ML18250A017
| ML18250A017 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/11/2016 |
| From: | Duke Energy Progress |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18250A015 | List: |
| References | |
| BSEP 16-0069 | |
| Download: ML18250A017 (46) | |
Text
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
25 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ROD WORTH VERSUS POWER LEVEL 4-23 EFFECTIVE CORE EIGENVALUE AS A FUNCTION OF AVERAGE CORE EXPOSURE (MOST REACTIVE ROD WITHDRAWN) 4-24 SCRAM REACTIVITY BEGINNING AND END OF FIRST CYCLE FOR HOT OPERATING CONDITIONS 4-25 XENON REACTIVITY BUILDUP AFTER SHUTDOWN AND BURNOUT ON RETURN TO FULL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
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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:
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4-1 Page:
1 of 1 FUEL ASSEMBLY (ISOMETRIC)
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4-2 Page:
1 of 1 TYPICAL GE BWR FUEL ASSEMBLY
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
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1 of 1 SCHEMATIC CROSS SECTION OF LOWER TIE PLATE SHOWING CHANNEL/LOWER TIE PLATE (FINGER SPRING) FLOW PATH
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1 of 1 TYPICAL CORE CELL
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1 of 1 CHANNEL FASTENER ASSEMBLY
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1 of 1 UNIT 2 INITIAL CORE - CORE LOADING MAP
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24 Figure:
4-7 Page:
1 of 1 FUEL ASSEMBLY ROD ENRICHMENTS
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24 Figure:
4-8 Page:
1 of 1 7X7 FUEL ASSEMBLY
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24 Figure:
4-9 Page:
1 of 1 CALCULATED RANGE OF HOT UNCONTROLLED MAXIMUM LOCAL PEAKING VERSUS EXPOSURE
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24 Figure:
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1 of 1 DOPPLER COEFFICIENT OF REACTIVITY
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1 of 1 DOPPLER COEFFICIENT AS FUNCTION OF FUEL EXPOSURE
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1 of 1 CORE AVERAGE DOPPLER DEFECT VERSUS CORE POWER LEVEL
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1 of 1 DOPPLER DEFECT VERSUS FUEL TEMPERATURE
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1 of 1 DOPPLER COEFFICIENT OF REACTIVITY VERSUS MODERATOR CONDITION OF AVERAGE FUEL TEMPERATURE AT BOL
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1 of 1 DOPPLER REACTIVITY COEFFICIENT AS A FUNCTION OF FUEL EXPOSURE AND AVERAGE FUEL TEMPERATURE AT AN AVERAGE VOID CONTENT OF 40%
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1 of 1 DOPPLER REACTIVITY AS A FUNCTION OF CORE AVERAGE VOID FRACTION AND AVERAGE FUEL TEMPERATURE AT BOL AND EOC
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1 of 1 VOID COEFFICIENTS AT BEGINNING OF CYCLE 1 AND AT A CORE AVERAGE EXPOSURE OF 7000 MWD/T
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1 of 1 MODERATOR VOID REACTIVITY COEFFICIENT AT BOL AND AT A CORE AVERAGE EXPOSURE OF 10 GWD/T
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1 of 1 BRUNSWICK UNIT 1 COLD SHUTDOWN REACTIVITY
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1 of 1 FRACTIONAL CONTROL ROD DENSITY VERSUS CORE AVERAGE MODERATOR DENSITY FOR A CRITICAL REACTOR AT BOL
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1 of 1 MAXIMUM ROD WORTH VERSUS MODERATOR DENSITY
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1 of 1 MAXIMUM ROD WORTH VERSUS POWER LEVEL
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1 of 1 EFFECTIVE CORE EIGENVALUE AS A FUNCTION OF AVERAGE CORE EXPOSURE (MOST REACTIVE ROD WITHDRAWN)
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1 of 1 SCRAM REACTIVITY BEGINNING AND END OF FIRST CYCLE FOR HOT OPERATING CONDITIONS
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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
UPDATED FSAR REACTOR CHAPTER 4 FIGURES Revision:
24 Figure:
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1 of 1 RELATIVE XENON STABILITY WITH NO FLUX FLATTENING
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24 Figure:
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1 of 1 EFFECT OF POWER DENSITY ON AXIAL XENON STABILITY INCLUDING VOID TRANSPORT
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4-28 Page:
1 of 1 AZIMUTHAL XENON STABILITY
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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 Core Flow (%)
Uprated Thermal Power (%)A 0
500 1000 1500 2000 2500 3000 3500 0
10 20 30 40 50 60 70 80 90 Core Flow (Mlb/hr)
Thermal Power (MWt)
ICF MELLLA Upper Boundary 100% OLTP 108% OLTP Minimum Power Line Jet Pump and Recirc Pump Cavitation Protection 80% OLTP 60% OLTP 100% LPU Power = 2923 MWt 100% CLTP = 2558 MWt 100% OLTP = 2436 MWt 100% Core Flow = 77.0 Mlb/hr This map derived from analytical methods A: Natural Circulation B: 28% Minimum Pump Speed C: 53.3% Power/ 36.1% Flow D: 100.0% Power/ 99.0% Flow E: 100.0% Power/100.0% Flow F: 100.0% Power/104.5% Flow G: 87.5% Power/104.5% Flow H: 83.3% Power/105.0% Flow I: 58.4% Power/110.0% Flow J: 31.7% Power/110.0% Flow K: 20.0% Power/ 99.0% Flow L: 20.0% Power/ 35.9% Flow A
B K
L D E C
J I
F 2923 MWt G 2558 MWt H 2436 MWt
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1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - BOL 3 W/O GD2O3
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1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - 5 YEARS 3 W/O GD2O3
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1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - BOL 3 W/O GD2O3
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1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - 5 YEARS 3 W/O GD2O3
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1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - BOL UO2
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1 of 1 FUEL TEMPERATURE VERSUS HEAT FLUX - 5 YEARS UO2
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1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - BOL UO2
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1 of 1 CLAD TEMPERATURE VERSUS HEAT FLUX - 5 YEARS UO2
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1 of 1 FUEL ASSEMBLY INITIAL ENRICHMENT DISTRIBUTION 2.1 AVERAGE ENRICHMENT
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1 of 1 LOCAL POWER FACTORS 0 MWD/T 40% VOIDS
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1 of 1 LOCAL POWER FACTORS 10,000 MWD/T 40% VOIDS
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1 of 1 GROSS PEAKING FACTOR AS A FUNCTION OF EXPOSURE BRUNSWICK 1
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1 of 1 DURALIFE - 230 CONTROL ROD
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24 Figure:
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1 of 1 ABB CR82M-1 CONTROL ROD
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25 Figure:
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1 of 1 WESTINGHOUSE ABB CR99 CONTROL ROD