ML20309A736
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{{#Wiki_filter:McGuire Nuclear Station UFSAR Appendix 3B. Figures Appendix 3B. Figures
McGuire Nuclear Station UFSAR Figure 3-1 (Page 1 of 1) (14 OCT 2000) Figure 3-1. Wind Pressure Distribution on Reactor Building l 35 E.L.'i37 :z'_,_,;/ **-- CPi::=!D ACTUAL PRESSURE DISTRIBUTION DESIGN PRESSURE DISTRIBUTION--- EL 760-0 \\ ..j \\ I lll{e,,,l"33-_2o' rr: I EL.72'.>*Ci' .110 \\ L-~> -1eo*-o* -LE - l? -1.2 -*l.c, -C., '/*.. ~ \\,,L-J ~*,,\\_--J_: 4 _;*7bn -*J.4 ~;_c -0.4 _pAP,15 J_I,][_ Cpe - -.6 +.3 cos,+ -!l29 cos 2* *. 412 cos 3a -.lli cos 4* +.01~ nos 5o +.061 cos 6e ~.OB& co:s 70 -.00 cos 8e -I.I -1_3 --f 1.2 __ _J PART lll \\--\\-).4 \\ I l.Lo.4 Cpe - -.~6 -.337 cos e +.179 cos 2* -.07 cos 38 -.038 cos 48 +.Olli cos 5e -.ll38 cos 69 -.01)( cos 7e -.013 cos Be /~~::x { ( \\J PAq; IT Cpe ~ -1.15 -0_8 ~A~""T _yz. Cpe ~ -.936 -.O'll cos a+.221 cos 2o +.002 cos Jo .,..002 cos !i8 -.013 cos 60,.018 cos 7o -.008 cos Bo //=~*~\\.1.15 I I I __j I PART 3liI Cpe ~ -1.15 l!INO PRESS !RE DISTRIBUTION ON THE REA TOR BUILDING
McGuire Nuclear Station UFSAR Figure 3-2 (Page 1 of 1) (14 OCT 2000) Figure 3-2. Turbine Building Tornado Wind Distributions
McGuire Nuclear Station UFSAR Figure 3-3 (Page 1 of 1) (14 OCT 2000) Figure 3-3. Fire Protection System Piping Penetration Detail CtJNCecr~ £,UCR.S£M£Nr
McGuire Nuclear Station UFSAR Figure 3-4 (Page 1 of 1) (14 OCT 2000) Figure 3-4. Turbines Missiles Projected Areas (Low Pressure Turbine Rotor Discs) t _.,...-*-~~-~ =... i j Al N.Qli :. REFER TO TABLE 3-15 FOR MISSLE PROPERTIES. TURBINE t\\llSSlLE PROJECTED AREAS ( LOW PRESSURE TU'3BINE
- ROTOR DISCS)
McGuire Nuclear Station UFSAR Figure 3-5 (Page 1 of 1) (14 OCT 2000) Figure 3-5. Loss of Reactor Coolant Accident Boundary Limits CASE I CASE I I CASE Ill CASE l V CASE V OUTGOING LINES WITH NORMALLY CLOSED VALVE s REACTOR COOLANT PIP IN\\ !~RY NOH: PPESSURIZER SAFEH VALVES ARE INCL1JDED 1*1iJDEREIS CASE. OUTGOING LINES WITH NORAALLY OPEN VALVES FAIL CLOS ED OR FAIL-AS-IS VALVES RESTAA INT NOTE: -1HE REACTOR COOLA,,T P~,,ip NO. l SEAL IS ASSUMED -: 0 BE EQUIVALENT -:0 f I RS-, VALVE. INCOMING LINES NORMALLY WITH FLIJw NO. NO. 2 _j_ B JU~CAf'.Y TEST CONNECT I ON INCOMING LINES NORMALLY WITHOUT FLOW TEST CONNECT I OtJ (MEAMS OF VER I FY I ilG THAT CHECK VALVE IS CLOSED; ALL i:lSlRUMEN"fATIJil -:-UBiNG Mm PlSTRUMENTS CO"lNECTED DIRECTL': TO THE REACTOR COOLM:T SYSTEM IS cm;s1DERED AS A BOUNDARY. HOWEVER, A BREAK WITl-'lrl *:HIS sou*:DARY RESULTS l"I A RELATl'JEL SMALL,:Low WHICH CA', *:ORr,Vl,LL'f SE MADE ' 1P WIT:l "f'-IE CHARG:::G s-s-*E,4.
McGuire Nuclear Station UFSAR Figure 3-6 (Page 1 of 1) (14 OCT 2000) Figure 3-6. Location of Postulated Breaks f'lAN VIEW ? OO<OTES BA.EAK lctATtO, ElE'JATIOH Note: RcCCRtJOeS 3 and 4 provtde u,., msk for eliminatmg lhe prenolWf postulated ffildor-coolant 6j'stem pipe breaks with the uce,pllon or loose b~b "t brtnclt colllltt(ions. REACTOR PRE5SUl!E VESSEL
McGuire Nuclear Station UFSAR Figure 3-7 (Page 1 of 1) (14 OCT 2000) Figure 3-7. Analytical Method for Resolving Pipe Break Consequences Identify High and Moderate Energy Piping Meeting Failure Criteria I Identify Safety Re lated Equipment, Structures and Components (Targets) IP!pe Whip I Jet Impingement I Env i ronmen ta 1 Effects Identify Identify Identify Unacceptable Unacceptable Unacceptable Interactions Interactions Interactions I I I Determine Special ldenti-Determine Special ldentl* Determine Special ldenti-fled Problem Areas Due fled Problem Areas Due fled Problem Areas Due to Pipe Whip to Jet Impingement to Environmental Effects I I Identify Piping Fa i I ure Identify Piping Failure Identify Piping Failure Locations, Types and Locations, Types and Locations, Types and Orientations Orientations Orientations I I I Determine Extent Determine Jet Determine Environmental of Pipe Whip Characteristics Conditions I I I Develop Pipe Whip Detennine Jet Impinge-Compare Environmental Interaction Matrix f1 ment Interaction Matrix... Conditions With Design I 1 Conditions I Evaluate Rerouting or Evaluate Rerouting, Develop Environmental Structural Barriers ~ Structural Barriers or Effect Table Additional Restraints I I I Locate Pipe Whip i,.. Locate Jet Deflectors Evaluate Rerouting, lso-Restraints Barriers latlon or Venting for I Structures and/or Determine Pipe Whip Determine Jet Deflector Components I Restraints Loadings Barri er Loadings Revise Design Criteria i I I for Structures and/or Prepare Pipe Whip Prepare Jet Deflector Components Restraint Structural Barrier Structural Design Drawings Design Drawings
McGuire Nuclear Station UFSAR Figure 3-8 (Page 1 of 1) (14 OCT 2000) Figure 3-8. Deleted per 2001 Update
McGuire Nuclear Station UFSAR Figure 3-9 (Page 1 of 1) (14 OCT 2000) Figure 3-9. Main Steam and Feedwater Routing Plan Outside Containment. See 3-10 for Elevation View. I lJ l __ lUJ EL -, i,4*7 1, '
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McGuire Nuclear Station UFSAR Figure 3-10 (Page 1 of 1) (14 OCT 2000) Figure 3-10. Main Steam and Feedwater Routing Elevation Outside Containment [Historical information, not required to be revised.] 46 47 R[t,C:T'.lR ?.clc, UNIT I 4'1 51 5 \\ ~ ~ :---- /ff IJ:i,*o I ___ J l _J M1ss11..:_ ARRtE. RooP-EL
McGuire Nuclear Station UFSAR Figure 3-11 (Page 1 of 1) (14 OCT 2000) Figure 3-11. Main Steam Routing Plan Outside Containment ft
McGuire Nuclear Station UFSAR Figure 3-12 (Page 1 of 1) (14 OCT 2000) Figure 3-12. Main Steam Routing Elevation Outside Containment Nearest Reactor Building Wall 7
McGuire Nuclear Station UFSAR Figure 3-13 (Page 1 of 1) (14 OCT 2000) Figure 3-13. Main Steam Routing Elevation Outside Containment Farthest From Reactor Building Wall _j l I i i:-J,l,,,.lt1PriM11rf'.Jltlltll't_/ I i I 1 I I ,--~; --------~--- #~- !i I 4 41. -,,o'.. I I"':"------'~ *- ~ I I[ I ~ ~~~- --#-!----~-,..~----'-----------'
McGuire Nuclear Station UFSAR Figure 3-14 (Page 1 of 1) (14 OCT 2000) Figure 3-14. Main Feedwater Routing Plan Outside Containment
McGuire Nuclear Station UFSAR Figure 3-15 (Page 1 of 1) (14 OCT 2000) Figure 3-15. Main Feedwater Routing Elevation A-A Outside Containment
McGuire Nuclear Station UFSAR Figure 3-16 (Page 1 of 1) (14 OCT 2000) Figure 3-16. Response Acceleration Spectra [Historical information, not required to be revised.] i i
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McGuire Nuclear Station UFSAR Figure 3-18 (Page 1 of 1) (14 OCT 2000) Figure 3-18. Response Acceleration Spectra [Historical information, not required to be revised.] c r * -1 i.; V) 0.. 0.. I V, 1/1 uJ I
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McGuire Nuclear Station UFSAR Figure 3-19 (Page 1 of 1) (14 OCT 2000) Figure 3-19. Multi-Degree of Freedom System with Support Motion lllr ffir .._ __...i Yr Ys
McGuire Nuclear Station UFSAR Figure 3-20 (Page 1 of 1) (27 MAR 2002) Figure 3-20. Reactor Building Interior Structure - Mass Model [Historical Information, not required to be revised.]
McGuire Nuclear Station UFSAR Figure 3-21 (Page 1 of 1) (27 MAR 2002) Figure 3-21. Auxilary Building Mass Model [Historical Information, not required to be revised.]
McGuire Nuclear Station UFSAR Figure 3-22 (Page 1 of 1) (14 OCT 2000) Figure 3-22. Reactor Building 1st and 2nd Horizontal Mode Shapes EL. 722' + 6 11 !SI HORIZONAL MODE rl =4.9 CPS __ EL. 722'+6" 2~ HORIZONTAL MODE +2 = 13. 5 CPS
McGuire Nuclear Station UFSAR Figure 3-23 (Page 1 of 1) (14 OCT 2000) Figure 3-23. Reactor Building 1st and 2nd Vertical Mode Shapes EL.722'+6' EL.722+6" 1.s..r VERTICAL MODE 2.t:11 VERTICAL MODE f"1 = ll.82 CPS ~ *17,50 CPS
McGuire Nuclear Station UFSAR Figure 3-24 (Page 1 of 1) (14 OCT 2000) Figure 3-24. Reactor Building - Shear Force (lb/in) Due to SSE [Historical information, not required to be revised.] --=---7.9 135.1
McGuire Nuclear Station UFSAR Figure 3-25 (Page 1 of 1) (14 OCT 2000) Figure 3-25. Reactor Building - Meridional Force N0 (lb/in) Due to SSE [Historical information, not required to be revised.] 2448.9 42L5 396.6
McGuire Nuclear Station UFSAR Figure 3-26 (Page 1 of 1) (14 OCT 2000) Figure 3-26. Reactor Building - Meridional Moment M0 (lb/in) Due to SSE [Historical information, not required to be revised.] 1058,3
McGuire Nuclear Station UFSAR Figure 3-27 (Page 1 of 1) (14 OCT 2000) Figure 3-27. Reactor Building - Membrane Shear N (lb/in) Due to SSE [Historical information, not required to be revised.] 7.3 824.3.. 38B2.7-.......::;;. ______
McGuire Nuclear Station UFSAR Figure 3-28 (Page 1 of 1) (14 OCT 2000) Figure 3-28. Reactor Building-Hoop Force N0 (lb/in) Due to SSE [Historical information, not required to be revised.] I271.I 1715.6 416.3
McGuire Nuclear Station UFSAR Figure 3-29 (Page 1 of 1) (14 OCT 2000) Figure 3-29. Reactor Building-Hoop Moment M0 (in.lb/in) Due to SSE [Historical information, not required to be revised.] 2414.. 8 16335.0
McGuire Nuclear Station UFSAR Figure 3-30 (Page 1 of 1) (14 OCT 2000) Figure 3-30. Containment Interior Structure, First Four Horizontal Mode Shapes, North-South Direction MODE I MODE 2 f=1 = 8.1 CPS f2 = 20.46 CPS MODE 3 f3~37.51 CPS MODE 4 f4 = 47.00 CPS
McGuire Nuclear Station UFSAR Figure 3-31 (Page 1 of 1) (14 OCT 2000) Figure 3-31. Containment Interior Structure, First Four Horizontal Mode Shapes, East-West Direction MODE I MODE 2 MODE 3 MODE 4 +1 = J_I CPS +z = 19.42 CPS +3 = 36.48 CPS +4 = 44.03 CPS
McGuire Nuclear Station UFSAR Figure 3-32 (Page 1 of 1) (14 OCT 2000) Figure 3-32. Containment Interior Structure - First Two Vertical Mode Shapes [Historical information, not required to be revised.] MODE I MODE 2 +1 =- 19.65 CPS tz = 48.09 CPS
McGuire Nuclear Station UFSAR Figure 3-33 (Page 1 of 1) (14 OCT 2000) Figure 3-33. Containment Interior Structure Response Loads Due to SSE in the North-South Direction [Historical information, not required to be revised.] WT_lJ_ Tl WTII
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McGuire Nuclear Station UFSAR Figure 3-34 (Page 1 of 1) (14 OCT 2000) Figure 3-34. Containment Interior Structure Response Loads Due to SSE in the East-West Direction [Historical information, not required to be revised.] WT 13 6-45 O.6ZI O 0093 644 0.0 'f'{__ 6-4& 0.571 OOOBB n 1292 15,563 WT 11 754 0.519 0 008,2 []_2040 ~ 15,895 _W_T 10 -4 0.-47!, 0.0076 WT 1013 0.-4 4 0.0073 WT R t,.110 ~ 0.396 0.0062 ~ wn 1 Io.,,. / I ooo ~ -~----
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McGuire Nuclear Station UFSAR Figure 3-35 (Page 1 of 1) (14 OCT 2000) Figure 3-35. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 738.22 i Hh. i I I fH,. d 'J flJ I
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McGuire Nuclear Station UFSAR Figure 3-36 (Page 1 of 1) (14 OCT 2000) Figure 3-36. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 768.22 I I I l I / I I I I I I I i I I ~ I / -*-"---~-----~- I------------ I t . ---- ( ') rn D 0 ~ z 0 w LL, U"") -*7 z L-----". I C '~ ~-~-< D
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McGuire Nuclear Station UFSAR Figure 3-37 (Page 1 of 1) (14 OCT 2000) Figure 3-37. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 789.47 I / ( ) ,1---.-T-- ( 1-----.---..---~--- ,,v ID ~ J
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McGuire Nuclear Station UFSAR Figure 3-38 (Page 1 of 1) (14 OCT 2000) Figure 3-38. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 817.92 / r ) {
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McGuire Nuclear Station UFSAR Figure 3-39 (Page 1 of 1) (14 OCT 2000) Figure 3-39. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 841.85 ---t----- i -i--T----*-- ~~l 0 0,- (.f; ! '=' 0 I._, 2 ---*1-- 0 L_! L,.,... (J7 0 ci o 0: L,.,... (L
McGuire Nuclear Station UFSAR Figure 3-40 (Page 1 of 1) (14 OCT 2000) Figure 3-40. Reactor Building and Base Rock Finite Element Representation a: =o
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McGuire Nuclear Station UFSAR Figure 3-41 (Page 1 of 1) (14 OCT 2000) Figure 3-41. Reactor Building First Horizontal Mode 11 11 10 10 \\ I 9 9 I MODE FREQ. =4 997 CPS NODE FIXED BASE - R z I 0.1 - 0.6 2 83 -4.0 3 17.6 - 8.8 4 26.6 -12.9 5 36.3 -16.3 6 4 6.6 -18.9 7 56.8 -2 I.0 8 66 8 -22.4 9
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- R DISPLACEMENT NORM ALI ZED TO 100.
McGuire Nuclear Station UFSAR Figure 3-42 (Page 1 of 1) (14 OCT 2000) Figure 3-42. Reactor Building Second Horizontal Mode NODE I 2 3 4 5 6 7 8 9 10 I I 12 13 14 I 13 j I 121 I 10 / 11 I 10 I / I 8 8 *...., 7 7 *, '\\ 6 6 s 4 / /4 3 z --
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FIXED BASE-SOIL INTER.--- R z R z + 0.1 - 0.4 -12.1 - 0. 7 -27.3 - 3.4 -39.9 -4.3 -66.7 -10.6 -75.3 -11.8 -9S.0 -20.1 -97.5 -21.4 -108.3 -37.3 -lOS.6 -32.4 -105.S -43,2 -99. I -43.8 -87. 5 -54. 7 -79.2 -54.6
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McGuire Nuclear Station UFSAR Figure 3-43 (Page 1 of 1) (14 OCT 2000) Figure 3-43. Reduced Model of Interior Building Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, East-West Direction, Elevation 738.22 _/ L,--- r -:, L---- -~ _,--P ? 1..--l ~ ~ < ___s-1/2_, ~ i....... ~ i/ ) V ~ \\ I I J I / 0 0 0 r::, C, ('J er, c:, Ci 0
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McGuire Nuclear Station UFSAR Figure 3-44 (Page 1 of 1) (14 OCT 2000) Figure 3-44. Combined Interaction Model Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, East-West Direction, Elevation 738.22 I ) ) / _/ i.----- r ~. - ~ ~ ? -_.I ~ ~ <: _____r-D, 1/2_, _) i.......,_ ~ "' \\ 9S"O 0i,*o on*o cE'rJ ti(*o 91*0 so*o ~ NI *~s 'NOI1~8373JJ~ 3SNOdS38
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McGuire Nuclear Station UFSAR Figure 3-45 (Page 1 of 1) (14 OCT 2000) Figure 3-45. Reduced Model of Interior Building Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, East-West Direction, Elevation 777.60 ~- I I 1 I I' I i ' I /: I I I I I I I I r.,
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McGuire Nuclear Station UFSAR Figure 3-46 (Page 1 of 1) (14 OCT 2000) Figure 3-46. Combined Interaction Model Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, East-West Direction, Elevation 777.60 i / ( ) / ,...,v ) /' ) / --L---- -~ I\\ l \\ I I Dh"c oo*c 09" I oc* l 08'0 Oh"O ~ N[ 't!S 'N[Jilt!8:373JJ\\:J 3SN JS.=lt! I I 0 0 CJ lf) () w 0 w 0 C"l 0 0 0 0 00 *cP ~ 0 z D u ..LI Ul z CJ D a: l1J (L
McGuire Nuclear Station UFSAR Figure 3-47 (Page 1 of 1) (14 OCT 2000) Figure 3-47. Reduced Model of Interior Building Response Acceleration Spectrum, Damping = 0.02, Reactor Building, North-South Direction, Elevation 768.30 / / ( ) ( ~ > __,,,-5 ~
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McGuire Nuclear Station UFSAR Figure 3-48 (Page 1 of 1) (14 OCT 2000) Figure 3-48. Combined Interaction Model, Response Acceleration Spectrum, Damping = 0.02, Reactor Building, North-South Direction, Elevation 768.30 I i I / I ( ) I I ( I i ~ 5 t ) ~ "' \\~ 1 Oh* l IJ?
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McGuire Nuclear Station UFSAR Figure 3-50 (Page 1 of 1) (14 OCT 2000) Figure 3-50. Dynamic Analysis Model of Typical Piping System ~ ~ 43 (47 ,_ ~} 2"~SCH.40 y N,t z:~x REF~ co-ORDINAT~S (0,752.01,0) A'T.JT.l ~., -..__g+ @ ~, 11 ""Si::,~ i di~ ~ lcas1 O* ~ ~* r;:::;-;i e!J LEGEND jcosj ]: = JOINT NAME S"'.'RAIGHT MEMS.ER NAME = CURVED MEMBER. N.61v1::
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McGuire Nuclear Station UFSAR Figure 3-52 (Page 1 of 1) (14 OCT 2000) Figure 3-52. Typical Envelope Horizontal Response Spectra for Analysis Comparison 17,S --------------------------- 15,0 12.S (/} z ~.. U\\
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McGuire Nuclear Station UFSAR Figure 3-53 (Page 1 of 1) (14 OCT 2000) Figure 3-53. Typical Verticle Response Spectra for Analysis Comparison o.as....... ------------------------7 Cf) 0.25' ~-z
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McGuire Nuclear Station UFSAR Figure 3-54 (Page 1 of 1) (14 OCT 2000) Figure 3-54. Typical Reactor Building and Containment Vessel Details ~ A(.ICTpR *., Are ANQ 9'MMM'.Ht STIII.JCTI..AAL.P.JTtN: N i REACTOR AN REACTOR BLOG PLAN UNIT 1 UNIT2 PP.HAN A8ClUTN-SCENTERLINE FIGURE 3-54 TYPICAL REACTOR BUILDING AND CONTAINMENT VESSEL DETAILS 13 APRIL 201!1 I
McGuire Nuclear Station UFSAR Figure 3-55 (Page 1 of 1) (14 OCT 2000) Figure 3-55. Reactor Building, Base Slab, Reinforcing, Bottom Radial Bars, Bottom Layer El. 717' + 4 3/4" I I i I
McGuire Nuclear Station UFSAR Figure 3-56 (Page 1 of 1) (14 OCT 2000) Figure 3-56. Reactor Building, Base Slab, Reinforcing Bottom Radial Bars, Top Layer Elevation 717' + 7 1/2" 11£ACTOR BUILC I ~G - LtllT 2 BASE SLAB -REINFORC ING EIOTTCNl!"'llllll. B/:ll!S TOPLAYEREL. 717'*7 112"
McGuire Nuclear Station UFSAR Figure 3-57 (Page 1 of 1) (14 OCT 2000) Figure 3-57. Reactor Building, Base Slab, Reinforcing Top Radial Bars, Bottom Layer Elevation 721' + 10 3/4" .-,.*---f *'** i~,t ~r*ro:.i, Gt j i ~ j I \\
McGuire Nuclear Station UFSAR Figure 3-58 (Page 1 of 1) (14 OCT 2000) Figure 3-58. Reactor Building, Base Slab El. 723' + 0", Reinforcing, El. 717' +6", El. 717' +9", 722' + 0" and El. 722' + 3" " *, '] p ln!J' 1rnn"cl" **" ~ I:ii ~ 0}) I*
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McGuire Nuclear Station UFSAR Figure 3-61 (Page 1 of 1) (14 OCT 2000) Figure 3-61. Reactor Building, Concrete Shell, Developed Elevation - Reinforcing El. 722 + 6 Thru El. 875 + 4 1/2 1,
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McGuire Nuclear Station UFSAR Figure 3-63 (Page 1 of 1) (14 OCT 2000) Figure 3-63. Reactor Building, Inner Plan of Dome, Reinforcing z
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McGuire Nuclear Station UFSAR Figure 3-65 (Page 1 of 1) (14 OCT 2000) Figure 3-65. Analysis of Reactor Building Penetration Space Frame Mathematical Model .....................,_..... *r**.. *-------*----*-.. --*-- 1 11 ..,.JI.
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McGuire Nuclear Station UFSAR Figure 3-66 (Page 1 of 1) (14 OCT 2000) Figure 3-66. Containment Vessel and Equipment Anchorage Details C:\\fsar\\Fig3-66.dgn 01/22/01 06:35:45 AM . t ~.-,... -l!
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McGuire Nuclear Station UFSAR Figure 3-67 (Page 1 of 2) (06 OCT 2003) Figure 3-67. Personnel Lock and Equipment Hatch Details ~-t: ~__q..cD.
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McGuire Nuclear Station UFSAR Figure 3-68 (Page 1 of 1) (13 APR 2008) Figure 3-68. Typical Penetration Details Ylr~ DH YiYl'AJ<<I n:MM$l ffl9Ml!t r<<NN'ilBIMllflflfJMffi Notes:
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McGuire Nuclear Station UFSAR Figure 3-69 (Page 1 of 1) (14 OCT 2000) Figure 3-69. Reactor Building Containment Vessel, Cylinder Plate Layout and Penetration Location i;i'! .-:* :~:'7::* , 'f.l...~T"'1L.t...
- McGuire Nuclear Station UFSAR Figure 3-70 (Page 1 of 1)
(06 OCT 2003) Figure 3-70. Containment Vessel Penetration Details ..!::1...!!..H.= ~ _................,,..,,....... '""--~ ~~...,._...,-,~...,.,--e---- ~;;;::::-~;~;.t~$
McGuire Nuclear Station UFSAR Figure 3-71 (Page 1 of 1) (14 OCT 2000) Figure 3-71. Reactor Building Containment Vessel, Base Liner Plate, Anchors and Embedded Items
McGuire Nuclear Station UFSAR Figure 3-72 (Page 1 of 1) (14 OCT 2000) Figure 3-72. Reactor Building Containment Vessel, Base Liner Plate, Test Channel Layout + ---~~--,.,. ~~ -.,,:,,,,,.,*,:., -... ) rl?Vf#L "rrs~~C::::.:-""** £eNNE&7"lON
McGuire Nuclear Station UFSAR Figure 3-73 (Page 1 of 1) (14 OCT 2000) Figure 3-73. Containment Vessel As Built Overall Dimensions and Plate Thicknesses HEMISPHERICAL DOME 252' EL 894'-t-3" E VERTICAL CYLINDER 1.o'TH'K EL. 723+0H FLAT LINER PLATE
McGuire Nuclear Station UFSAR Figure 3-74 (Page 1 of 1) (14 OCT 2000) Figure 3-74. Buckling Factors of Safety Comparison Between the McGuire and Catawba Stations rt -T 1 I I ~~ ,1 J--- ml SPRING LINE-, ;_.
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McGuire Nuclear Station UFSAR Figure 3-75 (Page 1 of 1) (14 OCT 2000) Figure 3-75. Break in Element No. 1 - Ice Condenser, Transient Pressure in Compartments 7, 8, and 9 ~ . ~ ' ~ ~' ', I
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McGuire Nuclear Station UFSAR Figure 3-81 (Page 1 of 1) (14 OCT 2000) Figure 3-81. Break in Element No.1 - Ice Condensor, Pressure Transients in Compartments 25, 29, and 33 14 12 C) f 10 11.J Cl:
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McGuire Nuclear Station UFSAR Figure 3-82 (Page 1 of 1) (14 OCT 2000) Figure 3-82. Fourier Series Representation of Dynamic Loads ---ACTUAL Pft[SSURE CURVE - - - - - FOUAIE II: R[PRESENTA TION IOI Cl) Q. / I ~t I /1 I\\ ' ' '\\ \\ U) r =*o II)
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McGuire Nuclear Station UFSAR Figure 3-83 (Page 1 of 1) (14 OCT 2000) Figure 3-83. Compartment Layout - Plan at Equipment Rooms Elevation COMPART 31 \\ I
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McGuire Nuclear Station UFSAR Figure 3-84 (Page 1 of 1) (14 OCT 2000) Figure 3-84. Compartment Layout - Containment Section View TOP OF ICE 25 2~, 21, 18, 15, 12 9 2 3, 20. 17, I ~, I l 8 22, 19.16, 13, 10 1,2,3,~,5 & 6 27,29,31,34, 35,36,37 7 26,28 SECTION "A-A" 25 UPPER COMPARTMENT 25 33 GATE 25 REFUELING CANAL D 25
McGuire Nuclear Station UFSAR Figure 3-85 (Page 1 of 1) (14 OCT 2000) Figure 3-85. Layout of Containment Shell 25 TOP OF I~ 9 I 12 I 15 l 18 l 2 I ~ 24 '"-"-,---t- _____ J_ __ _i_ __ t---- 8 I I I 14 I 17 I 20 23 __ 1_ __ 1 ____ L __ -1_ __ L __ _ rr, _ l ,a 1 13 16 19 22 ACC 34 FAN 27 ACC 35 INSTR. RM. 29 ACC 36 FAN 31 ACC 37 7 26 I I I 28 I PI PE TRENCH I I= TIGHT SEAL BETWEEN LINER AND COMPARTMENTS 30 I I 32
McGuire Nuclear Station UFSAR Figure 3-86 (Page 1 of 1) (22 APR 2017) Figure 3-86. Civil-Environmental Division Partial Organizational Chart [HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED] I Principal Engineer Environmental Section r Principal Engineer Civi 1 Projects Engineer Group (A) Leader Chief Engineer C ivi 1-Envi ronmental Division Principal Engineer Structural Sectior Engineer Group (B) Leader I I ~ Principal Engineer Civil Projects Designer Supervisor (Technicians and Drafting} I Senior Designer Architectural and Layout
McGuire Nuclear Station UFSAR Figure 3-87 (Page 1 of 1) (14 OCT 2000) Figure 3-87. Reactor Building, First Horizontal Mode, f = 4.96478 cps (Kalnin's) EL.722+6 i-------------......ii
McGuire Nuclear Station UFSAR Figure 3-88 (Page 1 of 1) (14 OCT 2000) Figure 3-88. Reactor Building, First Horizontal Mode, f = 4.97 cps (Finite Elements) r*---- --- EL 72; +6
McGuire Nuclear Station UFSAR Figure 3-89 (Page 1 of 1) (14 OCT 2000) Figure 3-89. Containment Vessel, First Horizontal Mode, f = 9.284 cps (Kalnin's) EL.725+0
McGuire Nuclear Station UFSAR Figure 3-90 (Page 1 of 1) (14 OCT 2000) Figure 3-90. Containment Vessel, First Horizontal Mode, f = 9.3234 cps (Finite Elements)
McGuire Nuclear Station UFSAR Figure 3-91 (Page 1 of 1) (14 OCT 2000) Figure 3-91. Containment Vessel, Second Horizontal Mode, f = 25.69 cps (Kalnin's) EL 725+C'
McGuire Nuclear Station UFSAR Figure 3-92 (Page 1 of 1) (14 OCT 2000) Figure 3-92. Containment Vessel, Second Horizontal Mode, f = 25.660 cps (Finite Elements) .~- (._; + Li ) i\\J r- _J w
McGuire Nuclear Station UFSAR Figure 3-93 (Page 1 of 1) (14 OCT 2000) Figure 3-93. Containment Vessel, First Vertical Mode EL.725+0
McGuire Nuclear Station UFSAR Figure 3-94 (Page 1 of 1) (14 OCT 2000) Figure 3-94. Containment Vessel, First Vertical Mode EL.7.-:7 5+0
McGuire Nuclear Station UFSAR Figure 3-95 (Page 1 of 1) (14 OCT 2000) Figure 3-95. Portion of the Operating Deck
McGuire Nuclear Station UFSAR Figure 3-96 (Page 1 of 1) (14 OCT 2000) Figure 3-96. Operating Deck Strudl Finite Elements Representation FULL OPERATING DECK £LAS (FEM) REPRESENTATION CATAWBA NUCLEAR STATION PSAR Figure 3.8.3-10 Amendment 4 (flew)
McGuire Nuclear Station UFSAR Figure 3-97 (Page 1 of 1) (14 OCT 2000) Figure 3-97. Comparison of Program Results Fixed Boundary Conditions c.i, 20 1-z 2, 10 ~ - --...... v, 10 15 XO ~-----+---~,,,.-..+-~-+-+-~l-..+--1-1......... j~*----.........,_..,___ '.x -10 I-
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McGuire Nuclear Station UFSAR Figure 3-98 (Page 1 of 1) (14 OCT 2000) Figure 3-98. Comparison of Program Results Pinned Boundry Conditions en ~ 20-z 3 10-en x ~ 0 X 5 ~ ,c( -20 1-ffi ~ / / / / / ~ 10 15 SECTION A-A SECTION B-B 20 FEET ___ STRUDL _ELAS 30 FEET ___ STRUDL __ ELAS
McGuire Nuclear Station UFSAR Figure 3-99 (Page 1 of 1) (14 APR 2005) Figure 3-99. Pressure Seals and Gaskets 4r*~ ~ ~ I~=--~ .... --.:.. ~- REACTORSUILDIN!l-UNIT!lo2 PRESSURESEALSIGASICET5 StiEET*I FIG.NO. 3-99 l4A?RIL21illil5
McGuire Nuclear Station UFSAR Figure 3-100 (Page 1 of 1) (14 OCT 2000) Figure 3-100. Pressure Seals and Gaskets This figure is currently unavailable in an electronic format. It can be located in a hardcopy version of the UFSAR.
McGuire Nuclear Station UFSAR Figure 3-101 (Page 1 of 1) (14 OCT 2000) Figure 3-101. Pressure Seals and Gaskets -nr------ 1 II '~ 11\\ I I \\ -~---'-'----_j_---'-.,. II f IH----H-+--++---+- ~: __ j ~ I~ *1 : / Ps:u!=1eC11c1'fiNf\\terrmwll ~---*-., -----
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McGuire Nuclear Station UFSAR Figure 3-102 (Page 1 of 1) (14 OCT 2000) Figure 3-102. Diesel Generator Area, General Arrangement Floor Plan, El. 736 +6, Roof Plan, El. 764 + 7 Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-103 (Page 1 of 1) (14 OCT 2000) Figure 3-103. Diesel Generator Area, General Arrangement Cross Section Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-104 (Page 1 of 1) (14 OCT 2000) Figure 3-104. Auxiliary Building, Fuel Building, General Arrangement Plan at El. 760+6 Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-105 (Page 1 of 1) (14 OCT 2000) Figure 3-105. Auxiliary Building, Fuel Building, General Arrangement Plan at El. 778+10 Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-106 (Page 1 of 1) (14 OCT 2000) Figure 3-106. Auxiliary Building, Fuel Building, General Arrangement, Longitudinal Section Thru Fuel Pool Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-107 (Page 1 of 1) (14 OCT 2000) Figure 3-107. Auxiliary Building, Fuel Building, General Arrangement, Transverse Section at Cask Area Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-108 (Page 1 of 1) (14 OCT 2000) Figure 3-108. Auxiliary Building, Floor El. 733 + 0, General Arrangement, Battery Room Plan Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-109 (Page 1 of 1) (14 OCT 2000) Figure 3-109. Auxiliary Building, El. 750 + 0, General Arrangement, Cable Room Plan Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-110 (Page 1 of 1) (05 APR 2011) Figure 3-110. Auxiliary Building, El. 767 + 0, General Arrangement, Control Room Plan Security-Related Information - Figure Withheld Under 10 CFR 2.390
McGuire Nuclear Station UFSAR Figure 3-111 (Page 1 of 1) (14 OCT 2000) Figure 3-111. Reactor Building Foundation and Its Connection to Reactor Building Shell and Crane Wall (Reinforcement Details) ',) I I ' \\
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McGuire Nuclear Station UFSAR Figure 3-112 (Page 1 of 1) (14 OCT 2000) Figure 3-112. Reinforcement Arrangement Between the Auxiliary Building Foundation and a Typical Vertical Wall I \\ ~ 'Q, \\:, t . \\_. __ ii; ~ r -f: \\ <O 1,1 \\ ~ ' t ti; f 3 ti; ~It,.: j i'~ i*--*
McGuire Nuclear Station UFSAR Figure 3-113 (Page 1 of 1) (14 OCT 2000) Figure 3-113. Vibration Checkout Functional Test Inspection Points I -~J /, . I // ~., \\ \\ /
McGuire Nuclear Station UFSAR Figure 3-114 (Page 1 of 1) (14 OCT 2000) Figure 3-114. Vibration Checkout Functional Test Inspection Points FEATURES TO BE EXAMINED 1 THERl()COUPLE COrlDUIT CLAMPS INSIDE THE 19 OUTLET NOZZLE INTERFACE SURFACE CONO rT ION. THER~COUPLE COLUIIN. 2() NElJTR0rl SHIELO PANEL DOIIEL PIN COVER PLATE 2 Cl RCUIT SWAGELOK FITTINGS, THEIR BANDlNGS, WELDS ANO THE TAB TVPE LOCKS. 21 NElJTRON SHIELD PMEL SCREW LOCKING DEVICES. 3 CLAM? ARRAN~EMENTS AT THE MOUNTING BRACKET LOCATIONS, 22 INTERFACE SURFACES AT THE SPACER PADS ALONG THE TOP AND BOTTOM ENDS OF THE NEUTRON PANELS. 4 PLUG TO cormun WELD AT THE FOUR SUPPORT COLUMNS ADJACENT TO THE THERMOCOUPLE COLUMNS. 23 BAFFLE ASSEll!LY SCREW LOCKI~G ARRANGEMENTS AT THE TWO TOP AND THE TWO BOTTOM FORMER 5 ACCESSIBLE ANGLE CONDUIT CLAMPS INSIDE THE ELEVATIONS. UPPER SUPPORT COLUM'IS, 24 LOWER CORE PLATE TO CORE BARREL FLAIIGE SCREW 6 ACCESSIBLE WELD JOllffS AT THE THERl'<<JCOUPLE LOCKING OEVICES ACCESSIBLE AT THE 0°, 90°, STOP FOR THE SELF INSTRUMENTED COLUMNS. 180°, AND 270° AXES. 7 WELD JOINTS Drl /\\CCESSIBLE SUPPORT COLUMN MID 25 CORE SUPPORT COLUt1NS AND THEIR SCREW LOCKING MI xrnG DEVICE GUSSETS (THERMOCOUPLE SUPPORT
- DEVICES, HARDWARE).
26 CORE SUPPORT COLUMN ADJUSTING SLEEVES. 8 RIGIDITY OF EXPOSED PORTION OF THERMOCOUPLE CONDUIT RUNS, AT ACCESSIBLE LOCATIONS. 27 ACCESSIBLE (2) INSTRUMENTATION GUIOE COLUMN LOCKING COLLARS NEAREST THE MANWAV. 9 RIGIDNESS OF THE ACCESSIBLE PROTRUDING THERMOCOUPLE TIPS. 28 LOCKING DEVICES AND CONTACT OF THE CRUCIFORM SHAPED BOTTOM rnsTRUHENTATION GUIDE COLUltlS 10 THERr()COUPLE COLUMN AND GUIDE TUBE SCREW WHERE ATTACHED TO THE CORE SUPPORT ANO TIE LOCKING DEVICES. PLATES. 11 ACCESSIBLE SUPPORT COLUMN, MIXING DEVICE, 29 LOCKING DEVICES OF THE SECONDARY CORE SUPPORT ORIFICE PLATE, AND CORE PLATE INSERT BUTT COLUt1NS AT THE CORE SUPPORT, TIE PLATE SCREW LOCKING DEVICES. Arm BASE PLATE, 12 UPPER CORE PLATE IIISERTS. 30 RADIAL SUPPORT KEY WELDS. 13 DEEP BEAl1 WELDS AT THE SKIRT AND AT THE OUTER 31 RADIAL SUPPORT KEY LOCKING ARRANGEMENTS AND HOLLOW ROUNDS, BEARING SURFACES, 14 11.CCE!>:HDLE 6UIDI: TUD1; li[LDS, Ji! HEAD AtlO VESSl;L, AL.IGNING Pirt SCREW LOCKirUi DEVICES AND BEARING SURFACES. 15 UPPER BARREL TO FLANGE GIRTH WELD. 33 IRRADIATION s*PECIMEN GUIDE SCREW LOCKING 16 UPPER BARREL TO LOWER BARREL GIRTH WELD. DEVICES AND DOWEL PINS 17 LOWER BARREL TO CORE SUPPORT GIRTH WELD. 34 VESSEL NOZZLE INTERFACE SURFACE CONDITION. 18 UPPER CORE PLATE ALIGNING PIN WELDS AND 35 VESSEL CLEVIS LOCKING ARRANGEMENTS AND BEARING BEARING SURFACES, SURFACES.
McGuire Nuclear Station UFSAR Figure 3-115 (Page 1 of 1) (14 OCT 2000) Figure 3-115. Time-History Dynamic Solution for LOCA Loading 6271.1-21 REACTOR COOLANT EQUIPMENT LOCA FORCING LOOP SUPPORT STRUCTURE FUNCTIONS LOOP GEOMETRY SUPPORT STRUCTURE AND MODEL STIFFNESS MATRICES FOR STATIC AHO DYNAMIC BEHAVIOR 1* DEFINE INITIAL DEFLECTION OF THE ~ SYSTEM NATURAL FREQUENCIES ~ SELECT NEW SET ANO NORMAL MODES Of DYNAMIC STIFFNESS MATRICES DYNAMIC DISPLACEMENT ~ RESPONSE AT MASS POINTS PLOT SUPPORT-POINT DISPLACEMENTS. REVIEW TO CHECK IF THE ASSUMED DYNAMIC STIFFNESS MATRICES NO ARE COMPATIBLE WITH THE DISPLACEMENT
RESPONSE
YES COMPUTE TIME-HISTORY SUPPORT LOADS, MEMBER FORCES, STRESSES AND DISPLACEMENTS PIPING STRESS EVALUATION I I SUPPORT MEMBER EVALUATION l
McGuire Nuclear Station UFSAR Figure 3-116 (Page 1 of 1) (14 OCT 2000) Figure 3-116. Theoretical Solution [Historical information, not required to be revised.] FU) ~w-,c,;,. f(t) 02 R,,,=45 3 *!ps K = 83. 4 kip/in. 2 M = 0, 0259 kip-sec /in. j ' I / / I 1max - ':l min Significant response pa1*ameters, calculated in a.ccorda.nce '1.ith Biggs' solution with intermediate steps to 5 significant figures: 'i. m - o. 3041:, t
== 0.066S sec. m Tn = 0.1107 sec. y -v max ~ min *-= o. 36'39 sec.
Reference:
John M. Biggs, Introduction to Structural Dynamics, McGraw-Hill, Figure 2.22, 1964
McGuire Nuclear Station UFSAR Figure 3-117 (Page 1 of 1) (14 OCT 2000) Figure 3-117. PWhip Verification Example Inelastic Pipe Element [Historical information, not required to be revised.] Structure: F (t) l 2 ,I _/Z\\I = 0. 0259 kip-sec /in / ~ / I 1:,1)'-Q i (,_ __________________ -----~ 20'-0 Resistance / I / / ' r.. --= S3. I k.in/l.n 1'- dbplacement i:.t t-eam Cf. Applied Force~ F (t)+ ~------------ 30 ki.p I -. *:ime t1 =
- 001 sec PW HIP Model :
M/2 EI=2. 40 x lOi ktp**tn2 .4 . -- - ---_- -------1
McGuire Nuclear Station UFSAR Figure 3-118 (Page 1 of 1) (14 OCT 2000) Figure 3-118. PWhip Verification Example Inelastic Yield (U-Bar) Element Plastic Behavior [Historical information, not required to be revised.] Structure: Inelastic y r T I Yield (U-:~~-;:),., ~ Element ,,J-, ~ i\\l y 1 t F'{t) 'l 0 0"~9 kip-sec*/in. 11 ~ * .:.;J R / R = 45. 3 kip. m ,.-~---- (_JK"" / ~*
- 83. 4 kip/in.
JL.I __________ -' F(ti t 30 kip. l:------- ----- 1 I I !_, _________ ""::'= time R tL_L __ R_m_-=_-!:_5_.3 __ ';d_p_. --y I jK = 83. 4 kip/in. ~ I... F(t) f I I 000~ 11 6.= o.
- )
(inltht.l g.:a.p) 30 klp, ~ ' ----;:---~:;-.;-:::::::;:---;:~ +- O, 001 sec, time \\::;:;:
McGuire Nuclear Station UFSAR Figure 3-119 (Page 1 of 1) (14 OCT 2000) Figure 3-119. Theoretical Solution [Historical information, not required to be revised.]
- Th<::Joretic.:al Soiurion:
K: 1973, 92 lb/Ln m = O *.5 lbwsec2 /ln g = 386. in/se-..:2 Time of initial impact, t0 = 0. 071982 sec, Vel.oclty at initio.l impact, y0 = 2i. 785 in/sec. Time to zero velocity (maximam defiection Ym), tm ~ 0. 100,37 sec. Maximum rllsplacernent of mass m, Ym ;;:: 1, 5506.9 ir1.
Reference:
Wil I iam T. Thomson, Vibration Theory' and Application, Prentice-Hall, Example 4.6~1, 1965,
McGuire Nuclear Station UFSAR Figure 3-120 (Page 1 of 1) (14 OCT 2000) Figure 3-120. PWhip Verification Example Inelastic Yield (U-Bar) Element Initial Gap Effect [Historical information, not required to be revised.] PWHIP Model: (Flgure 3. 9, 2. 3-d) y ~ I, U-Bar I ..-: m ~ i:; (t) U-Bar st:iifness, k::: 19i3.92 lb/in Nfa.ss, m :.::: O. 5 lb-se,:2 /in Gravitarion:,l acceleration, g = 3b6 in/sec2 Initial gap, h "' 1. D R4 F<t) h
- ------'""-1 (init i.al,q.1p J
/ .I ,I r1 =
- 001 sec I
/ ..( / time
McGuire Nuclear Station UFSAR Figure 3-121 (Page 1 of 1) (14 OCT 2000) Figure 3-121. Test Chamber Temperature Profile for Accident Environment Simulation 340 320~ i 1 l l l I l, 250-200 '=.--CHEMICAL SPRAY-~ ';Q_ ), I I I I 10 3 5
- ~
8 ~EC HR HR HR 5 HR-10 SEC I J I l I HR l /-~---.--. I / ") l DAYS TIME i !INDICATES CYCLING OF iVALVE ACTUATOR
- 1. P,. 70 ps I g
- 2. P.a 40 pslg
- 3. P~ 25 pslg
- 4. p;r, 10 pslg CHEMICAL SPAAV COMPOSITION:
1.5% boric acid, by weight Buffered with sodium hydroxide to pH of 7,7-8.o at Bo F. 1J DAYS I 21 DAYS ,1 3h DAYS
McGuire Nuclear Station UFSAR Figure 3-122 (Page 1 of 1) (14 OCT 2000) Figure 3-122. Reactor Coolant Loop Model for Steam Generator Replacement I I D ti IQ II
McGuire Nuclear Station UFSAR Figure 3-123 (Page 1 of 1) (14 OCT 2000) Figure 3-123. Reactor Coolant Loop Model for Steam Generator Replacement m g Ill "11 m g Ill "11
McGuire Nuclear Station UFSAR Figure 3-124 (Page 1 of 1) (14 OCT 2000) Figure 3-124. Reactor Coolant Loop Model for Steam Generator Replacement
McGuire Nuclear Station UFSAR Figure 3-125 (Page 1 of 1) (14 OCT 2000) Figure 3-125. Reactor Coolant Loop Model for Steam Generator Replacement w ii -z.. ii
McGuire Nuclear Station UFSAR Figure 3-126 (Page 1 of 1) (14 OCT 2000) Figure 3-126. Time-History Dynamic Solution for LOCA Loading Reactor Coolant Equipment L0CA Forcing Loop Support Structure Functions I I Loop Geometry - Support Structure and Model Stiffness Matrices t I I Def1ne Initial Oefl ect ion of ~ the System ./ \\., I) t I Natural Frequencies..._ and Nonrial Modes t I Dynamic Displacement Response at _Mass Points I I t Compute Time-History forces, Stresses and Displacements t I, 1 Piping Stress Evaluation Support Member EvaluationJ
McGuire Nuclear Station UFSAR Figure 3-127 (Page 1 of 1) (27 MAR 2002) Figure 3-127. Loop Layout and Global Coordinates REACTOR COOLANT PUMP CROSSOVER LEG _COLO LEG REAC'C C0OL.:.N PUMP
McGuire Nuclear Station UFSAR Figure 3-128 (Page 1 of 1) (27 MAR 2002) Figure 3-128. RPV Shell Submodel 25 TYPICAL SUPPORTED NOZZLE (4) 1 z 3 17 UPPER HEAD -C.G. INTERNALS SUPPORT LEDGE: TYPICALLY UNSUPPORTED NOZZLE (4) ( K] STIFFNESS MATRIX 19 ~Lt-ff-LINEAR IMPACT 4 8 LOWER RADIAL SUPPORT LOWER DOME C.G.
McGuire Nuclear Station UFSAR Figure 3-129 (Page 1 of 1) (27 MAR 2002) Figure 3-129. Core Barrel Submodel i~~~:L~~~EL Q DENOTES NOOES ON INTERNALS SUBHOOEl ~Ckl\\llo..,... Typical representation of the concentric Impact elements between the fuel assembly grids and the core barrel --H-f cf-N-CONCE.IITRlC IMPACT ~r.~ LINEAR IMPACT RPV NOZZl£
- CENTERLIHE UPPER CORE PLATE CORE t.G.
lOWER CORE -PLATE LMR RADIAL SUPPORT*
McGuire Nuclear Station UFSAR Figure 3-130 (Page 1 of 1) (27 MAR 2002) Figure 3-130. Reactor Internals Submodel DENOTES NODES ON RPV SHELL SUBMOOEL 0 DENOTES NODES ON CORE SARREL SUBMOOEL 15 UPPER SUPPORT PLATE SUPPORT COLUMNS ~ LI-ff-LINEAR IMPACT ANO GUIDE TUBES L FUEL UPPER CORE 16 PLATE L 1 TOP FUEL NOZZLE BOTTOM FUEL NOZZLE CORE C.G. LOWER CORE PLATE
McGuire Nuclear Station UFSAR Figure 3-131 (Page 1 of 1) (27 MAR 2002) Figure 3-131. Hydrodynamic Masses in Vessel/Barel Downcomer Annulus 0 -Node. num~er CJ
- N.Y-1~dynami!SM*~JElemenf*
McGuire Nuclear Station UFSAR Figure 3-132 (Page 1 of 1) (13 APR 2008) Figure 3-132. Containment Vessel Mathematical Model 1341" I= i" T=34 35 9@ 12d'= 1osd' 8 l..n
- 8 z C) r z
fTI 690" T= 11 i6}}