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| number = ML11290A239 | | number = ML11290A239 | ||
| issue date = 10/05/2011 | | issue date = 10/05/2011 | ||
| title = | | title = 2011 Updated Final Safety Analysis Report, Rev 16, Chapter 5, Appendix 5B. Figures | ||
| author name = | | author name = | ||
| author affiliation = Duke Energy Carolinas, LLC | | author affiliation = Duke Energy Carolinas, LLC | ||
Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter: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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'l......J~'~2'*T;P~~ | |||
~'''JEF''LI'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 / " | |||
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0 | |||
.c w | |||
::z::: | |||
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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 | |||
" \ | |||
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.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 | |||
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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(. . | |||
:9 ilIN | |||
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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 | |||
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60 6 0 'I' | |||
/ | |||
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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: | |||
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.....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 | |||
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C) t- U-C) | |||
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C) ct | |||
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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 | |||
~ | |||
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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)}} |
Latest revision as of 15:51, 10 March 2020
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\
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~
0 IL :I
- all N
!II:
I + ~
- I i0 III Z
Y
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~
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+
i
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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
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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
220 r--- ---- ---- ---- ---- ----____ ____ ____ _____
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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- - -
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
-+
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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)
><,,"""iFl-'"'
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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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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
\
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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
~ -
~. - "- ~ ~
'.~. V CRANE WALL PRESSURIZER .~ .....
~~
OPERATING FLOOR ---,
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--- PRESSURIZER UPPER
~r-~ . SUPPORT FRAME L"""" .. '
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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
--i*~-----***- -
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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
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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)