ML11290A239

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)

Text

McGuire Nuclear Station UFSAR Appendix 5B. Figures Appendix 5B. Figures

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

Figure 5-1. Flow Diagram of Reactor Coolant System

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

Figure 5-2. Deleted Per 1994 Update (14 OCT 2000)

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

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

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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)

(14 OCT 2000)

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

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 (27 MAR 2002)

Figure 5-8. Reactor Coolant Loop/Supports System Dynamic - Westinghouse Structural Model McGuire Nuclear Station STEMI GENERATOR STIA;-! GEKDu\TOR UPPER SUPPORT REACTOR COOLANT RE,\CTUR COLlL\:-';T pnlP Y SliPPUlrl' G

STEAM ZG LO\,ER SUPPORT Xc Lumped Mass RCL GLOBAL COORDINATE SYSTEN UFSAR Figure 5-8 (Page 1 of 1)

CR(lSSOVEI{ LEG I,ESTRAl:rr (14 OCT 2000)

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

Figure 5-9. Deleted Per 1998 Update (27 MAR 2002)

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

Figure 5-10. Power Operated Relief Valve Flow Characteristics I4Cr.UIRE NUCLEAR STATION PQ!.rER OPERATED RELIEF VALVE FLOt~ CHARACTERISTICS 1.0 - ....... , ,

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TIME NO~LIZED Valve Open1n1~

Valve Clo.ln~

(14 OCT 2000)

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

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 (14 OCT 2000)

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

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)

Figure 5-16. Predicted Fluence at 1/4T and 3/4T Locations as a Function of Full Power Service Years "15 l(. .

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

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

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-200 -150 -100 -50 0 50 100 150 200 REFERENCE TFMPERATURE (T-NOTTl-oF (14 OCT 2000)

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

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

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(14 OCT 2000)

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

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

(06 OCT 2003)

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

Figure 5-20. Reactor Vessel Head View Showing Top-Mounted Control Drive Mechanism Housing Locations 270 0 CRDM HOUSING (14 OCT 2000)

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

Figure 5-21. Surveillance Capsule for Unit 1- Elevation View NOZZLE WELD *t 16" 21"

• CORE" VESSEL INTERMEDIATE SHEll------~

144"

..... 52* - - - - + - - H ~~~-- ---- t- - -

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- APSULE YES SEL LOWER SHE LL -------f-,J.,

NEUTRON SH I fLD PAD 50-1/2" r 0.030 STAINLESS SHEATH

~ I-I SPACER

)II CORE 1

Cv CHAR PY SPEe I MEN WELD (14 OCT 2000)

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

Figure 5-22. Surveillance Capsule for Unit 2- Elevation View NOZZLE WELD 18" CORE 144" WELD _ _........... 1nt1t111--'--

s" ,

rv 52 ,,----~-I--I

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"CAPSULE VESSEL LOWER SHELL -~

NEUTRON SHIELD PAD WELD 0.030 STAINLESS SHEATH

---

4~. CORE SPACER CHARPY SPEC I MEN WELD (14 OCT 2000)

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

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 170 0 ~ 3S0 0 180 0 LOwER SHELL 90 0 & 270 0 (14 OCT 2000)

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

Figure 5-24. Reactor Coolant Controlled Leakage Pumps FLYWH EEL uPPER THRUST BEAR I NG RADIAL BEARING OIL LIFT PUMP +

MOTOR THRUST BEAR I NG MOTOR SHAFT r - - - _ _ MOTOR UNI T MOTOR STATOR ASSEM BLY MAIN LEAD CONDU I T BOll UPPER SE AL HOUSING LOWER RADIAL BEARING ~~j'~Lh..rl------ LOWER SEAL

---....,. HOUSING "APOI{ LEAKAGE TO ATMOSPHERE NO. I I NJECT I ON  ;::::J------ MAIN FLANGE WATER LEAK OFF 14._----COOLI KG WATER PUMP SHAFT OUTL IT COOLING WATER I tlLET THERMAL BARRI ER DISCHARGE '-i4rl~---t~-~--- RAD I AL BE AR IN G NOZZLE ASSEMBLY

......1.------- CASING SUCTION NOZZLE

--fi.::-....L------- IMPELLER (14 OCT 2000)

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

Figure 5-25. Estimated Performance Curve - Controlled Leakage Main Coolant Pump C)

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

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

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(14 OCT 2000)

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

Figure 5-27. BWI Steam Generator STEAM ourU::T "aZZLE SECOtlOIIRY M.l.NWiIY SECONDAAY CYCLONES STEAM DRUM HEm PRIM~Y CYCLOHES STEAM DRUM MAIN F£EOWATEA NOZZLE AUXILIARY FEEOWATER NOZZLE RECIRCULATION NOZZLE FlAT eAR 'U'BENO

~5TRAINT SYSTEM twER LATERAL SlFPORT TRI.N>IHlN INSPECTlctI PORTS 11 SECDNOARY SHELL II LATTICE GRIOS TUElESHEET PRIMM'!' HE,I.O--~ ___..

INLET/ruTLET NJZZLE PRtMARY MANW,o,y (14 OCT 2000)

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

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

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(10 OCT 2009)

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

Figure 5-29. Pressurizer SPHY NOZZLE RELIEF NOZZlE--_ _ _ _ _........~ SAFETY NOZZLE

- - - - - - - MANWAY UPPER HEAD INSTRUMENTATION NOZZLE liFTING TRUNNION SHEll LOWER HEAD HEATER SUPPORT PLATE IHSTRUMEHTATIOH NOZZLE ELECTRICAL HEATER SUPPORT SKIRT SU RGE NOZZLE (14 OCT 2000)

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

Figure 5-30. Typical Steam Generator Lower Lateral Support

~TO REACTOR

¥ESSEL ct

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

y STEAM GENERATOR LUG (TYPICAL 4 PLACES)

/CRANE

./ WALL (14 OCT 2000)

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

Figure 5-31. Typical Steam Generator Upper Support

~ OF REACiOA Vf~SEL

4. EL. 7'1'7". e.k (14 OCT 2000)

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

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 12 34' 0.;), SEAMLESS IO

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

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

5'-8"

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BUMPER NO. 3- BUMPER NO.2

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Ir-- ..

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(14 OCT 2000)

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

Figure 5-34. Typical Reactor Coolant Pump Lateral Support for Loops 3-4 5'-8" REACTOR PUMP LUG; BUMPER NO 3.- NO 2.

CRANE WALL!

x r-- .. -. 3'-1"

-+- -

I _ _ 3'_7'1"

~ _ _.lh-_ _:

(14 OCT 2000)

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

Figure 5-35. Pressurizer Support System Elevation

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OPERATING FLOOR ---,

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--- PRESSURIZER UPPER

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I El. 751 +- 4 II

~ _____ --+ ___ ~~ _

n _ *

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(14 OCT 2000)

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

Figure 5-36. Pressurizer Lower Lateral Support

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

Figure 5-37. Pressurizer Upper Lateral Support PRESSURIZER (T Y PI C LUG AL 4 PLACE. 5)

.../ .. \

IS

~ _______ t" l OF R £ A C iO R BUILDING (14 OCT 2000)

Figure 5-38. Typical Reactor Vessel Support McGuire Nuclear Station

/ r-- - REACTOR VESSEL EL.739'+-O"

- PRIMARY SUPPORT LUG

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SHIELD WALL ~

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~~-~~l~T 3'* g' 3'-9" UFSAR Figure 5-38 (Page 1 of 1)

(14 OCT 2000)

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

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 (14 OCT 2000)