ML24159A225
| 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:
|
| References | |
| AEP-NRC-2024-20 | |
| Download: ML24159A225 (1) | |
Text
INDIANA AND MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Chapter: 3 UPDATED FINAL SAFETY ANALYSIS REPORT 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 Figure: 3.2-2 Change
Description:
UCR-2116, Rev. 0 Unit:2
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
UFSAR Figure: 3.2-3 Change
Description:
UCR-2052, Rev. 0 Unit:2
Title:
17 X 17 Fuel Rod Assembly Revision: 19.0 Change
Description:
UCR-1703
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
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 -
1
\\
\\..
EXPANSiON LOBE EXPANSiON LOBE
---fit
OlMtNSlONS ARE IN INCHES (MOWN&)
Revision: 19.0 Change
Description:
UCR-1703
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
Unit 2 UFSAR Revision 32.0
UFSAR Figure: 3.2-6A Change
Description:
2 UCR-2330,. Rev. 0 Unit:
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.
Revision: 19.0 Change
Description:
UCR-1703
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
Unit 2 UFSAR Revision 32.0
UFSAR Figure: 3.2-8 Change
Description:
UCR-2221, Rev. 0 Unit: 2
Title:
Typical Core Barrel Assembly 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: 3.2-9 Sheet 1 of 1
UNIT 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 UNIT 2
16.4 REVISED PER 99-UFSAR-1243
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
16.4 REVISED PER 99-UFSAR-1243
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
16.4 REVISED PER 99-UFSAR-1243
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
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:
I A UNIT 2
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:
UCR-1836
AMERICAN ELECTRIC POWER
Title:
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:
UCR-1836
AMERICAN ELECTRIC POWER
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
UNIT 2 BEFORE LOAD TRANSFER AFTER LOAD LOAD TRANSFER D &!!
MG MG IF I I AT 70' 1 AT 70' I
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
AT 650' I I AT 650' I
LIFT COIL OFF
LIFT COIL ON I I LIFT COIL ON I I
P
Figure 3.2-23 Nominal Latch Cleal-ante at Minimum and Maximum Temper-atute 0.080
2 0.070 -
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"
6" 6"
UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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
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
16.4 REVISED PER 99-UFSAR-1242
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
UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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
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
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
16.4 REVISED PER 99-UFSAR-1242
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
UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-10 SH 1 of 1 UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-11 SH 1 of 1 UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-12 SH 1 of 1 UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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.
BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 3.3-13 SH 1 of 1
P - 1 P - 1 D - 0.130 D - 0.05 AO - -7.082%
AO - -2.132%
UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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
2.335 2.335
2.159
UNIT 2
16.4 REVISED PER 99-UFSAR-1242
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
16.4 REVISED PER 99-UFSAR-1242
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
16.4 REVISED PER 99-UFSAR-1242
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
16.4 REVISED PER 99-UFSAR-1242
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
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
iii b-
0.02
0.01 1600 0 3200
Figure 3.4-l Thermal Conductivity of U02 (Data Corrected to 95% Theoretical Density) I 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
- 0. I2
- 0. IO
0.011 UGElbD:
0 24' SfACIIll t-?uIsL 0 24" SrrclrG 24YIst E 0.06
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
I.170 I.215 Ia 168 I.190
0.990 0.900 0.991 0.990
1.231 I. 173 I. 193 1.066 0.987 m90 0.989. 0397
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
q n El
Minimum DNBR Corresponding to.Design Shape for Non-Overpower/Overtemperature Events
I.9.. 1
-a --6 -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 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
Figure 3.4-9 PWR Natural Circulation Test 6 LLGfItO:
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
- bi JN-V 8 x-3 0
& g -2
Figure 3.4-10 Comparison of a Representative w Two-Loop I Reactor Incore Thermocouple Measurements with THIN-IV Predictions 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
OAA OQ 00 AV V
o$
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
~~~JAED REM IVL A~S~HBL~ POWER ( NDRMAL~~UJ 10 1.o)
Figure 3.4-11 Comparison of a Representative 43 Three-Loop I Reactor Incore Thermocouple Measurements with THING-IV Predictions
0 A A A 8 0
0 LEGtWO: 0 MEASIJIED ATHINC-IV
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)
Figure 3.4-14 Distribution of Incore Instrumentation
UNIT 2 July 1991