ML21130A072
Text
Typical Fuel Rod Active Fuel Length Upper Tieplate Fuel Rod Spacers Handle Channel Lower Tieplate Casting Bypass Flow Hole Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Typical GE BWR Fuel Assembly Figure III-2-1 03/14/07
UPPER TIE PLATE CENTERING SPRING CONTROL ROD GAP TOP GUIDE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Schematic of Four Bundle Cell Arrangement Figure III-2-4
SHROUD HEAD LIFTING LU GS ----t----,-f---~~::;
SHROUD HEAD BOLTS---'--l--+-,r-3'o"<!I Sl1ROOD HEAD FLOOR SlJ PPOOT LEGS--++'"'1--ih,------,
JET PUMP lftLIT ELBOW AJID NOZZLE ASSEIIIBLY _ __...+-+-.
JET PUMP RISER BRACE --+---1--LJ.J
HEAD SPRAY COOLING NOZZLE VESSEL HEAD STUD lf+--t-- STEAM DRYER ANO SHROUD HEAD ALIGNMENT ANO GUIDE ROOS 1--11-+-t!t-Hf---,--t-----'.-:,,- STEAM SEPARATOR AND STANDPIPE ASSEMBLY FEEOWATER INLET
,..,,.,...-+--FEEDWATERSPARGER CORE SPRAY SPARGER
~-:::-,:~+-+-I--- CONTROL ROD FU EL SUPPORT CORE SHROUD
\\~rti'~-- CORE DIFFERENTIAL PRESSURE TAP & LIQUID CONTROL INLET NOZZLE RECIRCULATING WATER OUTLET NOZZLE CONTROL ROD GUIDE TUBE CONTROL ROD DRIVE HOUSING SUPPORT STRUCTURE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Reactor Internals Arrangement Figure III-3-1
CORE SHROUD DOWNCOMER FLOW SUCTION CHAMBER-THROAT (Mixing Section)
FROM RECIRCULATION PUMP REACTOR CORE SPRAY COOLING SPARGERS REACTOR CORE REACTOR COOLANT REACTOR
, ___ PRIMARY VESSEL Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Reactor Internals Flow Paths Figure III-3-2
TO RECIRCULATION _./
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WET STEAM RETURNING WATER
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TURNING VANES (INLET NOZZLE)
STANDPIPE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Axial Flow Steam Separator Figure III-3-3
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Fuel Support Pieces Figure III-3-4
TRANSITION PIECE SEATING SURFACE RISER BRACE INLET JET PUMP NOZZLE ASSEMSL Y
~--- CORE SHROUD
....,.....,!---f-*----REACTOR VESSEi.. WAI.I.
,,,,.....,._ __ CORE SUPPORT
,...-ttt---- DIFFUSER AND TAIi. PIPE RECIRCULATION INLET NOZZLE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Jet Pump Assembly Figure III-3-5 07/22/90
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Steam Dryer Figure III-3-6
0 1
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Node Identification Number C
Indicates Critical Flow Gulde Tube l
Stearn Break Feedwater Break Recirc Break Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Pressure Nodes Used for Depressurization Analysis Figure III-3-7 09/19/00
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I Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Transient Pressure Differentials Following Steam Line Break at 105-Percent Rated Steam Flow Figure III-3-8
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I Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Transient Pressure Differentials Following Steam Line Break at 20-Percent Rated Power and 110-Percent Rated Recirculation Flow Figure 111-3-9
FUEL ORO GUIDE TUBE SEPARATORS STANDPIPES SHROUD TOP PLATE HEAD FLANGES DRYER &
VESSEL STABILIZER VESSEL VESSEL VESSEL BOTTOM PLATE VESSEL SHROUD SUPPORT CRO HOUSING TOP OF SKIRT SKIRT BOTTOM HEAD PEDESTAL Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Analytical Model of Reactor Vessel Internals Figure III-3-10
BLADE NEUTRON ABSORBER RODS COUPLING RELEASE HANDLE VELOCITY LIMITER COUPLING SOCKET Nebraska Publi.c Power Di§b*kt COOPER NUCLEAR. STATION UPDATED SAFETY ANALYSIS REPORT (USk.!R)
Marathon Control Rod Assembly Figure III-4-la 07/22/92
22-1/16 TO ACTIVE FUEL ZONE 144 in.
3TROKE i.....;-11--10.420--L-1 FUEL SUPPORT CASTING CORE SUPPORT PLATE 148-7 116 VELOCITY LIMITER GUIDE TUBE CONTROL ROD DRIVE HOUSING J~.------------,
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Velocity Limiter Figure III-4-2
UNLOCKING HANDLE (SHOWN RAISED AGAINST SPRING FORCE)
SOCKET
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SPUD CONTROL ROD ASS EMBLY LOCK PLUG UNLOCKING TUBE INDEX TUBE* DRIVE
/
ACTUATING SHAFT SPRINGS RETURN LOCK PLUG Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod to Control Rod Drive Coupling Figure III-5-1
BOTTOM Of REACTOR VESSEL DRIVE HOUSING COLLET PISTON RETURN SPRING--+-H'll:tl;..f DRIVE INSERT LINE BALL CHECK VALVE DRIVE CY LINDER GUIDE CAP
,Plr-----"~H...1#1---+--I---FIXED PISTON (STOP PISTON)
INDEX TUBE MOVING PISTON (MAIN DRIVE PISTON)
DRIVE WITHDRAW LINE ARROWS SHOW WATER FLOW WHEN THE DRIVE IS IN THE WITHDRAWAL MQOE Of OPERATION.
PRESSURES SHOWN ARE MAXIMUM.
PR= REACTOR PRESSURE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Drive Unit Figure III-5-2
PRESSURE OVER PORT HOUSiNG FLANGE RING FLANGE BOLT POSITION INDICATOR WELL TO PISTON TUBE HEAD WELD CONTROL ROD VELOCITY LIMITER GUIDE TUBE c-,
0,...
COTTER PIN COLLET*FINGERSr~
COLLET-SPRING COLLET-PISTON ANO RINGS BALL CHECK VALVE
""~..__J.......- VESSEL PORTS DRIVE MAIN FLANGE WELDED PLUG POSITION INDICATOR HOUSING Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Drive Unit (Schematic)
Figure III-5-3
- l. EXTERNAL Fll TER ASSEMBLY
- 2. INTERNAL FILTER ASSEMBLY
- 3. UNCOUPLING ROD ASSEMBLY 4.GUIDECAP
- 5. BARREL
- 6. STOP PISTON 7.COLLETSPRING
- 8. COLLET AND COLLET PISTON
- 9. COLLET HOUSING(Partof cylmder,tubeandf!ange)
- 10. COLLET PISTON SEALS II. SPACER(Pa1tofcylmder,tube,and!lange)
- 12. BUFFEROR!F\\CES(Typ1cal)
- 13. POSITION INDICATOR SWITCHES {Typical)
- 14. LOCKING GROOVE (Typical)
- 15. OUTERTUBE{Partofcylmder,tube,andllange)
- 16. CYLINDER TUBE
- 11. INDEX TUBE
- 18. LOCKINGBANO(Typical)
- 19. INTERNAL PISTON SEAL RINGS (Typical)
- 20. INTERNAL PISTON BUSHINGS (Typical)
- 21. EXTERNAL PISTON BUSHINGS
- 22. EXTERNAL PISTON SEALS
- 23. STRAINER
- 24. COOLING WATER ORIFICE
- 25. ORIVE*INSERTWATER INLET (Normal aodsaam;drive-withdrawal outlet)
- 26. BALL-SHUTTLE VALVE
- 27. REACTOR WATER INLET (Throogh drive housing)
- 28. SWITCH-ACTUATING MAGNET {Part of dr1ve,p1stoo) 29, PISTON TUBE ASSEMBLY
- 30. DRIVE-WITHDRAW PORTS AND ANNULUS (A\\sosmmootlet)
- 31. RING FLANGE
- 32. M:ACHINESCREW(Typical)
- 33. POSITION !NOICATOR PROBE
- 34. POSITION INDICATOR CMLE
- 35. PISTON TUBE NUT
- 36. CAPSCREW(Typical) 37 *. 0-R1NGSEALS 38.'0RIVE-INSERT PORTS ANO ANNULUS
- 39. DRIVE FLANGE (Part of cylinder, tube, and flange}
- 41. ORIVE*WITHORAW WATER INLET (A\\sooo.tlet f0rsciamw3ter}
- 42. METAL 0-RING SEAL (Drive to housmg)
- 43. DRIVE PISTON 4~. INDICATOR TUBE (Part of piston tube)
- 45. THERMOCOUPLE (Part of position md1cator probe)
- 46. STUD (Part of piston lube)
- 47. SPRING WASHERS
~8. STOP PISTON BUSH!NGS(Typ1cal)
- 49. STOP PISTON SEAL RINGS (Typical)
- 50. COLLET FINGER(Typical)
- 51. COTTER PIN
- 52. COUPLING SPUD 15 16 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Drive Unit (Cutaway)
Figure III-5-4
CADD FILE: C0051214 ACCUMULATOR CHARGE LINE SCRAM DISCHARGE LINE COOLING WATER LINE INSERT LINE INLET SCRAM VALVE ACCUMULATOR FRAME WITHDRAWAL LINE DRIVE WATEij LINE EXHAUST WATER LINE OUTLET SCRAM VALVE ELECTRICAL CONDUIT CONNECTION ELECTRICAL JUNCTION BOX SPEED CONTROL VALVES DIRECTIONAL CONTROL VALVES (4)
NITROGEN VOLUME NITROGEN PRESSURE INDICATOR Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT Figure 111-5-8 6/8/04
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Stuck Rod Margin as Function of Core Average Exposure Figure III-6-1 03/08/00
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" ' '\\.
EQUILIBRUIM Xe AND Sm HOT STANDBY HOT OPERATING (38'& VOIDS) 0'-----------"---_,_ ______..__.,._ _ _._ _____ _.
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Fractional Control Rod Density Versus Average Moderator Density Figure III-6-2 03/08/00
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1.0 0.96 092 0.88 084 080 0.76 0.72 AVERAGE MODERATOR DENSITY. ptgm cci Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Maximum Rod Worth Versus Moderator Density Figure III-6-3 03/08/00
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Maximum Rod Worth Versus Power Level Figure III~6-4 03/08/00
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Doppler Coefficient of Reactivity Figure III-6-5 03/08/00
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Doppler Coefficient as Function of Fuel Exposure Figure III-6-6 03/08/00
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0 10 20 30 40 50 60 70 80 90 100 ll0 PERCENT RATED POWER Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Core Average Doppler Defect Versus Core Power Level Figure III-6-7 03/08/00
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Generic Figure Doppler Defect Versus Fuel Temperature Figure III-6-8 03/08/00
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10 BEGINNING-OF-LIFE AND END-OF-LIFE VOID COEFFICIENT OF REACTIVITY 20 30 40 -
50 60 70 80 CORE AVERAGE VOIDS(%)
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Moderator Void Coefficient of Reactivity Figure III-6-9 03/08/00
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Generic Figure Xenon Reactivity Buildup After Shutdown -
Beginning of Life Figure III-6-10 03/08/00
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Generic Figure Relative Xenon Stability with No Flux Flattening Figure III-6-11 03/08/00
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OPERATING RANGE E.O.L.
STABLE DESIGN POINT 4.8 x 1013 4.0 6.0 8.0 10.0 THERtML FLUX (n/cm 2-sec) x 1013 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Effect of Power Density on Axial Xenon Stability Including Void Transport Figure III-6-12 03/08/00
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___._ _____ _._ ____ ___.L--____ _._ _______..._ _ _.
0 20 40 60 80 100 PERCENT OF RADIUS FLUX FLATTENED Nebr.aska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
- Generic Figure Azimuthal Xenon Stability Figure III-6-13 03/08/00
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0 0.20 0.4 0.8 1.2 1.6 2.0 2.4 2.8 3.0 TIME AFTER RECEIPT OF SCRAM SIGNAL AT SENSORS (sec)
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Generic Figure Control Rod Scram Reactivity Characteristics Excursion Analysis Figure III-6-14 03/08/00
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Generic Figure Scram Characteristics Assumed for Transient Analysis Figure III-6-15 03/08/00
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0 10 20 30 40 50 60 70 80 90 100 110 120 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Operating Map Figur. III-7-la
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Core Flow (Mlbm/hr) 0 10 20 30 40 50 60 70 80 130 -l-----t--,---!---f---t---,---t--+--t-,----t--,-f---,f--,---+---,--t---+-;--+----t--,-f--7 120 110 100 90 80 70 60 50 40 30 20 10 A,
- 60. 6% Power /
33*.6\\ Fl.ow B: 100,0t Power/
76.8% Flow --------------~-------~---------~-------**-:--------
B':
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75.0\\- Flow Ci 100.0\\ Power/ 100.0% Flow C' I 98.4% Power / 100.0% Flow
- 1-..
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- 98. 4t Power / 105. O\\ Flow E1
- 24. H Power / 10.5. 0\\ Flow F:
- 24. 6% Power /
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Circul!ltion
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- 2419 MWt
- 2381 MWt
~ 73.S Mlbm/hr 2800 2400 2000 1600 1200 800 400 f 6 lo..
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Q.)
15 0 I I I I I I I I I I Y:r"I I I I I I I I I I I I I I I I I I I I I I I I I I I.
I I I I I I I I I I I I I I I I I I I I I 0 0
10 20 30 40 50 60 70 Core Flow (%)
80 90 100 110 120 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Power/Flow Map MELLL and ICF Fig;1re III-7-lb 08/07/08
2.00,----------------------------------....
1.90
- 1. 70 _____......, __________......, __.....__...... ___________......,,
0 1,000 2,000 3,000 4,000 5,000 6,000 7,000 8,000 9,000 10,000 11,000 EXPOSURE (MWd)
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Gross Power Peaking versus Exposure Figure 111-7-3
1.5 1.4 1.3 1.2 1.1 1.0 0.9
~ !
0.8
~
H
~
0.7 J:il p-H
~
0.6
....:l J:il
~
0.5 0.4 0.3 0.2 0.1 0
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 AXIAL NODE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT /USA!{)
Axial Power Distribution (Case 1)
Figure III-7-4a
1.5 1.4 1.3 1.2 1.1 1.0 0.9
~
5 0.8 p..,
~
H
~
0.7
µcl H
tl 0.6
,..:i
µcl
~
0.5 0.4 0.3 0.2 0.1 0
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 AXIAL NODE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Axial Power Distribution (Case 2)
Figure III-7-4b
GRID CLAMP 1--1+---I--- HANGER ROD
-STEEL FORM LINER i,
VESSEL SUPPORT PEDESTAL Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Drive Housing Support Figure III-8-1
Figure 10.1 140 120 APRM Scram Line~
100 APRM Rod Block 80 Rated rod line 60 40 20 0
0 20 40 60 80 Core Flow(% of rated)
- where, P = a core thermal power value on the Exclusion Region boundary (% of rated),
W = the core flow rate corresponding to power, p, on the Exclusion Region boundary
(% of rated),
PA = core thermal power at State Point A (% of rated),
P0 = core thermal power at State Point B (% of rated),
WA = core flow rate at State Point A (% of rated),
W 0 = core flow rate at State Point B (% of rated),
100 120 Coordinates of Exclusion Region BoundarJ Point#
Power(3/4)
Flow(3/4)
A 75.4 43.8 B
363 30.0 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Power to Flow Operating Map Figure III-10-1 08/15/98