Text

6 to Updated Final Safety Analysis Report, Chapter 4, Reactor, Figures
	ML18249A140
Person / Time
Site:	Brunswick
Issue date:	08/13/2018
From:	; Duke Energy Progress
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML18249A165	List: ML18249A126; ML18249A128; ML18249A129; ML18249A130; ML18249A131; ML18249A133; ML18249A134; ML18249A135; ML18249A140; ML18249A142; ML18249A143; ML18249A145; ML18249A146; ML18249A147; ML18249A148; ML18249A149; ML18249A150; ML18249A151; ML18249A153; ML18249A154; ML18249A155; ML18249A159; RA-18-0004, Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 43; RA-18-0131, Technical Requirements Manual, Revision 66;
References
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

26 Chapter:

4 Page:

1 of 2 LIST OF FIGURES FIGURE NUMBER TITLE 4-1 FUEL ASSEMBLY (ISOMETRIC) 4-2 TYPICAL GE BWR FUEL ASSEMBLY 4-3 SCHEMATIC CROSS SECTION OF LOWER TIE PLATE SHOWING CHANNEL/LOWER TIE PLATE (FINGER SPRING) FLOW PATH 4-4 TYPICAL CORE CELL 4-5 CHANNEL FASTENER ASSEMBLY 4-6 UNIT 2 INITIAL CORE - CORE LOADING MAP 4-7 FUEL ASSEMBLY ROD ENRICHMENTS 4-8 7X7 FUEL ASSEMBLY 4-9 CALCULATED RANGE OF HOT UNCONTROLLED MAXIMUM LOCAL PEAKING VERSUS EXPOSURE 4-10 DOPPLER COEFFICIENT OF REACTIVITY 4-11 DOPPLER COEFFICIENT AS FUNCTION OF FUEL EXPOSURE 4-12 CORE AVERAGE DOPPLER DEFECT VERSUS CORE POWER LEVEL 4-13 DOPPLER DEFECT VERSUS FUEL TEMPERATURE 4-14 DOPPLER COEFFICIENT OF REACTIVITY VERSUS MODERATOR CONDITION OF AVERAGE FUEL TEMPERATURE AT BOL 4-15 DOPPLER REACTIVITY COEFFICIENT AS A FUNCTION OF FUEL EXPOSURE AND AVERAGE FUEL TEMPERATURE AT AN AVERAGE VOID CONTENT OF 40%

4-16 DOPPLER REACTIVITY AS A FUNCTION OF CORE AVERAGE VOID FRACTION AND AVERAGE FUEL TEMPERATURE AT BOL AND EOC 4-17 VOID COEFFICIENTS AT BEGINNING OF CYCLE 1 AND AT A CORE AVERAGE EXPOSURE OF 7000 MWD/T 4-18 MODERATOR VOID REACTIVITY COEFFICIENT AT BOL AND AT A CORE AVERAGE EXPOSURE OF 10 GWD/T 4-19 BRUNSWICK UNIT 1 COLD SHUTDOWN REACTIVITY 4-20 FRACTIONAL CONTROL ROD DENSITY VERSUS CORE AVERAGE MODERATOR DENSITY FOR A CRITICAL REACTOR AT BOL 4-21 MAXIMUM ROD WORTH VERSUS MODERATOR DENSITY 4-22 MAXIMUM ROD WORTH VERSUS POWER LEVEL 4-23 EFFECTIVE CORE EIGENVALUE AS A FUNCTION OF AVERAGE CORE EXPOSURE (MOST REACTIVE ROD WITHDRAWN) 4-24 SCRAM REACTIVITY BEGINNING AND END OF FIRST CYCLE FOR HOT OPERATING CONDITIONS 4-25 XENON REACTIVITY BUILDUP AFTER SHUTDOWN AND BURNOUT ON RETURN TO FULL POWER FROM MAXIMUM SHUTDOWN XENON BUILDUP AT BEGINNING OF LIFE 4-26 RELATIVE XENON STABILITY WITH NO FLUX FLATTENING 4-27 EFFECT OF POWER DENSITY ON AXIAL XENON STABILITY INCLUDING VOID TRANSPORT 4-28 AZIMUTHAL XENON STABILITY 4-29 POWER/FLOW OPERATING MAP FOR POWER UPRATE 4-30 FUEL TEMPERATURE VERSUS HEAT FLUX - BOL 3 W/O GD2O3 4-31 FUEL TEMPERATURE VERSUS HEAT FLUX - 5 YEARS 3 W/O GD2O3 4-32 CLAD TEMPERATURE VERSUS HEAT FLUX - BOL 3 W/O GD2O3

UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

26 Chapter:

4 Page:

2 of 2 LIST OF FIGURES FIGURE NUMBER TITLE 4-33 CLAD TEMPERATURE VERSUS HEAT FLUX - 5 YEARS 3 W/O GD2O3 4-34 FUEL TEMPERATURE VERSUS HEAT FLUX - BOL UO2 4-35 FUEL TEMPERATURE VERSUS HEAT FLUX - 5 YEARS UO2 4-36 CLAD TEMPERATURE VERSUS HEAT FLUX - BOL UO2 4-37 CLAD TEMPERATURE VERSUS HEAT FLUX - 5 YEARS UO2 4-38 FUEL ASSEMBLY INITIAL ENRICHMENT DISTRIBUTION 2.1 AVERAGE ENRICHMENT 4-39 LOCAL POWER FACTORS 0 MWD/T 40% VOIDS 4-40 LOCAL POWER FACTORS 10,000 MWD/T 40% VOIDS 4-41 GROSS PEAKING FACTOR AS A FUNCTION OF EXPOSURE BRUNSWICK 1 4-42 DURALIFE - 230 CONTROL ROD 4-43 ABB CR82M-1 CONTROL ROD 4-44 WESTINGHOUSE ABB CR99 CONTROL ROD

UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

24 Figure:

4-1 Page:

1 of 1 FUEL ASSEMBLY (ISOMETRIC)

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

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4-2 Page:

1 of 1 TYPICAL GE BWR FUEL ASSEMBLY

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

24 Figure:

4-3 Page:

1 of 1 SCHEMATIC CROSS SECTION OF LOWER TIE PLATE SHOWING CHANNEL/LOWER TIE PLATE (FINGER SPRING) FLOW PATH

( ~ DUKE ENERGY CHANNEL FINGER SPRING LOWER TIE PLATE -CHANNEL FLOW PATH LOWER TIE PL.ATE

UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

24 Figure:

4-4 Page:

1 of 1 TYPICAL CORE CELL

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ENERGY.

CONTROL ROD

UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

24 Figure:

4-5 Page:

1 of 1 CHANNEL FASTENER ASSEMBLY

UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

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1 of 1 UNIT 2 INITIAL CORE - CORE LOADING MAP 41

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

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1 of 1 7X7 FUEL ASSEMBLY

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

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1 of 1 CALCULATED RANGE OF HOT UNCONTROLLED MAXIMUM LOCAL PEAKING VERSUS EXPOSURE

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

24 Figure:

4-10 Page:

1 of 1 DOPPLER COEFFICIENT OF REACTIVITY

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

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4-11 Page:

1 of 1 DOPPLER COEFFICIENT AS FUNCTION OF FUEL EXPOSURE

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:

24 Figure:

4-18 Page:

1 of 1 MODERATOR VOID REACTIVITY COEFFICIENT AT BOL AND AT A CORE AVERAGE EXPOSURE OF 10 GWD/T

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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-19 Page:
1 of 1 BRUNSWICK UNIT 1 COLD SHUTDOWN REACTIVITY l&J >...
0 l&J la.
la.
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( ~ DUKE ENERGY o.se----------------......... -.-----......... --.-........ -----------
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-20 Page:
1 of 1 FRACTIONAL CONTROL ROD DENSITY VERSUS CORE AVERAGE MODERATOR DENSITY FOR A CRITICAL REACTOR AT BOL
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-21 Page:
1 of 1 MAXIMUM ROD WORTH VERSUS MODERATOR DENSITY
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WORST IITHDRAWABLE RODS ALLOWED FOR NO~AL PATTERNS' 0!12 0.88 0.84 0.80 076
0. 72 0.68 IIIODERATOR DENSITY, p /cal
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-22 Page:
1 of 1 MAXIMUM ROD WORTH VERSUS POWER LEVEL
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er:;
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0 0.2 0.4 0.6 0.8 1.0 FRACTION OF RATED POWER
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-23 Page:
1 of 1 EFFECTIVE CORE EIGENVALUE AS A FUNCTION OF AVERAGE CORE EXPOSURE (MOST REACTIVE ROD WITHDRAWN)
( ~ DUKE ENERGY
.960
.952 \\;V
.944
~.936
~
.928
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. 912
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3 4
5 6
7 8
9 10 Average Core Exposure, (GWD/T)
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-24 Page:
1 of 1 SCRAM REACTIVITY BEGINNING AND END OF FIRST CYCLE FOR HOT OPERATING CONDITIONS
II
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( ~ DUKE ENERGY
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FRACTION OF AVERAGE SCRAM CORE FULLY INSERTION TIME
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0 0.2 5
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20 0.90 50 2.0 90 3.5
-a.1'2
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Measured from time of de-energization of scram solenoid
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-25 Page:
1 of 1 XENON REACTIVITY BUILDUP AFTER SHUTDOWN AND BURNOUT ON RETURN TO FULL POWER FROM MAXIMUM SHUTDOWN XENON BUILDUP AT BEGINNING OF LIFE
( ~ DUKE ENERGY
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-26 Page:
1 of 1 RELATIVE XENON STABILITY WITH NO FLUX FLATTENING
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-27 Page:
1 of 1 EFFECT OF POWER DENSITY ON AXIAL XENON STABILITY INCLUDING VOID TRANSPORT
( ~ DUKE ENERGY
-0.02
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_._2 _____
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1
.... o----J THERMAL FLUX {n/cm2-sec) x 10-13
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-28 Page:
1 of 1 AZIMUTHAL XENON STABILITY
( ~ DUKE ENERGY
~
ii:
0.05 0.04
<l 0.03 li'-----L--""'----------....L--"""'-----iC.--......... --""-------':..........f 3::
.>C
St 0.02 0.01 0
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-29 Page:
1 of 1 POWER/FLOW OPERATING MAP FOR POWER UPRATE 0
10 20 30 40 50 60 70 80 90 100 110 120 0
10 20 30 40 50 60 70 80 90 100 110 120 C ore Flow (% )
Uprated Thermal Power (%)A 0
500 1000 1500 2000 2500 3000 3500 0
10 20 30 40 50 60 70 80 90 C ore Flow (M lb/h r)
Thermal Power (MWt)
IC F M E L L L A U pper B oundary 100% O L T P 108% O L T P M inim um Pow er L ine Jet Pum p and R ecirc Pum p C avitation Protection 80% O L T P 60% O L T P 100 % LP U Pow er = 2923 MWt 100 % CL TP = 2558 MWt 100 % OL TP = 2436 MWt 100 % Co re Fl ow = 77.0 Mlb/h r T his map d erive d fr om an alyt ical metho ds A: Nat ural Circu lati on B: 28% Mini mum P ump Speed C: 53. 3% Po wer/ 36.1 % Flo w D: 100. 0% Po wer/ 99.0 % Flo w E: 100. 0% Po wer/1 00.0 % Flo w F: 100. 0% Po wer/1 04.5 % Flo w G: 87. 5% Po wer/1 04.5 % Flo w H: 83. 3% Po wer/1 05.0 % Flo w I: 58. 4% Po wer/1 10.0 % Flo w J: 31. 7% Po wer/1 10.0 % Flo w K: 20. 0% Po wer/ 99.0 % Flo w L: 20. 0% Po wer/ 35.9 % Flo w A
B K
L D E C
J I
F 2923 M W t G 2558 M W t H 2436 M W t
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-30 Page:
1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - BOL 3 W/O GD2O3 la..
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-31 Page:
1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - 5 YEARS 3 W/O GD2O3
( ~ DUKE ENERGY 5
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-32 Page:
1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - BOL 3 W/O GD2O3
( ~ DUKE ENERGY 1000.------,-------------------------
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-33 Page:
1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - 5 YEARS 3 W/O GD2O3
rooc, 900
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-34 Page:
1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - BOL UO2
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-35 Page:
1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - 5 YEARS UO2 5
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-36 Page:
1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - BOL UO2
( ~ DUKE ENERGY 1000,-------------------------------.-.
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-37 Page:
1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - 5 YEARS UO2 1000 9oa
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UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-38 Page:
1 of 1 FUEL ASSEMBLY INITIAL ENRICHMENT DISTRIBUTION 2.1 AVERAGE ENRICHMENT I
r.. DUKE I
~ EN~ER::G~Y_JL__ __
wt%
NO.
ROD TYPE 1
38 2.35 2
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4 1
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-39 Page:
1 of 1 LOCAL POWER FACTORS 0 MWD/T 40% VOIDS
( ~ DUKE ENERGY 1.101 2
1.148 3
1.037 4
1.175 5
1.136 6
1.150 7
1.002 8
1.124 2
1.148 1.153 1.D11 1.087 1.029 1.029 1.141 1.138 3
1.037 1.011 1.007 0.888 0.833 0.407 0.967 1.010 4
1.175 1.087 Q.886 0.~
0.803 0.825 0.933
1.127 PEAK* 1.175 ROC (1, 4) 5 8
7 8
1.135 1.150 1.002 1.124 1.029 1.029 1.141 1.136 D.833 0.407 0.987 t.010 0.803 0.825 0.933 1.127
o.
0.894 0.963 1.120 0.894 0.926 0.995 1.162 0.963 0.996 1.075 1.05S 1.120 1.162 1.056 0.988
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-40 Page:
1 of 1 LOCAL POWER FACTORS 10,000 MWD/T 40% VOIDS
( ~ DUKE ENERGY 2
1,091 1.092 2
1.092 1.073 3
0.992 0.963 4
1.088 1.027 5
1.064 1.001 e
1.080 1.019 7
1.013 1.085 8
1.088 1.097 3
0.992 0.963 1.017 0.948 0.927 0.933 t.007 a.an 4
5 1.088 1.064 1.027 1.001 0.948 0.927 0.907 0.906 0.905
0.
0.896 0.900 0.943 0.927 1.050 1.028 PEAK* 1.097 ROD (2,81 8
7 8
1.080 t.013 1.088 1.019 1.086 1.097 0.933 1.007 0.977 0.888 0.943 1.060 0.900 0.927 t.028 0.887 0.944 1.051 0.944 1.009 a.en 1.051 o.sn 0.990
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-41 Page:
1 of 1 GROSS PEAKING FACTOR AS A FUNCTION OF EXPOSURE BRUNSWICK 1
( ~ DUKE ENERGY a:
0 t; c(
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1.9 1.8
<.:I 1.7
~
~
c(
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~ 1.6 1.5 0
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2.0 3.0 4.0
. 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 EXPSOURE (GWD/Tl
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
4-42 Page:
1 of 1 DURALIFE - 230 CONTROL ROD
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ML18249A140

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