ML20339A035
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GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.2-1 Figure DELETED Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.2-2 Figure DELETED Figure Deleted Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.2-3 Reactor Coolant Leak Detection Sensitivity METHOD I* SENSITIVITY REACTOR COOLANT ACTIVITY Xe-138 = (l.04 µCi/cc Kr-88 = 0.01 µCi/cc LEAK DETECTION TIME (FOR MAXIMUM CIRCULATION IN CONTAINMENT)
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CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS C - 180" & 90° - 270° crnTERLINE OF C - 180° & 90* - 270° KEYWAYS CHAil S MUST PASS THRU OR W[THI" .002 OF THE SAFETY INJECTION NOZZLE THEORETICAL VESSEL CENTERUNE WELD PREPARATION crnTERLlNE OF 90' -270° HYWAYS HUST BE PERPEND[CULAR TO THE CENTERLINE OF THE O' - 100' KEYWAYS W[TH[H . 001/FT NOTES:
I. TOTAL CONCENTRICITY (TOTAL JNOICATOR READING) TO BE EQUAL TO LESS THAN KI.LF OF TOTAL TOLERANCE OF DIAMETERS IN TI-ERl<IAL SHIHD REGION
- 2. ALL DIMENSIONS ARE RELATED TO A ROCtlEnUt GAi A.ND ELECTRIC CORPORATION TEMPERATURE Of 68°F R.l. OINNA NUCLEAR POWER Pl.ANT 3, SHELL COURSE TOLERANCE I N THE THfRl<IAL SHIELD REGION SHALL BE ~ OPDATlD FO~A.L SAFETY A'IALYILI- RDOIIJT SECTION T- T D~CASEl I Figure 5- l-l. Sheet. 2 l OVALITY CASE 2 Oz Dz FLATNESS Rea<: tor Vessel Scheut.ic:
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GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.3-2 Identification and Location of Beltline Region Material
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ROCHESTER GAS AND ELECTRIC CORPORATION R. E. GINNA N UCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYS IS REPORT Fig u re 5 . 3- 2 Identification a nd Locat i on of Beltline Re g i on ~a teria l REV 7 12/91 Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.3-3 Arrangement of Surveillance Capsules in the Reactor Vessel 270° R (3.37 p
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NOTES:
- 1. Lead Factors for the capsules are shown in parentheses.
- 2. In chronological order, capsules V, R, T, S, and N were removed. Ref. Sections 5.3.3.2 and 5.3.3.3.
Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-1 Reactor Coolant Pump MOTOR SHAFT MOTOR ITATOR----
MOTOR SUPP OR 1 IIAND COOLING WAH MAIN FLANGE l
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GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-2 Reactor Coolant Pump Estimated Performance Characteristics
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GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-2a Reactor Coolant Pump Composite Curve, Calculated Hot Performance, Total Head and Hydraulic Efficiency Versus Flow TOTAL HEAD-FT HYDRAULIC EFFICIENCY- %
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- 252 FT ROCHESTER GAS AND ELECTRIC CORPORATION R.E . GINNA NUCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Figure 5.4-2a Reactor Coolant Pump Composite Curve, Calculated Hot Performance, Total Head and Hydraulic Efficiency Versus Flow REV. 13-1 7/96 Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-2b Reactor Coolant Pump Composite Curve, Calculated Hot Performance, Brake Horsepower Versus Flow BRAKE HORSEPOWER 6000 ! 6000 I
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- 90000 GPM ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Figure 5. 4-Zb Reactor Coola nt Pump Composite Curve, Calculated Hot Performance , Break Hors epower Versus Flow REV. 13-1 7/96 Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-2c Reactor Coolant Pump Composite Curve, Calculated Cold Performance, Total Head and Hydraulic Efficiency Versus Flow TOTAL HEAD -FT HYDRAULIC EFFIC IENC Y--.
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GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-2d Reactor Coolant Pump Composite Curve, Calculated Cold Performance, Brake Horsepower Versus Flow BRAKE HORSEPOWER 8000 8000 7600 - '
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- 80000 GPM ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Figure 5. 4 - 2d Reactor Coolant Purnp Composite Curve, Calculated Cold Performanc e, Brake Horsepower Versus Flow REV. 13-1 7/96 Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-3 Reactor Coolant Pressure Shaft Seal Arrangement Figure 5.4-3 Reactor Coolant Pressure Shaft Seal Arrangement l ~OTOR SEALING SURFACE NO. 3 TO REACTOR t==:Jr=~- RltlG CLAMP
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GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-4 Reactor Coolant Pump Flywheel 75 .75 in .
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GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-5 Reactor Coolant Pump Flywheel Primary Stress at Operating Speed 24 22 FLYWHEEL 0. D. 75 in .
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ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Figure 5 . 4-5 Reactor Coolant Pump Flywheel Primary Stress at Ope r ating Speed Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-6 Replacement Steam Generator STEAM OUTLET NOZZLE WI TH ------------ MANWAY (l)
FLO\.l RESTRICTOR ~
DECK LUGS(6) SECONDARY SEPARATOR PRIMARY SEPARATOR LIFTING TRUNNIONS STEAM ORUM (UPPER) SHELL R£CIROJLATION NOZZLE FEEOWATER NOiZLE FEEO\.IATER HEADER CONICAL TRANSITION S£CTICVII F.U.R. ASSEMBLY INSPECTION PORTS (14)
HANOHOLES (2 IN CONE)
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ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYSIS REPORT rigure 5. 4-6 Replacement Steam Generator REV. 13-1 7/96 Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-7 Figure DELETED Figure Deleted Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-8 Pressurizer t - - - - - - - - S P R A Y NOZZLE
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( HEATER ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYSIS REPORT
. . . _ - - - - - - - S U R G E NOZZLE Figure 5. 4-8 Pressurizer Revision 29 11/2020
GINNA/UFSAR CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Figure 5.4-9 Pressurizer Relief Tank PRESSURIZER SAFETY AND RELIEF VALV E DISCHARGE NITROGEN VENT DEMINERALIZED _,/ MANWAY A~~s7 CONNECTION\ CONNECTION SPRAY WATER / SAFETY HE' l [
PERFORATED DISTRIBUTION HEADER LEVEL GUAGE TEMPERATURE CONNECTION CONNECTION ROCHESTER GAS AND ELECTR IC CORPORATION R.E. GINNA NUCLEAR POWER PLANT UPDATED FINAL SA FETY ANALYSIS REPORT Figure 5.4-9 Pressurizer Relief Tank Revision 29 11/2020