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

"""',"0.'"("-1=,"'-' RE'.

~ ~~~. 1 t~ ' I '"

~"

I'<JSlLITF'lALI'E iB1(;,;2;,'c.L

'l......J~'~2'*T;P~~

~'JEFLI'E (10 OCT 2009)

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

~

.c

~

en PUMP CAPABILITY UJ

/

~

en lOS ca 1.07 x BEST ESTIMATE LL..

PUMP CAPAB I LI TV 0

~

z:

LLJ BEST ESTIMATE SYSTEM ,

<..> RESISTANCE a::

L.I.J 100 Q..

BEST ESTIMb.TE / "

-~,

0

.c w

z:::

E w

~

en 95 SYSTEM RESISTAHCE 0.9 x BEST ESTIMATE-;;"

/ ,

en SYSTEM RESISTANCE" 0

z:

Q..

E

)

Q..

90 t THERMIIL t

BEST t

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 - ....... , ,

.9

" \

\

.8

\

.7 \

\

\

.6 Q

r.&.:

\

N

...I .5

\

~ \

i \

3 .4 \

c

...I C&,

.3

.2

.5 See-- --,

.1 Delay I I

I I

I 0

.5 1 LO I. 1 2.0 - - -........i Sec.

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

~ *

~.I.

=0

",,_0

~ ~.

QYIL

~~~

N N

~

• 1-0 N

. j

~

~

1\

0 I0 c;i 1401

~

0 IL :I

- all N

!II:

I + ~

I i0 III Z

Y

-§

~

N

~

+

i

!l Cc III",

22 I .......

"'a i tl

• ~ ** -*-

N I I I -8 f:jo) f.LONJ.WVJ I 2 3wnJ.Y"JtlWiJ. i:lNiWi:iiW ~O J.Ni .... J.SnrCy OiJ.:lIOikl41 (14 OCT 2000)

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(. .

9 ilIN

\ .) /J' I I I II I I I I I I  !

, I I I

, I '

I I I I II I I I I I I I I I I I N ,

N I I I I , >

2 I I I I II I

=,

~

~

I I! I I II i I  ! I III I! I I ,I

.. II II III i t I I I I

l I' , II

\ I Ii I

II t iii I I 111111 II I II I N

- u I II

~

~

III iI II II I I I  ! !I I I I Ii: It! I o 5

=

III ColI

~

III I 'I ,\ I i I

1II1 : i  !

IIII i~ I:

• I

~ \, I'i~ I I I.

I I.I 1 :

l' ~

• I ,  :

\ ~ ,

1:1 ~'1\ I I '

l' I I I I

I.

I' I

II I I* I 1\~'\ ~I' i I ~ i, j

I I. '

I I;

r I:

I' '

I f .

It:

i N

'" ~~ ...

i II I

1

~

!III , i o o *.. ..

• .-o (14 OCT 2000)

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

220 r--- ---- ---- ---- ---- ----____ ____ ____ _____

~I 200 180 o I I

60 I

I I

~

I o I A I I

~ I

~"

I I

~"

60 6 0 'I'

/

~ ~,,1:> LOWER o

o ...e..- g.,t:J BOUND K, d 20 O~ __ ~ ____ ~ __ ~ ____ ~ __ ~~ __ ~ ____ ~ __ ~

-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

-Z

E:

~ ,8 w

I:

U Z

...,w

~ .6

l:

u

.....I l.J..I W

.....I I.L.

0 w .4 I-

~

~

.....I

<l .2

,0 o 5 10 15 20 LEAKAGE RATE (GPM)

(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- - -

WElD

- 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

-+

e-.

"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)

N C) w Z

~

~

C) t- U-C)

~

~

~

C) ct

~

~

0 ~

< C) w X

~

~

~

< ~

~ C) 0 ~

~

~

~

~

U-C)

~

133~ Nl HSdN aNY OV3H lVl01 (14 OCT 2000)

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

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

..,j Go C

• c

~

~

I It I

~

I Ic I~

"I -- ~

.- t

=

....=

i S

L

- I I

I I

I I

I I I L~

~

~-

c

z:

~

It

• 1 ......

0 c

A- It 8

A-D.

z ....I c

...., c 0

~

=

A- ." ."

(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)

><,,"""iFl-'"'

ce:; '\:fc,",COOiR~

L>,O<O:","L""

~ ~~~T:~~

(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

~f-LJ<{

! Il: PIPE COLUMN - ~"

Il::I UPPER ZIl:: 01 a.. CLEVIS I.J....~

WW II~

-.JZ Lr..J Z0 t;ZII-

~~ wl <<

Z d~ -.J-.J O

Uf-I(/) Z'O

~Iu Oi W w

~

-.J1l:

~,I 00

=.JI- u:f-

~o:: :u

,0 O'e(

<1: ' u... ww

~ct::

~IW (f)I

- LowER

<{II- CLEVIS I

- LOWER CLEVIS t

EL,725' +0" SLAB PVERTICAL PVERTICAL TYPICAL COLUMN ASSEMBLY TYPICAL COLUMN ASSEMBLY FOR FOR THE STEAM GENERATOR THE REACTOR COOLANT PUM P (14 OCT 2000)

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"

/

BUMPER NO. 3- BUMPER NO.2

\

\

\

\.

\

Ir-- ..

-~

(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

~ -

~. - "- ~ ~

'.~. V CRANE WALL PRESSURIZER .~ .....

~~

OPERATING FLOOR ---,

. Q-

./

--- PRESSURIZER UPPER

~r-~ . SUPPORT FRAME L"""" .. '

3"~-~=:=~d~.~~=.1IJ.:::t::.£=~~

1 EL 779 -t-

? to.." -II.

4 ... ..

Ii II II "II II II II II It PRESSURIZER LOWER II SUPPORT FRAME II II II 8i II~

I El. 751 +- 4 II

~ _____ --+ ___ ~~ _

n _ *

+-

(14 OCT 2000)

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

Figure 5-36. Pressurizer Lower Lateral Support

--i*~-----***- -

0::

0

~ ..

~ ., .

~

w 0: \..?

z (3

-.J

.101J p v.'

0 5 I

-('11 c) f-- Q) c*

0 ~

105 .

f I

1

\"

-I"') &>

()

.' *t' r;,

to (14 OCT 2000)

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

\

-+-"""1?'~-!~:(/~

SHIELD WALL ~

llF= - I, t' 1

" - PRIMARY SHIELD WALl PHORI~N T :"L P.HORI LON r AL o ' I I I 0 I I IJ:-= ~ I ~.-o~. ~~:OL T--,-  ::0 t:=::=fl

~ I/0 ~l()--

LI -1 V 0 ii (~; ;; o ~ ~

. - I

,~.

EL.73S.7-l!>

~~-~~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)