-UFSAR-1243
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE SECONDARY SOURCE ASSEMBLY COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2 - 18 SH 1 of 1 0.426 DIA.
 
UNIT 2
 
16.4 REVISED PER 99-UFSAR-1243
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE THIMBLE PLUG ASSEMBLY COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.2-19 SH 1 of 1 Revision: 21.2 Change


== Description:==
== Description:==
UCR-1836
UCR-1836 Revision: 21.2 UNIT 2 UFSAR Revision 32.0
 
AMERICAN ELECTRIC POWER


==Title:==
Revision: 21.2 Change
Full Length Control Rod Drive Mechanism
 
COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-20 Sheet 1 of 1
 
UNIT 2 Revision: 21.2 Change


== Description:==
== Description:==
UCR-1836
UCR-1836
AMERICAN ELECTRIC POWER


==Title:==
==Title:==
Full Length Control Rod Drive Mechanism COOK NUCLEAR PLANT Schematic NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-21 Sheet 1 of 1
Full Length Control Rod Drive Mechanism Schematic AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-21 Sheet 1 of 1 UNIT 2 UFSAR Revision 32.0


UNIT 2 BEFORE LOAD TRANSFER AFTER LOAD LOAD TRANSFER D &!!
BEFORE LOAD TRANSFER MG IF I I
MG MG IF I I AT 70' 1 AT 70' I
B I
LIFT COIL OFF LIFT COIL ON LIFT COIL OFF LIFT COIL ON Figure 3.2-23 AT 70' 1
AT 650' I
LOAD AFTER LOAD D &!!
MG B
B I
I LIFT COI LIFT COIL OFF IL OFF I I I I LIFT COI LIFT COIL ON L ON I
I I
I I
I LIFT COIL OFF I
I LIFT COIL ON I
I P
SG TRANSFER AT 70' I
I AT 650' I
Nominal Latch Cleal-ante at Minimum and Maximum Temper-atute UFSAR Revision 32.0


B I LIFT COIL OFF B B I I LIFT COI LIFT COIL OFF IL OFF LIFT COIL ON I I LIFT COIL ON L ON I I LIFT COI I I I I I I LIFT COIL OFF
0.080 2
 
0.070 W
AT 650' I I AT 650' I
5 0.060 W
 
w c
LIFT COIL OFF
g 0.050 W w Ei 0.0110 E
 
0.030 E
LIFT COIL ON I I LIFT COIL ON I I
5 0.020 E
 
2 0.010 Y
SG
0 0.000 LIFT COIL OFF
 
/
P
MG CLEARANCE AFTER
 
/
Figure 3.2-23 Nominal Latch Cleal-ante at Minimum and Maximum Temper-atute 0.080
LOAD TRANSFER 0
 
too 200 300 ill0 TEMPERATURE (OF) 500 600 Figure 3.2-24 Control Rod D rive Mechanism Latch Cleatonce Thelma1  
2 0.070 -
.Effect 300 UFSAR Revision 32.0
W
 
5
: 0.060 - LIFT COIL OFF /
 
W w MG CLEARANCE AFTER /
LOAD TRANSFER c g 0.050
 
W w
 
Ei 0.0110 E
; 0.030 E
5 0.020 -
 
E 2 0.010 -
Y 0
 
0.000
 
0 too 200 300 ill0 500 600 300
 
TEMPERATURE (OF)
 
Figure 3.2-24 Control Rod D rive Mechanism Latch Cleatonce Thelma1.Effect 6" 6"
 
5"
 
132" 121"
 
6"


16.4 REVISED PER 99-UFSAR-1242 Typical Axial Zoning of Uranium Enrichment and IFBA Poisoning FSAR FIG. 3.3-1 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 5"
121" 6"
6" 6"
6" 6"
6" 6"
132" UFSAR Revision 32.0


UNIT 2
16.4 REVISED PER 99-UFSAR-1242 EXAMPLE LOW LEAKAGE FUEL LOADING ARRANGEMENT FSAR FIG. 3.3-2 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
 
DESCRIPTION REVISIONS TITLE DWG. NO.
16.4 REVISED PER 99-UFSAR-1242
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE Typical Axial Zoning of Uranium COOK NUCLEAR PLANT Enrichment and IFBA Poisoning NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-1 SH 1 of 1 UNIT 2
16.4 REVISED PER 99-UFSAR-1242 TYPICAL PRODUCTION AND CONSUMPTION OF HIGHER ISOTOPES FSAR FIG. 3.3 - 3 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE EXAMPLE LOW LEAKAGE FUEL LOADING COOK NUCLEAR PLANT ARRANGEMENT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-2 SH 1 of 1 UNIT 2
UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 EXAMPLE BORON CONCENTRATION OVER CYCLE LENGTH FSAR FIG. 3.3-6 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLETYPICAL PRODUCTION AND COOK NUCLEAR PLANT CONSUMPTION OF HIGHER ISOTOPES NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3 - 3 SH 1 of 1
16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT BEGINNING-OF-LIFE UNRODDED CORE, HOT FULL POWER, NO XENON FSAR FIG. 3.3-7 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


UNIT 2
16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT BEGINNING-OF-LIFE UNRODDED CORE, HOT FULL POWER, EQUILIBRIUM XENON FSAR FIG. 3.3-8 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION NEAR BEGINNING-OF-LIFE GROUP D AT INSERTION LIMIT, HOT FULL POWER, EQUILIBRIUM XENON FSAR FIG. 3.3-9 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE EXAMPLE BORON CONCENTRATION OVER COOK NUCLEAR PLANT CYCLE LENGTH NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-6 SH 1 of 1 UNIT 2
16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT MIDDLE-OF-LIFE UNRODDED CORE, HOT FULL POWER, EQUILIBRIUM XENON.
FSAR FIG. 3.3-10 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 AVERAGE POWER UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION NEAR END-OF-LIFE UNRODDED CORE, HOT FULL POWER, EQUILIBRIUM XENON.
FSAR FIG. 3.3-11 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT COOK NUCLEAR PLANT BEGINNING-OF-LIFE UNRODDED CORE, HOT FULL POWER, NO NUCLEAR GENERATION GROUP XENON BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-7 SH 1 of 1 UNIT 2
16.4 REVISED PER 99-UFSAR-1242 TYPICAL RODWISE POWER DISTRIBUTION IN A TYPICAL ASSEMBLY (ASSEMBLY G-12) NEAR BEGINNING-OF-LIFE, HOT FULL POWER, EQUILIBRIUM XENON, UNRODDED CORE.
FSAR FIG. 3.3-12 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 TYPICAL RODWISE POWER DISTRIBUTION IN A TYPICAL ASSEMBLY (ASSEMBLY G-12) NEAR END-OF-LIFE, HOT FULL POWER EQUILIBRIUM XENON, UNRODDED CORE.
FSAR FIG. 3.3-13 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT COOK NUCLEAR PLANT BEGINNING-OF-LIFE UNRODDED CORE, HOT FULL POWER, NUCLEAR GENERATION GROUP EQUILIBRIUM XENON BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-8 SH 1 of 1 UNIT 2
8 d tl3fiOd 03ZllVWMON UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 EXAMPLE AXIAL POWER SHAPES OCCURRING AT MOL FSAR FIG. 3.3-15 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 P - 1 D - 0.05 AO - -2.132%
P - 1 D - 0.130 AO - -7.082%
UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION NEAR COOK NUCLEAR PLANT BEGINNING-OF-LIFE GROUP D AT INSERTION LIMIT, HOT FULL NUCLEAR GENERATION GROUP POWER, EQUILIBRIUM XENON BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-9 SH 1 of 1 AVERAGE POWER
UFSAR Revision 32.0


UNIT 2
16.4 REVISED PER 99-UFSAR-1242 MAXIMUM F Q (Z) x POWER VERSUS AXIAL HEIGHT (Z) DURING NORMAL OPERATION FSAR FIG. 3.3-20 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 2.159 2.335 2.335 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 TYPICAL PEAK LINEAR POWER DURING CONTROL ROD MALFUNCTION OVERPOWER TRANSIENTS FSAR FIG. 3.3-21 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT COOK NUCLEAR PLANT MIDDLE-OF-LIFE UNRODDED CORE, HOT FULL POWER, NUCLEAR GENERATION GROUP EQUILIBRIUM XENON.
16.4 REVISED PER 99-UFSAR-1242 TYPICAL PEAK LINEAR POWER DURING BORATION/DILUTION OVERPOWER TRANSIENTS FSAR FIG. 3.3-22 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-10 SH 1 of 1 UNIT 2
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 ILLUSTRATION OF A COMPARISON BETWEEN CALCULATED AND MEASURED RELATIVE FUEL ASSEMBLY POWER DISTRIBUTION FSAR FIG. 3.3-23 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION NEAR COOK NUCLEAR PLANT END-OF-LIFE UNRODDED CORE, HOT FULL POWER, NUCLEAR GENERATION GROUP EQUILIBRIUM XENON.
16.4 REVISED PER 99-UFSAR-1242 COMPARISON OF TYPICAL CALCULATED AND MEASURED AXIAL SHAPE FSAR FIG. 3.3-24 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-11 SH 1 of 1 UNIT 2
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL RODWISE POWER DISTRIBUTION IN A TYPICAL COOK NUCLEAR PLANT ASSEMBLY (ASSEMBLY G-12) NEAR BEGINNING-OF-LIFE, HOT NUCLEAR GENERATION GROUP FULL POWER, EQUILIBRIUM XENON, UNRODDED CORE.
16.4 REVISED PER 99-UFSAR-1242 EXAMPLE DOPPLER TEMPERATURE COEFFICIENT AT BOL AND EOL FSAR FIG. 3.3-26 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-12 SH 1 of 1 UNIT 2
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 EXAMPLE DOPPLER ONLY POWER COEFFICIENT AT BOL AND EOL FSAR FIG. 3.3-27 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL RODWISE POWER DISTRIBUTION IN A TYPICAL COOK NUCLEAR PLANT ASSEMBLY (ASSEMBLY G-12) NEAR END-OF-LIFE, HOT FULL NUCLEAR GENERATION GROUP POWER EQUILIBRIUM XENON, UNRODDED CORE.
I-I 8OL LJ w-a.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-13 SH 1 of 1
EOL Figure 3.3-28 Example Doppler Only Power Defect
- BOL, EOL UNIT 2 July 1991 UFSAR Revision 32.0


P - 1 P - 1 D - 0.130 D - 0.05 AO - -7.082%
UFSAR Revision 32.0
AO - -2.132%


UNIT 2
Figure 3s.3.30
#ourmr TWERAllJRt (F)
Example Moderator Temperature Coefficient EOL UNIT 2 July 199b UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
16.4 REVISED PER 99-UFSAR-1242 EXAMPLE MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF BORON CONCENTRATION - BOL, NO RODS FSAR FIG. 3.3-31 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE EXAMPLE AXIAL POWER SHAPES COOK NUCLEAR PLANT OCCURRING AT MOL NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-15 SH 1 of 1
16.4 REVISED PER 99-UFSAR-1242 EXAMPLE HOT FULL POWER MODERATOR TEMPERATURE COEFFICIENT (AT THE CRITICAL BORON CONCENTRATION)
VERSUS BURNUP FSAR FIG. 3.3-32 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 2 UFSAR Revision 32.0


2.335 2.335
Figure 3.3-33 Example Total Power Coefficient at BOL and EOL UNIT 2 July 1991 UFSAR Revision 32.0


2.159
Figure 3.3-34 Example Total Power Defect at BOL and EOL UNIT 2
July 1991 UFSAR Revision 32.0


UNIT 2
1 2
3 4
3 6
7 9GO a
9 10 1 1 12 17
?J 1s
?
I I
33 I
/
/ j j
it/
joi j*i
/q
/*I j3/
11 i
/ sa I I
1 I I
/
I
/ / i sa i j
j
/l(lj dl*
c
!/I8
/
I so I
I I
1 0
/
SC i
fA
/
I SA I
1 0
0
/
I I
SC Iso/
I
]
SA SWtgoUN 8ANK fiWtD@UW
#AlUK fnutoowru HANK CaNtllOC 8ANK CoNtROt.
8ANK CONTROL OANK CONTROL 8ANK 00 FUNCtrON i:
SC 6
so c
0 NUM8Ei)
OF 800 CLiJSfCRS 8
464 4
a a
9 Figure 3.3-35 Rod Cluster Control Assembly Pattern July 1991 UNIT 2 UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
CuaVL 1
2 1650 7700 32.1 27.2
-O.OYb
-0.011)
I I
I I
I I
I I
I I
I I
I I
I I
I 0
4 8
12 16 20 2l 28 32 36 40 UU l8 52 56 60 64 68 72 71wL (HOURS)
Figure 3.3-36 Axial Offset Versus Time PWR Core With a 12-Ft Height and 121 Assemblies I
UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE MAXIMUM F Q (Z) x POWER VERSUS AXIAL COOK NUCLEAR PLANT HEIGHT (Z) DURING NORMAL OPERATION NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-20 SH 1 of 1 UNIT 2
0
- a
-a 3
0 3
B i
0 Y
8 12 16 20 2u 26 32 36 110 uu UB 52
!j6 60
(
Figure 3.3-37 IN Xenon Test Thermocouple


16.4 REVISED PER 99-UFSAR-1242
===Response===
Quadrant Tilt Difference Versus Time UFSAR Revision 32.0


REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL PEAK LINEAR POWER DURING CONTROL ROD COOK NUCLEAR PLANT MALFUNCTION OVERPOWER TRANSIENTS NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-21 SH 1 of 1 UNIT 2
-60.0
-50.0 CI P
c 1 30.0 6 5 -30.0 L 3 3 -20.0 ii!
ii
-10.0 0
ii c0n1a01 UYU wnffrsrrlow uouow CoHrLaSAllOn tx?trrnfrr CALCUl AI Ion 0
YO 50 60 PERCLrl Of FULL POWER Figure 3.3-38 Calculated and Measured Doppler Defect and Coefficients at BOL Two-Loop
: Plant, 121 Assemblies, LZ-Ft Core
-2uOo
-2200
-2000
-UOO
-200 0
UFSAR Revision 32.0


16.4 REVISED PER 99-UFSAR-1242
0.07 0.06 c
 
i z
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE TYPICAL PEAK LINEAR POWER DURING BORATION/DILUTION COOK NUCLEAR PLANT OVERPOWER TRANSIENTS NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-22 SH 1 of 1 UNIT 2
0.05 t-  
 
- Y g
16.4 REVISED PER 99-UFSAR-1242
0.w w
 
E z
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE ILLUSTRATION OF A COMPARISON BETWEEN CALCULATED COOK NUCLEAR PLANT AND MEASURED RELATIVE FUEL ASSEMBLY POWER NUCLEAR GENERATION GROUP DISTRIBUTION BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-23 SH 1 of 1 UNIT 2
B 0
 
0.03  
16.4 REVISED PER 99-UFSAR-1242
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE COMPARISON OF TYPICAL CALCULATED COOK NUCLEAR PLANT AND MEASURED AXIAL SHAPE NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-24 SH 1 of 1
 
UNIT 2
 
16.4 REVISED PER 99-UFSAR-1242
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE EXAMPLE DOPPLER TEMPERATURE COOK NUCLEAR PLANT COEFFICIENT AT BOL AND EOL NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-26 SH 1 of 1 UNIT 2
 
16.4 REVISED PER 99-UFSAR-1242
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE EXAMPLE DOPPLER ONLY POWER COOK NUCLEAR PLANT COEFFICIENT AT BOL AND EOL NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-27 SH 1 of 1 I-I w-a. 8OL LJ EOL
 
Figure 3.3-28 Example Doppler Only Power Defect - BOL, EOL
 
UNIT 2 July 1991
 
#ourmr TWERAllJRt (F)
 
Figure 3s.3.30 Example Moderator Temperature Coefficient -
EOL
 
UNIT 2 July 199b UNIT 2
 
16.4 REVISED PER 99-UFSAR-1242
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE EXAMPLE MODERATOR TEMPERATURE COEFFICIENT AS A COOK NUCLEAR PLANT FUNCTION OF BORON CONCENTRATION - BOL, NO RODS NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-31 SH 1 of 1 UNIT 2
 
16.4 REVISED PER 99-UFSAR-1242
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE EXAMPLE HOT FULL POWER MODERATOR TEMPERATURE COOK NUCLEAR PLANT COEFFICIENT (AT THE CRITICAL BORON CONCENTRATION)
NUCLEAR GENERATION GROUP VERSUS BURNUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-32 SH 1 of 1
 
Figure 3.3-33 Example Total Power Coefficient at BOL and EOL
 
UNIT 2 July 1991 Figure 3.3-34 Example Total Power Defect at BOL and EOL
 
UNIT 2 July 1991
?
 
1
 
2
 
3
 
4
 
3
 
6
, I I 33
 
7 I, / / j j
, it/ joi j*i /q /*I j3/ 11 i 9GO a
 
9
! / sa I I 1 I I / I / / i sa i j j
 
10
/l(lj dl* c !/I8 / I
 
1 1
! I so I I I
 
12 SA 0 0 / 1 0 / SC i fA /
I 1
 
17 SC
, Iso/ I ! ] I I
?J SA
 
1s
 
00
 
NUM8Ei) OF FUNCtrON 800 CLiJSfCRS
 
SWtgoUN 8ANK fiWtD@UW #AlUK i: 8 fnutoowru HANK SC 6 so 464 4 a a CaNtllOC 8ANK CoNtROt. 8ANK :
CONTROL OANK c CONTROL 8ANK 0 9
 
Figure 3.3-35 Rod Cluster Control Assembly Pattern
 
July 1991 UNIT 2
 
CuaVL
 
1 2 1650 -O.OYb 7700 32.1 27.2 -0.011)
I I I I I I I I I I I I I I I I I 0 4 8 12 16 20 2l 28 32 36 40 UU l8 52 56 60 64 68 72 71wL (HOURS)
 
Figure 3.3-36 Axial Offset Versus Time PWR Core With a 12-Ft Height and 121 Assemblies I 0
- a
-a 3 0
 
3
 
B
 
i
 
0 Y 8 12 16 20 2u 26 32 36 110 uu UB 52 !j6 60 (
 
Figure 3.3-37 IN Xenon Test Thermocouple Response Quadrant Tilt Difference Versus Time
-60.0 -2uOo
 
-2200
-50.0 c0n1a01 UYU wnffrsrrlow -2000 CI P c 1 30.0 ii uouow CoHrLaSAllOn
- tx?trrnfrr
- - - CALCUl AI Ion 6 5 -30.0 L 3
 
3 -20.0 ii!
ii
-10.0 -UOO
 
-200
 
0 0 0 YO 50 60 PERCLrl Of FULL POWER
 
Figure 3.3-38 Calculated and Measured Doppler Defect and Coefficients at BOL Two-Loop Plant, 121 Assemblies, LZ-Ft Core 0.07
 
LfGfYD: PfRCLYI tEICLN 1
 
lYtDlfllCA1 INCDUfIICM 0.06 DfNSI IY DLltllY
- 0 GYllAWDfl 96.4 0 wOUA80 A Gulvlw 96.0 c l AS&U10 95.0. LUClS A DffM 96.6 0 DDBCILY 93.4 0 DAYIt fl Al 96.5 i z 0.05 A SIDIA 92.2 + ffllll 97.9
. - t- - Y l AD. WI at.4 0 YOGI f1 Al 97.0 A IIISHIJIMA 95.0 v rnUGCl 93.7 v WffLfl 6 AlNSCOUGN 97.0 g 0.w SEE RfffIfICfS fOR INfUMAL-HYDAAUllC SECTtOY w
E A z
B 0 0.03
-l z
-l z
iii b-
iii b-0.02 0.01 0
LfGfYD:
PfRCLYI tEICLN 1 lYtDlfllCA1 INCDUfIICM DfNSI IY DLltllY 0
GYllAWDfl 96.4 0
wOUA80 A Gulvlw 96.0 l AS&U10 95.0 LUClS A DffM 96.6 0
DDBCILY 93.4 0
DAYIt fl Al 96.5 A
SIDIA 92.2
+
ffllll 97.9 l
AD. WI at.4 0
YOGI f1 Al 97.0 A
IIISHIJIMA 95.0 v
rnUGCl 93.7 v
WffLfl 6 AlNSCOUGN 97.0 SEE RfffIfICfS fOR INfUMAL-HYDAAUllC SECTtOY A
1600 Figure 3.4-l Thermal Conductivity of U02 (Data Corrected to 95% Theoretical Density) 3200 I
UFSAR Revision 32.0


0.02
2 0.60 hove th IS 1 ine with 952 O.lMl 0.10 0.20 0.30 0.40 0.50 0.60 l-J.70 0.80 lJ.!m I.u)o I.rn 6
 
((J;JIFl  
0.01 1600 0 3200
)PRED, PREDlCTlD CPITICU HEAT fl IIX (ETU/llR-FT)
 
Figure 3.4-2 Measured Versus Predicted Critical Heat Flux URB2 Correlation UNIT 2
Figure 3.4-l Thermal Conductivity of U02 (Data Corrected to 95% Theoretical Density) I 2 0.60
July 1991 UFSAR Revision 32.0
 
hove th IS 1 ine with 952
 
O.lMl 0.10 0.20 0.30 0.40 0.50 0.60 l-J.70 0.80 lJ.!m I.u)o I.rn 6
((J;JIFl )PRED, PREDlCTlD CPITICU HEAT fl IIX (ETU/llR-FT)
 
Figure 3.4-2 Measured Versus Predicted Critical Heat Flux -
URB2 Correlation
 
UNIT 2 July 1991
: 0. I2
: 0. I2
: 0. IO
: 0. IO 0.011 E 0.06 O.oY 0.02 0
 
UGElbD:
0.011 UGElbD:
0 24' SfACIIll t-?uIsL 0 24" SrrclrG 24YIst 0
 
1.0 2.0 3.0 u.0 5.0 6.0 7.0 8.0 0.
0 24' SfACIIll t-?uIsL 0 24" SrrclrG 24YIst E 0.06
Figure 3.4-3 TDC Versus Reynolds Number fcx 26" 6rid Spacing UFSAR Revision 32.0
 
O.oY
 
0.02
 
0 0 1.0 2.0 3.0 u.0 5.0 6.0 7.0 8.0 0.
 
Figure 3.4-3 TDC Versus Reynolds Number fcx 26" 6rid Spacing I. IS5 1.m
 
I r
I. 166 I.209 I. 162 I. I85 l.ooo l.ooo I I I,ool Loo0 -
 
I.223 I. I70 I.238 Loo0 I.001 I.000
* 1 I. I26 I.161 I.093 I.066 0.967 I.001 I.001 1,002 I.002 I.001 1.A I.ozs 0.990 0.97s 0.823 0. we I.002 1.002 I.002 I.002 1.m 0.997
 
Figure 3.4-4 Normalized Radial Flow and Enthalpy Distribution at 4-Ft Elevation
 
UNIT 2 July 1991 1 1 F F I I T T 4 4 1.096 KEY: KEY:
0.996 1.096 -m I I r r -- -- Ad$
t-t- I I IV IV.-.- -m 0.996 Ad$ -- --
L L I I 1.026 1.026 I. I20 I. I20 1.002 0.994 1.002 0.994
/ / I I I I / /
I. I55 1.072 1.072 1. I88 1. I88 I. I55 0.991 0.998 0.991 I I I I I 4 4 0.998 0.988 0.988
 
I. 169 I. I69 I.212 I.212 I. I65 I. I65 I. I89 I. I89 0.990 0.990 0.998 0.990 0.998 0.990 0,986 1 1 I I t 0.986..
 
I. 22% I. I73 I.191 I.065 I.242 I. 22% I. I73 I.191 I.065 I.242 0.965 0,989 0.908 0.998 0.w 0.965 0*989 0.908 0.998 0.w 7 I 1 1 7 I 1 I. I29 I. I65 I.093 I.006 0.916 0.963 I. I29 I. I65 I.093 I.006 0.916 0.963 0.992 0.990 0.995 0.996 I*009 I.006 a.992 0.990 0.99s 0.996 I.009 I.006 I r I r--
 
l.02U lAzs as9 0.973 0.819 0-w l.02U I.025 as9 0.973 0.819 0.468 l.ooo I.00 I.003 I.ooy I.018 I.018 1 I
 
0.715 0.m 0.663 0.662
* FOR RAOlAL PQUER OlSTR~eKIflOH 1.022 I.019 1.021 I.019 REIR 8EGIWllRG-OF-LIFE. HOT FULL I I PMR, EQUILIBRIUI EMOR
 
CALaJlxED FA; c I. 3Y
 
Figure 3.4-5 Normalized Radial Flow and Enthalpy Distribution at 8-Ft Elevation
 
UNIT 2 July 1991 0.999 0.993 L I


I. 157 I.073 I.189 0.991 0.996 0.989
r I. 166 I.209 l.ooo l.ooo I I I.223 I. I70 Loo0 I.001
* 1 I. I26 I.161 I.001 I.001 1.A I.ozs I.002 1.002 I. IS5 1.m I
I. 162 I. I85 I,ool Loo0 I.238 I.000 I.093 I.066 1,002 I.002 0.990 0.97s I.002 I.002 0.823 1.m 0.967 I.001
: 0. we 0.997 Figure 3.4-4 Normalized Radial Flow and Enthalpy Distribution at 4-Ft Elevation UNIT 2
July 1991 UFSAR Revision 32.0


I.170 I.215 Ia 168 I.190
F F 1 1 I I T T 4 4 1.096 1.096 KEY:
KEY:
t-t-
I I IV IV
-m
-m I I r r
-- Ad$
Ad$
0.996 0.996 L L I I 1.026 1.026 I. I20 I. I20 1.002 1.002 0.994 0.994
/ /
I I I I
/ /
I. I55 I. I55 1.072 1.072
: 1. I88
: 1. I88 0.991 0.991 0.998 0.998 0.988 0.988 I I I I I
4 4 I. 169 I. I69 I.212 I.212 I. I65 I. I65 I. I89 I. I89 0.990 0.990 0,986 0.986 0.990 0.990 0.998 0.998 1 1 I I t
I. 22%
I. I73 I.191 I.065 I.242 0.965 0,989 0.908 0.998 0.w 7
I 1 1
I. I29 I. I65 I.093 I.006 0.916 0.963 0.992 0.990 0.995 0.996 I*009 I.006 I r I. 22%
I. I73 I.191 I.065 I.242 0.965 0*989 0.908 0.998 0.w 7
I 1 I. I29 I. I65 I.093 I.006 0.916 0.963 a.992 0.990 0.99s 0.996 I.009 I.006 I r--
l.02U lAzs as9 0.973 0.819 0-w l.02U I.025 as9 0.973 0.819 0.468 l.ooo I.00 I.003 I.ooy I.018 I.018 1 I 0.715 0.m 0.663 0.662 FOR RAOlAL PQUER OlSTR~eKIflOH 1.022 I.019 1.021 I.019 REIR 8EGIWllRG-OF-LIFE. HOT FULL I I
: PMR, EQUILIBRIUI EMOR CALaJlxED FA; c I. 3Y Figure 3.4-5 Normalized Radial Flow and Enthalpy Distribution at 8-Ft Elevation UNIT 2
July 1991 UFSAR Revision 32.0


0.990 0.900 0.991 0.990
0.999 0.993 L I I. 157 I.073 I.189 0.991 0.996 0.989 I.170 I.215 Ia 168 0.990 0.900 0.991 1.231 I. 173 I. 193 0.987 m90 0.989 I
I.130
: 1. I65 I.=
0.993 0.991 0.995
-r r
LO23 Lost 0.987 1.m l.mo la2 I.190 0.990 1.066 0397 I.087 0.996 0.970 I.003 o.r;l 0.m 0.640 IJl6 I.013 I.019 0.560 I.025 0.9N 0.961 I.005 I.003 01817 0.469 l.Oll 1.030 Figure 3.4-4 Nowlized Radial Flow and Enthalpy Distribution at 120Ft Elevation
- Core Exit UNIT 2 July 1991 UFSAR Revision 32.0


1.231 I. 173 I. 193 1.066 0.987 m90 0.989. 0397
0 Figure 3.4-7 Void Fraction Versus Thermodynamic Quality (H-H SAT)'(Hg-HSAT)
UFSAR Revision 32.0


I I.130 1. I65 I.= I.087 0.9N 0.961 0.993 0.991 0.995 0.996 I.005 I.003
-r r LO23 Lost 0.987 0.970 01817 0.469 1.m l.mo la2 I.003 l.Oll 1.030
o.r;l 0.m 0.640 0.560 IJl6 I.013 I.019 I.025
Figure 3.4-4 Nowlized Radial Flow and Enthalpy Distribution at 120Ft Elevation - Core Exit
UNIT 2 July 1991 0
Figure 3.4-7 Void Fraction Versus Thermodynamic Quality (H-H SAT)'(Hg-HSAT)
I II q n Ian n
I II q n Ian n
q n El Minimum DNBR Corresponding to.Design Shape for Non-Overpower/Overtemperature Events I.9
-a
--6 1
-C
-1 0
I 2
4-Axial Offset (Peroent)
Figure 3.4-8 100% Power C" r)es Evaluated at Conditions Representat of Loss of Flow:
All Shapes Evaluated WB Fjy-1.59 UFSAR Revision 32.0


q n El
0
 
/
Minimum DNBR Corresponding to.Design Shape for Non-Overpower/Overtemperature Events
L TYING I
 
lLAS1 sgurrts f 11 1LCfYD:
I.9.. 1
0 MEASUAfO ASfLn0l.r EN11 ILMPf AAilUflt I
-a --6 -C -1 0 I 2 4- -
I I
 
I 0.7 0.8 0.9 1.0 ASSEM8LY POWER ( Bh/HR II w6 1
Axial Offset (Peroent)
I. I 1.2 Figure 3.4-9 PWR Natural Circulation Test UFSAR Revision 32.0
 
Figure 3.4-8 100% Power C" r)es Evaluated at Conditions Representat of Loss of Flow: All Shapes Evaluated WB Fjy-1.59 0
 
L TYING I lLAS1 sgurrts f 11 1LCfYD:
/ 0 MEASUAfO ASfLn0l.r EN11 ILMPf AAilUflt


I I I I 0.7 0.8 0.9 1.0 I. I 1.2 ASSEM8LY POWER ( Bh/HR II w6 1
6
*bi JN-x-
3 0
g -2 LLGfItO:
ala NO.
0 U6 cl 47 0
us A
r(s 0
50 V
53 V 8 POWf I 74.0 72.9 83.9 83.7
: 83. I 99.0 0
v e t
RUY YO.
5Y 55 56 67 58 60 rowf I 99.5 83.9 SO. 6 97.5 98.9 98.3 Figure 3.4-10 Comparison of a Representative w Two-Loop Reactor Incore Thermocouple Measurements with THIN-IV Predictions I
UFSAR Revision 32.0


Figure 3.4-9 PWR Natural Circulation Test 6 LLGfItO:
LfCf8k I
ala RUY NO. POWf I YO. rowf I 0 U6 74.0 0 5Y 99.5 cl 47 72.9 55 83.9 0 us 83.9 v e 56 SO. 6 A r(s 83.7 67 97.5 0 50 83. I 58 98.9 V 53 99.0 t 60 98.3
Pow 0
* bi JN-V 8 x-3 0
26
& g -2
: 83. I 0
21 84.8 A
28 88.0 V
0 28 100.7 v
38 101.0 0
00 AV OAA OQ 00 o$
V I
I I
I I
I I
0.5 0.6 0.1 0.8 0.9 1.0 1.1
~~~JAED REM IVL A~S~HBL~ POWER ( NDRMAL~~UJ 10 1.o)
Figure 3.4-11 Comparison of a Representative 43 Three-Loop Reactor Incore Thermocouple Measurements with THING-IV Predictions 1.2 1.3 I
UFSAR Revision 32.0


Figure 3.4-10 Comparison of a Representative w Two-Loop I Reactor Incore Thermocouple Measurements with THIN-IV Predictions LfCf8k I,
A A
!!!!!! Pow 0 26 83. I -
8 0
0 21 84.8 A 28 88.0 V 0 28 100.7 v 38 101.0
0 A
0 LEGtWO:
0 MEASIJIED ATHINC-IV I
I 30 Figure 3.4-12 Hanford Subchannel Temperature Data Comparison with THINGIV UNIT 2 July 1991 UFSAR Revision 32.0


0 00
1 PRC SsuRL 2OIY PSIA MASS flOY 0.5-2.21 1061cl/,f 12-HR MD DIWtlEa O.Y22 IIICIIES RDD PIICI o-555 IICHf s lItAIL 1LlGll BY lWCHlS YLAI fLUl DIS~IIIUIIOY IYIItR Iu)D:
OUIf11 100 1.20~:
1.0 IC -
InLRHOcOUrLL LOCAIrOw Figure 3.4-13 Hanford Subcritical Temperature Data Comparison with THINC-IV UFSAR Revision 32.0


OAA OQ 00 AV V
I 89@
o$
9 IO II I2 13 IV I3 R
I I I I I I I 0.5 0.6 0.1 0.8 0.9 1.0 1.1 1.2 1.3
P H
~~~JAED REM IVL A~S~HBL~ POWER ( NDRMAL~~UJ 10 1.o)
M I.
 
K J
Figure 3.4-11 Comparison of a Representative 43 Three-Loop I Reactor Incore Thermocouple Measurements with THING-IV Predictions
H G
 
F E
0 A A A 8 0
0 C. 8 A
 
l8@
0 LEGtWO: 0 MEASIJIED ATHINC-IV
0 00 UPPER HEAO PEWffRATlOW FOR CONTROL ROOS (73) 0 UPPER HEAD PENETRATIOM FOR THERMOCWPLTS (5) 0 UIWER HEAD PENETRATION FOR FLUX THIM8l.B (58)
 
I I 30
 
Figure 3.4-12 Hanford Subchannel Temperature Data Comparison with THINGIV
 
UNIT 2 July 1991 1
 
PRC SsuRL 2OIY PSIA MASS flOY 0.5-2.21 1061cl/,f 12-HR MD DIWtlEa O.Y22 IIICIIES RDD PIICI o-555 IICHf s lItAIL 1LlGll BY lWCHlS YLAI fLUl DIS~IIIUIIOY IYIItR Iu)D: OUIf11 100 1.20~: 1.0 IC - InLRHOcOUrLL LOCAIrOw
 
Figure 3.4-13 Hanford Subcritical Temperature Data Comparison with THINC-IV R P H M I. K J H G F E 0 C. 8 A l8@
I
 
89@ 270° 9
IO II
 
I2 13 IV I3
 
00 0 UPPER HEAO PEWffRATlOW FOR CONTROL ROOS (73) 0 UPPER HEAD PENETRATIOM FOR THERMOCWPLTS (5) 0 UIWER HEAD PENETRATION FOR FLUX THIM8l.B (58)
T THERMOCWPE LOCATIONS IN THE CORE (65)
T THERMOCWPE LOCATIONS IN THE CORE (65)
 
Figure 3.4-14 Distribution of Incore Instrumentation UNIT 2
Figure 3.4-14 Distribution of Incore Instrumentation
270° July 1991 UFSAR Revision 32.0}}
 
UNIT 2 July 1991}}

Revision as of 18:03, 24 November 2024

Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 3, Figures (Unit 2)
ML24159A225
Person / Time
Site: Cook  
Issue date: 05/30/2024
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML24159A261 List: ... further results
References
AEP-NRC-2024-20
Download: ML24159A225 (1)
v • d • e


Text

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

26.0 Chapter:

3 Sheet:

1 of 1 UFSAR Figure: 3.2-1 Change

Description:

UCR-2052, Rev. 0 Unit: 2

Title:

Fuel Assembly Cross Section 17 x 17 Vantage 5 Update UFSAR Revision 32.0

UFSAR Figure: 3.2-2 Change

Description:

UCR-2116, Rev. 0 Unit: 2

Title:

Vantage 5 Fuel Assembly UFSAR Revision 32.0

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

26.0 Chapter:

3 Sheet:

1 of 1 UFSAR Figure: 3.2-3 Change

Description:

UCR-2052, Rev. 0 Unit: 2

Title:

17 X 17 Fuel Rod Assembly UFSAR Revision 32.0

Unit 2 Revision: 19.0 Change

Description:

UCR-1703 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-4 Sheet 1 of 1

Title:

D.C. Cook Unit 2 Plan View UFSAR Revision 32.0

-3 I-

?

0.C.

C3OK UNIT 2

I Tap GRID TO THIMBLE ATTACHMENT FIGURE 3.2-5 I

UFSAR Revision 32.0

iFM Ml0 GUIDE THIMBLE TUBE GUIDE THIMBLE TUBE d.-----.,

d.-----.,

-7 GRID GRID

)

i i

..-----,I..-----,I

..--w-.,

+

..--w-.,

+

!2 11%

GRID SLEEVE 4

11%

GRID SLEEVE 4

WELD WELD EXPANSiON LOBE EXPANSiON LOBE GUIDE THiMBLE

-i;BE GUIDE THiMBLE

-i;BE I

1 GRID GRID -

1

\\

\\

MID GRIO SLEEVE EXPANSiON LOBE

---fit EXPANSiON LOBE OlMtNSlONS ARE IN INCHES (MOWN&)

UFSAR Revision 32.0

Unit 2 Revision: 19.0 Change

Description:

UCR-1703 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-6 Sheet 1 of 1

Title:

D. C. Cook Unit 2 Top Nozzle to Thimble Attachment UFSAR Revision 32.0

UFSAR Figure: 3.2-6A Change

Description:

UCR-2330,. Rev. 0 Unit: 2

Title:

Top Nozzle and Top Grid* Attachment Illustration

There is a double top grid bulge configuration starting with the Unit 2 fresh fuel in Cycle 24, where a triple top grid bulge configuration was the previous configuration.

UFSAR Revision 32.0

Unit 2 Revision: 19.0 Change

Description:

UCR-1703 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-7 Sheet 1 of 1

Title:

D.C. Cook Unit 2 Guide Thimble to Bottom Nozzle Joint UFSAR Revision 32.0

UFSAR Figure: 3.2-8 Change

Description:

UCR-2221, Rev. 0 Unit: 2

Title:

Typical Core Barrel Assembly UFSAR Revision 32.0

UNIT 2 Revision: 19.1 Change

Description:

UCR-1727 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-9 Sheet 1 of 1

Title:

Upper Core Support Structure UFSAR Revision 32.0

6 I6U-2 HEAD AND VESSEL ALIGNMENT PIN LOCATION Figure 3.2-10 Plan View of Upper Core Support Structure UNIT 2

July, 1982 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 TYPICAL FULL LENGTH ROD CLUSTER CONTROL AND DRIVE ROD ASSEMBLY WITH INTERFACING COMPONENTS FSAR FIG. 3.2-11 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 FULL LENGTH ROD CLUSTER CONTROL ASSEMBLY OUTLINE FSAR FIG. 3.2-12 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 160.949 1.838 Dia.

Max.

0.362 Dia. Max.

1.470 Dia. Max.

UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 FULL LENGTH ABSORBER ROD FSAR FIG. 3.2-13 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 171.845 for groups 08, 09, & 14 151.885 for groups 11-13 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 TYPICAL BURNABLE POISON ASSEMBLY FSAR FIG. 3.2 - 15A SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

CWAE3A) ASSEMBLY 1EF. DWGS:

I A

UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 TYPICAL BURNABLE POISON ROD CROSS SECTION FSAR FIG. 3.2-16A SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 PRIMARY SOURCE ASSEMBLY FSAR FIG. 3.2-17 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 HISTORICAL UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 SECONDARY SOURCE ASSEMBLY FSAR FIG. 3.2 - 18 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 NOTE: ALL DIMENSIONS ARE IN INCHES 97.0 SECONDARY SOURCE 0.426 DIA.

0.338 DIA.

UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1243 THIMBLE PLUG ASSEMBLY FSAR FIG. 3.2-19 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 0.426 DIA.

UFSAR Revision 32.0

Title:

Full Length Control Rod Drive Mechanism Sheet 1 of 1 UFSAR Figure: 3.2-20 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Change

Description:

UCR-1836 Revision: 21.2 UNIT 2 UFSAR Revision 32.0

Revision: 21.2 Change

Description:

UCR-1836

Title:

Full Length Control Rod Drive Mechanism Schematic AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 3.2-21 Sheet 1 of 1 UNIT 2 UFSAR Revision 32.0

BEFORE LOAD TRANSFER MG IF I I

B I

LIFT COIL OFF LIFT COIL ON LIFT COIL OFF LIFT COIL ON Figure 3.2-23 AT 70' 1

AT 650' I

LOAD AFTER LOAD D &!!

MG B

B I

I LIFT COI LIFT COIL OFF IL OFF I I I I LIFT COI LIFT COIL ON L ON I

I I

I I

I LIFT COIL OFF I

I LIFT COIL ON I

I P

SG TRANSFER AT 70' I

I AT 650' I

Nominal Latch Cleal-ante at Minimum and Maximum Temper-atute UFSAR Revision 32.0

0.080 2

0.070 W

5 0.060 W

w c

g 0.050 W w Ei 0.0110 E

0.030 E

5 0.020 E

2 0.010 Y

0 0.000 LIFT COIL OFF

/

MG CLEARANCE AFTER

/

LOAD TRANSFER 0

too 200 300 ill0 TEMPERATURE (OF) 500 600 Figure 3.2-24 Control Rod D rive Mechanism Latch Cleatonce Thelma1

.Effect 300 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 Typical Axial Zoning of Uranium Enrichment and IFBA Poisoning FSAR FIG. 3.3-1 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 5"

121" 6"

6" 6"

6" 6"

132" UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 EXAMPLE LOW LEAKAGE FUEL LOADING ARRANGEMENT FSAR FIG. 3.3-2 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL PRODUCTION AND CONSUMPTION OF HIGHER ISOTOPES FSAR FIG. 3.3 - 3 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

UFSAR Revision 32.0

UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 EXAMPLE BORON CONCENTRATION OVER CYCLE LENGTH FSAR FIG. 3.3-6 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT BEGINNING-OF-LIFE UNRODDED CORE, HOT FULL POWER, NO XENON FSAR FIG. 3.3-7 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT BEGINNING-OF-LIFE UNRODDED CORE, HOT FULL POWER, EQUILIBRIUM XENON FSAR FIG. 3.3-8 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION NEAR BEGINNING-OF-LIFE GROUP D AT INSERTION LIMIT, HOT FULL POWER, EQUILIBRIUM XENON FSAR FIG. 3.3-9 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION AT MIDDLE-OF-LIFE UNRODDED CORE, HOT FULL POWER, EQUILIBRIUM XENON.

FSAR FIG. 3.3-10 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 AVERAGE POWER UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL NORMALIZED POWER DENSITY DISTRIBUTION NEAR END-OF-LIFE UNRODDED CORE, HOT FULL POWER, EQUILIBRIUM XENON.

FSAR FIG. 3.3-11 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL RODWISE POWER DISTRIBUTION IN A TYPICAL ASSEMBLY (ASSEMBLY G-12) NEAR BEGINNING-OF-LIFE, HOT FULL POWER, EQUILIBRIUM XENON, UNRODDED CORE.

FSAR FIG. 3.3-12 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL RODWISE POWER DISTRIBUTION IN A TYPICAL ASSEMBLY (ASSEMBLY G-12) NEAR END-OF-LIFE, HOT FULL POWER EQUILIBRIUM XENON, UNRODDED CORE.

FSAR FIG. 3.3-13 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

8 d tl3fiOd 03ZllVWMON UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 EXAMPLE AXIAL POWER SHAPES OCCURRING AT MOL FSAR FIG. 3.3-15 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 P - 1 D - 0.05 AO - -2.132%

P - 1 D - 0.130 AO - -7.082%

UFSAR Revision 32.0

UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 MAXIMUM F Q (Z) x POWER VERSUS AXIAL HEIGHT (Z) DURING NORMAL OPERATION FSAR FIG. 3.3-20 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 2.159 2.335 2.335 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL PEAK LINEAR POWER DURING CONTROL ROD MALFUNCTION OVERPOWER TRANSIENTS FSAR FIG. 3.3-21 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 TYPICAL PEAK LINEAR POWER DURING BORATION/DILUTION OVERPOWER TRANSIENTS FSAR FIG. 3.3-22 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 ILLUSTRATION OF A COMPARISON BETWEEN CALCULATED AND MEASURED RELATIVE FUEL ASSEMBLY POWER DISTRIBUTION FSAR FIG. 3.3-23 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 COMPARISON OF TYPICAL CALCULATED AND MEASURED AXIAL SHAPE FSAR FIG. 3.3-24 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 EXAMPLE DOPPLER TEMPERATURE COEFFICIENT AT BOL AND EOL FSAR FIG. 3.3-26 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 EXAMPLE DOPPLER ONLY POWER COEFFICIENT AT BOL AND EOL FSAR FIG. 3.3-27 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

I-I 8OL LJ w-a.

EOL Figure 3.3-28 Example Doppler Only Power Defect

- BOL, EOL UNIT 2 July 1991 UFSAR Revision 32.0

UFSAR Revision 32.0

Figure 3s.3.30

  1. ourmr TWERAllJRt (F)

Example Moderator Temperature Coefficient EOL UNIT 2 July 199b UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 EXAMPLE MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF BORON CONCENTRATION - BOL, NO RODS FSAR FIG. 3.3-31 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

16.4 REVISED PER 99-UFSAR-1242 EXAMPLE HOT FULL POWER MODERATOR TEMPERATURE COEFFICIENT (AT THE CRITICAL BORON CONCENTRATION)

VERSUS BURNUP FSAR FIG. 3.3-32 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

UNIT 2 UFSAR Revision 32.0

Figure 3.3-33 Example Total Power Coefficient at BOL and EOL UNIT 2 July 1991 UFSAR Revision 32.0

Figure 3.3-34 Example Total Power Defect at BOL and EOL UNIT 2

July 1991 UFSAR Revision 32.0

1 2

3 4

3 6

7 9GO a

9 10 1 1 12 17

?J 1s

?

I I

33 I

/

/ j j

it/

joi j*i

/q

/*I j3/

11 i

/ sa I I

1 I I

/

I

/ / i sa i j

j

/l(lj dl*

c

!/I8

/

I so I

I I

1 0

/

SC i

fA

/

I SA I

1 0

0

/

I I

SC Iso/

I

]

SA SWtgoUN 8ANK fiWtD@UW

  1. AlUK fnutoowru HANK CaNtllOC 8ANK CoNtROt.

8ANK CONTROL OANK CONTROL 8ANK 00 FUNCtrON i:

SC 6

so c

0 NUM8Ei)

OF 800 CLiJSfCRS 8

464 4

a a

9 Figure 3.3-35 Rod Cluster Control Assembly Pattern July 1991 UNIT 2 UFSAR Revision 32.0

CuaVL 1

2 1650 7700 32.1 27.2

-O.OYb

-0.011)

I I

I I

I I

I I

I I

I I

I I

I I

I 0

4 8

12 16 20 2l 28 32 36 40 UU l8 52 56 60 64 68 72 71wL (HOURS)

Figure 3.3-36 Axial Offset Versus Time PWR Core With a 12-Ft Height and 121 Assemblies I

UFSAR Revision 32.0

0

- a

-a 3

0 3

B i

0 Y

8 12 16 20 2u 26 32 36 110 uu UB 52

!j6 60

(

Figure 3.3-37 IN Xenon Test Thermocouple

Response

Quadrant Tilt Difference Versus Time UFSAR Revision 32.0

-60.0

-50.0 CI P

c 1 30.0 6 5 -30.0 L 3 3 -20.0 ii!

ii

-10.0 0

ii c0n1a01 UYU wnffrsrrlow uouow CoHrLaSAllOn tx?trrnfrr CALCUl AI Ion 0

YO 50 60 PERCLrl Of FULL POWER Figure 3.3-38 Calculated and Measured Doppler Defect and Coefficients at BOL Two-Loop

Plant, 121 Assemblies, LZ-Ft Core

-2uOo

-2200

-2000

-UOO

-200 0

UFSAR Revision 32.0

0.07 0.06 c

i z

0.05 t-

- Y g

0.w w

E z

B 0

0.03

-l z

iii b-0.02 0.01 0

LfGfYD:

PfRCLYI tEICLN 1 lYtDlfllCA1 INCDUfIICM DfNSI IY DLltllY 0

GYllAWDfl 96.4 0

wOUA80 A Gulvlw 96.0 l AS&U10 95.0 LUClS A DffM 96.6 0

DDBCILY 93.4 0

DAYIt fl Al 96.5 A

SIDIA 92.2

+

ffllll 97.9 l

AD. WI at.4 0

YOGI f1 Al 97.0 A

IIISHIJIMA 95.0 v

rnUGCl 93.7 v

WffLfl 6 AlNSCOUGN 97.0 SEE RfffIfICfS fOR INfUMAL-HYDAAUllC SECTtOY A

1600 Figure 3.4-l Thermal Conductivity of U02 (Data Corrected to 95% Theoretical Density) 3200 I

UFSAR Revision 32.0

2 0.60 hove th IS 1 ine with 952 O.lMl 0.10 0.20 0.30 0.40 0.50 0.60 l-J.70 0.80 lJ.!m I.u)o I.rn 6

((J;JIFl

)PRED, PREDlCTlD CPITICU HEAT fl IIX (ETU/llR-FT)

Figure 3.4-2 Measured Versus Predicted Critical Heat Flux URB2 Correlation UNIT 2

July 1991 UFSAR Revision 32.0

0. I2
0. IO 0.011 E 0.06 O.oY 0.02 0

UGElbD:

0 24' SfACIIll t-?uIsL 0 24" SrrclrG 24YIst 0

1.0 2.0 3.0 u.0 5.0 6.0 7.0 8.0 0.

Figure 3.4-3 TDC Versus Reynolds Number fcx 26" 6rid Spacing UFSAR Revision 32.0

r I. 166 I.209 l.ooo l.ooo I I I.223 I. I70 Loo0 I.001

  • 1 I. I26 I.161 I.001 I.001 1.A I.ozs I.002 1.002 I. IS5 1.m I

I. 162 I. I85 I,ool Loo0 I.238 I.000 I.093 I.066 1,002 I.002 0.990 0.97s I.002 I.002 0.823 1.m 0.967 I.001

0. we 0.997 Figure 3.4-4 Normalized Radial Flow and Enthalpy Distribution at 4-Ft Elevation UNIT 2

July 1991 UFSAR Revision 32.0

F F 1 1 I I T T 4 4 1.096 1.096 KEY:

KEY:

t-t-

I I IV IV

-m

-m I I r r

-- Ad$

Ad$

0.996 0.996 L L I I 1.026 1.026 I. I20 I. I20 1.002 1.002 0.994 0.994

/ /

I I I I

/ /

I. I55 I. I55 1.072 1.072

1. I88
1. I88 0.991 0.991 0.998 0.998 0.988 0.988 I I I I I

4 4 I. 169 I. I69 I.212 I.212 I. I65 I. I65 I. I89 I. I89 0.990 0.990 0,986 0.986 0.990 0.990 0.998 0.998 1 1 I I t

I. 22%

I. I73 I.191 I.065 I.242 0.965 0,989 0.908 0.998 0.w 7

I 1 1

I. I29 I. I65 I.093 I.006 0.916 0.963 0.992 0.990 0.995 0.996 I*009 I.006 I r I. 22%

I. I73 I.191 I.065 I.242 0.965 0*989 0.908 0.998 0.w 7

I 1 I. I29 I. I65 I.093 I.006 0.916 0.963 a.992 0.990 0.99s 0.996 I.009 I.006 I r--

l.02U lAzs as9 0.973 0.819 0-w l.02U I.025 as9 0.973 0.819 0.468 l.ooo I.00 I.003 I.ooy I.018 I.018 1 I 0.715 0.m 0.663 0.662 FOR RAOlAL PQUER OlSTR~eKIflOH 1.022 I.019 1.021 I.019 REIR 8EGIWllRG-OF-LIFE. HOT FULL I I

PMR, EQUILIBRIUI EMOR CALaJlxED FA; c I. 3Y Figure 3.4-5 Normalized Radial Flow and Enthalpy Distribution at 8-Ft Elevation UNIT 2

July 1991 UFSAR Revision 32.0

0.999 0.993 L I I. 157 I.073 I.189 0.991 0.996 0.989 I.170 I.215 Ia 168 0.990 0.900 0.991 1.231 I. 173 I. 193 0.987 m90 0.989 I

I.130

1. I65 I.=

0.993 0.991 0.995

-r r

LO23 Lost 0.987 1.m l.mo la2 I.190 0.990 1.066 0397 I.087 0.996 0.970 I.003 o.r;l 0.m 0.640 IJl6 I.013 I.019 0.560 I.025 0.9N 0.961 I.005 I.003 01817 0.469 l.Oll 1.030 Figure 3.4-4 Nowlized Radial Flow and Enthalpy Distribution at 120Ft Elevation

- Core Exit UNIT 2 July 1991 UFSAR Revision 32.0

0 Figure 3.4-7 Void Fraction Versus Thermodynamic Quality (H-H SAT)'(Hg-HSAT)

UFSAR Revision 32.0

I II q n Ian n

q n El Minimum DNBR Corresponding to.Design Shape for Non-Overpower/Overtemperature Events I.9

-a

--6 1

-C

-1 0

I 2

4-Axial Offset (Peroent)

Figure 3.4-8 100% Power C" r)es Evaluated at Conditions Representat of Loss of Flow:

All Shapes Evaluated WB Fjy-1.59 UFSAR Revision 32.0

0

/

L TYING I

lLAS1 sgurrts f 11 1LCfYD:

0 MEASUAfO ASfLn0l.r EN11 ILMPf AAilUflt I

I I

I 0.7 0.8 0.9 1.0 ASSEM8LY POWER ( Bh/HR II w6 1

I. I 1.2 Figure 3.4-9 PWR Natural Circulation Test UFSAR Revision 32.0

6

  • bi JN-x-

3 0

g -2 LLGfItO:

ala NO.

0 U6 cl 47 0

us A

r(s 0

50 V

53 V 8 POWf I 74.0 72.9 83.9 83.7

83. I 99.0 0

v e t

RUY YO.

5Y 55 56 67 58 60 rowf I 99.5 83.9 SO. 6 97.5 98.9 98.3 Figure 3.4-10 Comparison of a Representative w Two-Loop Reactor Incore Thermocouple Measurements with THIN-IV Predictions I

UFSAR Revision 32.0

LfCf8k I

Pow 0

26

83. I 0

21 84.8 A

28 88.0 V

0 28 100.7 v

38 101.0 0

00 AV OAA OQ 00 o$

V I

I I

I I

I I

0.5 0.6 0.1 0.8 0.9 1.0 1.1

~~~JAED REM IVL A~S~HBL~ POWER ( NDRMAL~~UJ 10 1.o)

Figure 3.4-11 Comparison of a Representative 43 Three-Loop Reactor Incore Thermocouple Measurements with THING-IV Predictions 1.2 1.3 I

UFSAR Revision 32.0

A A

8 0

0 A

0 LEGtWO:

0 MEASIJIED ATHINC-IV I

I 30 Figure 3.4-12 Hanford Subchannel Temperature Data Comparison with THINGIV UNIT 2 July 1991 UFSAR Revision 32.0

1 PRC SsuRL 2OIY PSIA MASS flOY 0.5-2.21 1061cl/,f 12-HR MD DIWtlEa O.Y22 IIICIIES RDD PIICI o-555 IICHf s lItAIL 1LlGll BY lWCHlS YLAI fLUl DIS~IIIUIIOY IYIItR Iu)D:

OUIf11 100 1.20~:

1.0 IC -

InLRHOcOUrLL LOCAIrOw Figure 3.4-13 Hanford Subcritical Temperature Data Comparison with THINC-IV UFSAR Revision 32.0

I 89@

9 IO II I2 13 IV I3 R

P H

M I.

K J

H G

F E

0 C. 8 A

l8@

0 00 UPPER HEAO PEWffRATlOW FOR CONTROL ROOS (73) 0 UPPER HEAD PENETRATIOM FOR THERMOCWPLTS (5) 0 UIWER HEAD PENETRATION FOR FLUX THIM8l.B (58)

T THERMOCWPE LOCATIONS IN THE CORE (65)

Figure 3.4-14 Distribution of Incore Instrumentation UNIT 2

270° July 1991 UFSAR Revision 32.0

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