ML23129A274
| ML23129A274 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/20/2023 |
| From: | Nebraska Public Power District (NPPD) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23129A261 | List:
|
| References | |
| NLS2023022 | |
| Download: ML23129A274 (1) | |
Text
Typical Fuel Rod Handle Upper Tieplate Channel Active Fuel Length Fuel Rod Spacers 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
CONTROL ROD GAP UPPER TIE PLATE CENTERING SPRING TOP GUIDE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Schematic of Four Bundle Cell Arrangement Figure III-2-4
- - - - - - HEAD SPRAY COOLING NOZZLE VESSEL HEAD STUD l f + - - t - - STEAM DRYER ANO SHROUD HEAD ALIGNMENT ANO GUIDE ROOS 1--11-+-t!t-Hf---,--t-----'.- :,,- STEAM SEPARATOR AND SHROUD HEAD STANDPIPE ASSEMBLY LIFTING LU GS ----t----,-f---~~::;
FEEOWATER INLET
,..,,.,...-+--FEEDWATERSPARGER SHROUD HEAD BOLTS---'--l--+-,r-3'o"<!I Sl1ROOD HEAD FLOOR SlJ PPOOT LEGS--++'"'1--ih,- -----,
JET PUMP lftLIT ELBOW CORE SPRAY SPARGER AJID NOZZLE ASSEIIIBLY _ __...+-+-.
JET PUMP RISER BRACE --+---1--LJ.J
~-:::-,:~+-+-I--- CONTROL ROD FU EL SUPPORT CORE SHROUD
\ ~ r t i ' ~ - - 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
REACTOR CORE SPRAY COOLING REACTOR COOLANT SPARGERS CORE SHROUD DOWNCOMER FLOW REACTOR CORE SUCTION CHAMBER- REACTOR
, ___ PRIMARY THROAT VESSEL (Mixing Section)
FROM RECIRCULATION PUMP Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Reactor Internals Flow Paths Figure III-3-2
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WET STEAM
- RETURNING WATER
- ?
TURNING VANES (INLET NOZZLE)
STANDPIPE TO RECIRCULATION _ . /
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
TRANSITI ON PIECE SEATING SURFACE INLET RISER BRACE JET PUMP NOZZLE ASSEMSL Y
~ - - - CORE SHROUD
....,.....,!---f-*----REACTOR VESSEi.. WAI.I.
,,,,.....,.__ _ CORE SUPPORT
,...-tt t---- DIFFUSER AND TAIi. PIPE RECIRCUL ATION INLET NOZZLE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Jet Pump Assem bly Figure III 5 07/22/ 90
Nebras ka Public Power District COOPE R NUCLEAR STATION UPDAT ED SAFETY ANALYSIS REPOR T (USAR)
Steam Dryer Figur e III 6
0 Stearn Break 1
Feedwater Break
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Gulde Tube Recirc Break 0 Node Identification Number C Indicates Critical Flow 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)
Transie nt Pressure Differe ntials Followin g Steam Line Break at 105-Per cent 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 Differentia ls Following Steam Line Break at 20-Percent Rated Power and 110-Percent Rated Recirculatio n Flow Figure 111-3-9
HEAD FLANGES DRYER &
VESSEL STABILIZER SEPARATORS VESSEL STANDPIPES VESSEL TOP PLATE SHROUD VESSEL FUEL BOTTOM PLATE VESSEL ORO GUIDE TUBE SHROUD SUPPORT TOP OF SKIRT SKIRT BOTTOM HEAD CRO HOUSING 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 Nebra ska Publi.c Power Di§b*kt COOP ER NUCLEAR. STAT ION UPDATED SAFETY ANALYSIS REPO RT (USk.!R)
Mar atho n Con trol Rod Asse mbly Figu re III- 4-la 07/2 2/92
FUEL SUPPORT CASTING CORE SUPPORT PLATE 22-1/16 TO ACTIVE FUEL ZONE 148-7 116 144 in.
3TROKE VELOCITY LIMITER GUIDE TUBE CONTROL ROD DRIVE HOUSING i.....;-11--10 .420--L-1 J~.- ----- ----- -,
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Velocity Limiter Figure III-4-2
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CONTROL ROD ASS EMBLY UNLOCKING HANDLE (SHOWN RAISED AGAINST SPRING FORCE)
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LOCK PLUG UNLOCKING TUBE
/
SPUD INDEX TUBE* DRIVE ACTUATING SHAFT SPRINGS RETURN LOCK PLUG SOCKET 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 GUIDE CAP DRIVE HOUSING ,Plr-----"~H...1#1---+--I---FIXED PISTON (STOP PISTON)
COLLET PISTON RETURN SPRING--+-H'll:tl;..f INDEX TUBE DRIVE CY LINDER MOVING PISTON (MAIN DRIVE PISTON)
DRIVE WITHDRAW DRIVE INSERT LINE LINE ARROWS SHOW WATER FLOW WHEN THE DRIVE IS IN THE WITHDRAWAL MQOE Of OPERATION.
BALL CHECK PRESSURES SHOWN ARE MAXIMUM.
VALVE PR= REACTOR PRESSURE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Drive Unit Figure III-5-2
CONTROL ROD VELOCITY LIMITER GUIDE TUBE c-,
0 COTTER PIN ;;!
COLLET*FINGERSr~
COLLET-SPRING COLLET-PISTON ANO RINGS PRESSURE OVER PORT HOUSiNG FLANGE BALL CHECK VALVE
""~..__J.......- VESSEL PORTS DRIVE MAIN FLANGE WELDED PLUG RING FLANGE BOLT POSITION INDICATOR WELL POSITION INDICATOR TO PISTON TUBE HEAD WELD HOUSING Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Control Rod Drive Unit (Schematic)
Figure III-5-3
15 16
- l. EXTERNAL Fll TER ASSEMBLY 15. OUTERTUBE{Partofcylmder,tube,andllange) 28. SWITCH-ACTUATING MAGNET {Part of dr1ve,p1stoo) 41. ORIVE*WITHORAW WATER INLET
- 2. INTERNAL FILTER ASSEMBLY 16. CYLINDER TUBE 29, PISTON TUBE ASSEMBLY (A\sooo.tlet f0rsciamw3ter}
- 3. UNCOUPLING ROD ASSEMBLY 11. INDEX TUBE 30. DRIVE-WITHDRAW PORTS AND ANNULUS 42. METAL 0-RING SEAL (Drive to housmg) 4.GUIDECAP 18. LOCKINGBANO(Typical) (A\sosmmootlet) 43. DRIVE PISTON
- 5. BARREL 19. INTERNAL PISTON SEAL RINGS (Typical) 31. RING FLANGE 4~. INDICATOR TUBE (Part of piston tube)
- 6. STOP PISTON 20. INTERNAL PISTON BUSHINGS (Typical) 32. M:ACHINESCREW(Typical) 45. THERMOCOUPLE (Part of position md1cator probe) 7.COLLETSPRING 21. EXTERNAL PISTON BUSHINGS 33. POSITION !NOICATOR PROBE 46. STUD (Part of piston lube) Nebraska Public Power District
- 8. COLLET AND COLLET PISTON 22. EXTERNAL PISTON SEALS 34. POSITION INDICATOR CMLE 47. SPRING WASHERS COOPER NUCLEAR STATION
- 9. COLLET HOUSING(Partof cylmder,tubeandf!ange) 23. STRAINER 35. PISTON TUBE NUT ~8. STOP PISTON BUSH!NGS(Typ1cal) UPDATED SAFETY ANALYSIS REPORT (USAR)
- 10. COLLET PISTON SEALS 24. COOLING WATER ORIFICE 36. CAPSCREW(Typical) 49. STOP PISTON SEAL RINGS (Typical)
II. SPACER(Pa1tofcylmder,tube,and!lange) 25. ORIVE*INSERTWATER INLET 37 *. 0-R1NGSEALS 50. COLLET FINGER(Typical)
- 12. BUFFEROR!F\CES(Typ1cal) (Normal aodsaam;drive-withdrawal outlet) 38.'0RIVE-INSERT PORTS ANO ANNULUS 51. COTTER PIN
- 13. POSITION INDICATOR SWITCHES {Typical) 26. BALL-SHUTTLE VALVE 39. DRIVE FLANGE (Part of cylinder, tube, and flange} 52. COUPLING SPUD Control Rod Drive Unit
- 27. REACTOR WATER INLET (Throogh drive housing)
(Cutaway)
Figure III-5-4
ACCUMULATOR CHARGE LINE SCRAM DISCHARGE LINE COOLING WATER LINE WITHDRAWAL LINE INSERT LINE DRIVE WATEij LINE EXHAUST WATER LINE OUTLET SCRAM VALVE ELECTRICAL INLET SCRAM CONDUIT VALVE CONNECTION ELECTRICAL JUNCTION BOX SPEED CONTROL VALVES DIRECTIONAL CONTROL VALVES (4)
ACCUMULATOR NITROGEN VOLUME FRAME 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 CADD FILE: C0051214 6/8/04
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Nebra ska Public Power District COOP ER NUCL EAR STAT ION
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UPDA TED SAFE TY ANAL YSIS REPORT (USAR Gener ic Figur e Stuck Rod Marg in as Funct ion of Core Avera ge Expos ure Figur e III-6-1 03/08 /00
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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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Generic Figure Maximum Rod Worth Versus Moderator Density Figure III-6-3 03/08/00
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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 COOPE R 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 PERCEN T RATED POWER Nebraska Public Power District COOPE R NUCLE AR 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
-2.0 BEGINNING-OF-LIF E AND END-OF-LIFE VOID COEFFICIENT OF REACTIVITY
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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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Generic Figure Effect of Power Density on Axial Xenon Stability Including Void Transport Figure III-6-12 03/08/00
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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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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
120 NOMINAL EXPECTED FLOW CONTROL LINE 100 CONSTAN T PUMP SPEED LINE 80 a:
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CIRCULAT ION LINE 40 20 MINIMUM POWER LINE JET PUMP NPSH LIMIT LINE RECIRC PUMP NPSH LIMIT LINE 0 1--lllll::;,; J...--....l.-. ..a::-1.-..:: :::;;;;;;.i.. ._ _...1._ _..c;,i.,__ _
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30 40 50 60 70 80 90 100 110 120 0 10 20 Nebraska Public Power District COOPER NUCLEA R STATION UPDATE D SAFETY ANALYSIS REPORT (USAR)
Operati ng Map Figur. III-7-l a
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 A, 60. 6% Power / 33*.6\ Fl.ow 120 B: 100,0t Power/ 76.8% Flow - -------------~-------~---------~-------**-
B': 98,4\' Power / 75.0\- Flow Ci 100.0\ Power/ 100.0% Flow 2800 110 C' I 98.4% Power / 100.0% Flow ***1-..
D: l.00,0t Power / 105.0\' Flow D': 98. 4t Power / 105. O\ Flow 100 E1 24. H Power / 10.5. 0\ Flow B ' ' C D. .
,** ~ ..2.U9.MWt. ...
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34.8% Flow 100% Rod Line - - C - - - - - - - - - " - " - - - 2381 MWt 2400 32.5% Flow 90 -
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Natqral Circul!ltion 30 *-r-**. 800
' E 20 *.J Cavitation Interlock Line 400 100% TPO
- 2419 MWt i
10
- !**'!- - ...... 100% CLTP
- 2381 MWt 100% Core Flow ~ 73 .S Mlbm/hr I
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 80 90 100 110 120 Core Flow (%)
Nebrask a Public Power District COOPE R NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Power/F low 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 p.., 0.8
~
H
~ 0.7
µcl H
tl,..:i 0.6
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
-STEEL FORM LINER 1--1+---I--- HANGER ROD i, VESSEL SUPPORT PEDESTAL GRID CLAMP 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 APRM Scram Line ~
120 100 APRM Rod Block 80 Rated rod line 60 40 20 0
0 20 40 60 80 100 120 Core Flow( % of rated)
Coordina tes of Exclusio n Region Boundar J
- where, Point# Power(3/4 ) Flow(3/4)
A 75.4 43.8 P = a core thermal power value on the Exclusio n Region boundar y (% of rated),
boundary B 363 30.0 W = the core flow rate corresponding to power, p, on the Exclusio n Region
(% 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),
W0 = core flow rate at State Point B (% of rated),
Nebrask a Public Power District COOPE R NUCLEA R STATIO N UPDATE D SAFETY ANALY SIS REPOR T (USAR)
Power to Flow Operating Map Figure III-10-1 08/15/98