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2011 Updated Final Safety Analysis Report, Rev 16, Chapter 5, Appendix 5B. Figures
	ML11290A239
Person / Time
Site:	McGuire, Mcguire
Issue date:	10/05/2011
From:	; Duke Energy Carolinas
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML11290A239 (34)
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McGuire Nuclear Station UFSAR Appendix 5B. Figures Appendix 5B. Figures

McGuire Nuclear Station UFSAR Figure 5-1 (Page 1 of 1)

(10 OCT 2009)

Figure 5-1. Flow Diagram of Reactor Coolant System

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McGuire Nuclear Station UFSAR Figure 5-2 (Page 1 of 1)

(14 OCT 2000)

Figure 5-2. Deleted Per 1994 Update

McGuire Nuclear Station UFSAR Figure 5-3 (Page 1 of 1)

(14 OCT 2000)

Figure 5-3. Pump Head - Flow Characteristics 115 110 IoU

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PUMP CAPABILITY en

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90 THERMIIL BEST MECHANICAL DESIGH ESTIMATE DESI GN FLOW FLOW FLOW 85 92 9~

96 98 100 102 IO~

106 REACTOR COOLANT LOOP FLOW (PERCENT OF BEST ESTIMATE)

McGuire Nuclear Station UFSAR Figure 5 5-7 (Page 1 of 1)

(27 MAR 2002)

Figure 5-4. Deleted Per 1998 Update Figure 5-5. Deleted Per 1998 Update Figure 5-6. Deleted Per 1998 Update Figure 5-7. Deleted Per 1998 Update

McGuire Nuclear Station UFSAR Figure 5-8 (Page 1 of 1)

(14 OCT 2000)

Figure 5-8. Reactor Coolant Loop/Supports System Dynamic - Westinghouse Structural Model YG Xc ZG Lumped Mass RCL GLOBAL COORDINATE SYSTEN STEMI GENERATOR STIA;-! GEKDu\\TOR UPPER SUPPORT REACTOR COOLANT STEAM LO\\,ER SUPPORT CR(lSSOVEI{ LEG I,ESTRAl:rr RE,\\CTUR COLlL\\:-';T pnlP SliPPUlrl'

McGuire Nuclear Station UFSAR Figure 5-9 (Page 1 of 1)

(27 MAR 2002)

Figure 5-9. Deleted Per 1998 Update

McGuire Nuclear Station UFSAR Figure 5-10 (Page 1 of 1)

(14 OCT 2000)

Figure 5-10. Power Operated Relief Valve Flow Characteristics 1.0

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Valve Clo.ln~ ---

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McGuire Nuclear Station UFSAR Figure 5 5-14 (Page 1 of 1)

(14 OCT 2000)

Figure 5-11. Deleted Per 1997 Update Figure 5-12. Deleted Per 1997 Update Figure 5-13. Deleted Per 1997 Update Figure 5-14. Deleted per 1997 Update

McGuire Nuclear Station UFSAR Figure 5-15 (Page 1 of 1)

(14 OCT 2000)

Figure 5-15. Effect of Fluence and Copper Content on Shift of RTNDT for Reactor Vessel Steels Exposed to 550°F Temperature

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McGuire Nuclear Station UFSAR Figure 5-16 (Page 1 of 1)

(14 OCT 2000)

Figure 5-16. Predicted Fluence at 1/4T and 3/4T Locations as a Function of Full Power Service Years

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McGuire Nuclear Station UFSAR Figure 5-17 (Page 1 of 1)

(14 OCT 2000)

Figure 5-17. KID Lower bound Fracture Toughness A533V (Reference WCAP 7623) Grade B Class 1

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McGuire Nuclear Station UFSAR Figure 5-18 (Page 1 of 1)

(14 OCT 2000)

Figure 5-18. Nominal Containment Sump Level Change Rate Versus Leakage Rate 1.0 Z

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McGuire Nuclear Station UFSAR Figure 5-19 (Page 1 of 1)

(06 OCT 2003)

Figure 5-19. Relationship Between Reactor Coolant System Temperature and Power Refer to Sections 4.4.3.4 and 5.3.3 for applicability.

McGuire Nuclear Station UFSAR Figure 5-20 (Page 1 of 1)

(14 OCT 2000)

Figure 5-20. Reactor Vessel Head View Showing Top-Mounted Control Drive Mechanism Housing Locations 2700 CRDM HOUSING

McGuire Nuclear Station UFSAR Figure 5-21 (Page 1 of 1)

(14 OCT 2000)

Figure 5-21. Surveillance Capsule for Unit 1-Elevation View NOZZLE WELD VESSEL INTERMEDIATE SHEll------~

..... 52* ----+--H WElD YES SEL LOWER SHE LL -------f-,J.,

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CORE" 144"

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CHAR PY S PEe I MEN WELD

McGuire Nuclear Station UFSAR Figure 5-22 (Page 1 of 1)

(14 OCT 2000)

Figure 5-22. Surveillance Capsule for Unit 2-Elevation View NOZZLE WELD 18",

WELD __........... 1nt1t111--'--

rv 52,,----~-I--I VESSEL LOWER SHELL

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CORE 144" 0.030 STAINLESS SHEATH

4~. CORE SPACER CHARPY SPEC I MEN WELD

McGuire Nuclear Station UFSAR Figure 5-23 (Page 1 of 1)

(14 OCT 2000)

Figure 5-23. Surveillance Capsule Plan View (Representative for Unit 1, Unit 2 Similar)

CORE BARREL VESSEL S~IELD CAPSULE 81-S/S" VERTICAL WELD SEAMS INT. SHELL 1700

~ 3S0 0 1800 LOwER SHELL 900 & 2700

McGuire Nuclear Station UFSAR Figure 5-24 (Page 1 of 1)

(14 OCT 2000)

Figure 5-24. Reactor Coolant Controlled Leakage Pumps FLYWH EEL uPPER RADIAL BEARING THRUST BEAR I NG MOTOR SHAFT MOTOR STATOR MAIN LEAD CONDU I T BOll LOWER RADIAL BEARING "APOI{ LEAKAGE TO ATMOSPHERE NO.

I I NJECT I ON WATER LEAK OFF PUMP SHAFT COOLING WATER I tlLET DISCHARGE NOZZLE SUCTION NOZZLE THRUST BEAR I NG OIL LIFT PUMP +

MOTOR r---__ MOTOR UNI T ASSEM BLY UPPER SE AL HOUSING

~~j'~Lh..rl------ LOWER SEAL HOUSING

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'-i4rl~---t~-~--- RAD I AL BE AR IN G ASSEMBLY

...... 1.------- CASING

--fi.::-....L------- IMPELLER

McGuire Nuclear Station UFSAR Figure 5-25 (Page 1 of 1)

(14 OCT 2000)

Figure 5-25. Estimated Performance Curve - Controlled Leakage Main Coolant Pump 0 < w

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McGuire Nuclear Station UFSAR Figure 5-26 (Page 1 of 1)

(14 OCT 2000)

Figure 5-26. Reactor Coolant Pump Spool Piece and Motor Support Stand

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McGuire Nuclear Station UFSAR Figure 5-27 (Page 1 of 1)

(14 OCT 2000)

Figure 5-27. BWI Steam Generator STEAM ourU::T "aZZLE SECOtlOIIRY M.l.NWiI Y STEAM DRUM HEm STEAM DRUM MAIN F£EOWATEA NOZZLE RECIRCULATION NOZZLE twER LATERAL SlFPORT TRI.N>IHlN INSPECTlctI PORTS SECDNOARY SHELL TUElESHEET PRIMM'!' HE,I.O--~ ___..

INLET/ruTLET NJZZLE 11 II SECONDAAY CYCLONES PRIM~Y CYCLOHES AUXILIARY FEEOWATER NOZZLE FlAT eAR 'U'BENO

~5TRAINT SYSTEM LATTICE GRIOS PRtMARY MANW,o,y

McGuire Nuclear Station UFSAR Figure 5-28 (Page 1 of 1)

(10 OCT 2009)

Figure 5-28. Flow Diagram of Residual Heat Removal System (ND)

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McGuire Nuclear Station UFSAR Figure 5-29 (Page 1 of 1)

(14 OCT 2000)

Figure 5-29. Pressurizer RELIEF NOZZlE--_____

........ ~

HEATER SUPPORT PLATE SPHY NOZZLE SAFETY NOZZLE

MANWAY UPPER HEAD INSTRUMENTATION NOZZLE liFTING TRUNNION SHEll LOWER HEAD IHSTRUMEHTATIOH NOZZLE ELECTRICAL HEATER SUPPORT SKIRT SU RGE NOZZLE

McGuire Nuclear Station UFSAR Figure 5-30 (Page 1 of 1)

(14 OCT 2000)

Figure 5-30. Typical Steam Generator Lower Lateral Support y

STEAM GENERATOR LUG (TYPICAL 4 PLACES)

~TO REACTOR

¥ESSEL ct

-- - -~~- 0" - 180* AXIS OF REACTOR x

/CRANE

./

WALL

McGuire Nuclear Station UFSAR Figure 5-31 (Page 1 of 1)

(14 OCT 2000)

Figure 5-31. Typical Steam Generator Upper Support

~ OF REACiOA Vf~SEL

4. EL. 7'1'7". e.k

McGuire Nuclear Station UFSAR Figure 5-32 (Page 1 of 1)

(14 OCT 2000)

Figure 5-32. Typical Column Assembly for the Steam Generator and Reactor Coolant Pump I PVERTICAL J

g" fl, 743 +91.6 EL. ?40'+O" 1

UPPER CLEVIS 1234' 0.;), SEAMLESS

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McGuire Nuclear Station UFSAR Figure 5-33 (Page 1 of 1)

(14 OCT 2000)

Figure 5-33. Typical Reactor Coolant Pump Lateral Support for Loops 1-2 y

BUMPER NO. 3-

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5'-8"

/

BUMPER NO.2

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McGuire Nuclear Station UFSAR Figure 5-34 (Page 1 of 1)

(14 OCT 2000)

Figure 5-34. Typical Reactor Coolant Pump Lateral Support for Loops 3-4 BUMPER NO 3.-

x r--.. -.

5'-8" REACTOR PUMP LUG; 3'-1" I -+- -

3'_7'1"

~ _ _ _.lh-__

NO 2.

CRANE WALL!

McGuire Nuclear Station UFSAR Figure 5-35 (Page 1 of 1)

(14 OCT 2000)

Figure 5-35. Pressurizer Support System Elevation

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PRESSURIZER LOWER SUPPORT FRAME

McGuire Nuclear Station UFSAR Figure 5-36 (Page 1 of 1)

(14 OCT 2000)

Figure 5-36. Pressurizer Lower Lateral Support

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McGuire Nuclear Station UFSAR Figure 5-37 (Page 1 of 1)

(14 OCT 2000)

Figure 5-37. Pressurizer Upper Lateral Support PRESSURIZER LUG (TYPICAL 4 PLACE. 5)

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IS"

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_______ t l

OF R£ACiOR BUILDING

McGuire Nuclear Station UFSAR Figure 5-38 (Page 1 of 1)

(14 OCT 2000)

Figure 5-38. Typical Reactor Vessel Support

/

- PRIMARY SHIELD WALL ~

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REACTOR VESSEL SUPPORT LUG

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McGuire Nuclear Station UFSAR Figure 5 5-43 (Page 1 of 1)

(14 OCT 2000)

Figure 5-39. Deleted Per 1995 Update Figure 5-40. Deleted Per 1995 Update Figure 5-41. Deleted Per 1995 Update Figure 5-42. Deleted Per 1995 Update Figure 5-43. Deleted Per 1995 Update

ML11290A239

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