ML24159A225
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
- 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
- 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