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{{#Wiki_filter:McGuire Nuclear Station UFSAR Appendix 3B. Figures Appendix 3B. Figures
Figure 3-1. Wind Pressure Distribution on Reactor Building McGuire Nuclear Station
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McGuire Nuclear Station UFSAR Figure 3-2 (Page 1 of 1) Figure 3-2. Turbine Building Tornado Wind Distributions (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-3 (Page 1 of 1) Figure 3-3. Fire Protection System Piping Penetration Detail CtJNCecr~
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Figure 3-4. Turbines Missiles Projected Areas (Low Pressure Turbine Rotor Discs) McGuire Nuclear Station t --- _.,...-*-~~-~ =... i j N.Qli : .REFER TO TABLE Al 3-15 FOR MISSLE PROPERTIES. UFSAR Figure 3-4 (Page 1 of 1) (14 OCT 2000) TURBINE t\llSSlLEPROJECTED AREAS ( LOW PRESSURE TU'3BINE
- ROTOR DISCS)
McGuire Nuclear Station UFSAR Figure 3-5 (Page 1 of 1) Figure 3-5. Loss of Reactor Coolant Accident Boundary Limits CASE I OUTGOING LINES WITH NORMALLY CLOSED VALVE s REACTOR COOLANT PIP IN\
!~RY NOH: PPESSURIZER SAFEH VALVES ARE INCL 1JDED 1*1iJDEREIS CASE.
CASE I I OUTGOING LINES WITH NORAALLY OPEN VALVES NOTE: -1HE REACTOR COOLA,,T P~,,ip NO. l SEAL IS ASSUMED -: 0 BE EQUIVALENT -:0 f I RS-, FAIL CLOS ED OR VALVE. FAIL-AS-IS VALVES RESTAA INT CASE Ill INCOMING LINES NORMALLY WITH FLIJw NO. NO. 2 _j_ B JU~CAf'.Y TEST CONNECT I ON CASE l V INCOMING LINES NORMALLY WITHOUT FLOW TEST CONNECT I OtJ (MEAMS OF VER I FY I ilG THAT CHECK VALVE IS CLOSED; CASE V 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. (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-6 (Page 1 of 1) Figure 3-6. Location of Postulated Breaks
? OO<OTES BA.EAK lctATtO, f'lAN VIEW REACTOR PRE5SUl!E VESSEL 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. (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-7 (Page 1 of 1) 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 IEnv i ronmen ta 1 Effects Identify Unacceptable -- Identify Unacceptable . Identify 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 Characteristic s Conditions I I I Develop Pipe Whip Interaction Matrix f1 Detennine Jet Impinge-ment Interaction Matrix
... Compare Environmental Conditions With Design Conditions I 1 I Evaluate Rerouting or Evaluate Rerouting, Develop Environmental Structural Barriers ~
Structural Barriers or Effect Table Additional Restraints I I I Locate Pipe Whip Locate Jet Deflectors Evaluate Rerouting, lso-i,.. Restraints Barriers latlon or Venting for I Structures and/or Components Determine Pipe Whip Determine Jet Deflector I Restraints Loadings Barri er Loadings I I Revise Design Criteria for Structures and/or i Prepare Pipe Whip Prepare Jet Deflector Components Restraint Structural Barrier Structural Design Drawings Design Drawings (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-8 (Page 1 of 1) Figure 3-8. Deleted per 2001 Update (14 OCT 2000)
Figure 3-9. Main Steam and Feedwater Routing Plan Outside Containment. See 3-10 for Elevation McGuire Nuclear Station
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(14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-10 (Page 1 of 1) Figure 3-10. Main Steam and Feedwater Routing Elevation Outside Containment [Historical information, not required to be revised.] R[t,C:T'.lR ?.clc, UNIT I 46 47 4'1 51 5
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McGuire Nuclear Station UFSAR Figure 3-11 (Page 1 of 1) Figure 3-11. Main Steam Routing Plan Outside Containment ft (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-12 (Page 1 of 1) Figure 3-12. Main Steam Routing Elevation Outside Containment Nearest Reactor Building Wall 7 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-13 (Page 1 of 1) Figure 3-13. Main Steam Routing Elevation Outside Containment Farthest From Reactor Building Wall I i
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McGuire Nuclear Station UFSAR Figure 3-14 (Page 1 of 1) Figure 3-14. Main Feedwater Routing Plan Outside Containment (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-15 (Page 1 of 1) Figure 3-15. Main Feedwater Routing Elevation A-A Outside Containment (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-16 (Page 1 of 1) Figure 3-16. Response Acceleration Spectra [Historical information, not required to be revised.] i i 1.
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McGuire Nuclear Station UFSAR Figure 3-20 (Page 1 of 1) Figure 3-20. Reactor Building Interior Structure - Mass Model [Historical Information, not required to be revised.] (27 MAR 2002)
McGuire Nuclear Station UFSAR Figure 3-21 (Page 1 of 1) Figure 3-21. Auxilary Building Mass Model [Historical Information, not required to be revised.] (27 MAR 2002)
McGuire Nuclear Station UFSAR Figure 3-22 (Page 1 of 1) Figure 3-22. Reactor Building 1st and 2nd Horizontal Mode Shapes EL. 722' + 6 11 __EL. 722'+6"
!SI HORIZONA L MODE 2~ HORIZONT AL MODE rl =4.9 CPS +2 = 13. 5 CPS (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-23 (Page 1 of 1) 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 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-24 (Page 1 of 1) Figure 3-24. Reactor Building - Shear Force (lb/in) Due to SSE [Historical information, not required to be revised.]
--=---7.9 135.1 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-25 (Page 1 of 1) Figure 3-25. Reactor Building - Meridional Force N0 (lb/in) Due to SSE [Historical information, not required to be revised.] 42L5 396.6 2448.9 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-26 (Page 1 of 1) Figure 3-26. Reactor Building - Meridional Moment M0 (lb/in) Due to SSE [Historical information, not required to be revised.] 1058,3 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-27 (Page 1 of 1) 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-.......::;;._ _ _ _ _ __ (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-28 (Page 1 of 1) 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 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-29 (Page 1 of 1) 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 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-30 (Page 1 of 1) Figure 3-30. Containment Interior Structure, First Four Horizontal Mode Shapes, North-South Direction MODE 4 f4 = 47.00 CPS CPS MODE 3 f3~37.51 MODE 2 f2 = 20.46 CPS CPS MODE I 8.1
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McGuire Nuclear Station UFSAR Figure 3-31 (Page 1 of 1) Figure 3-31. Containment Interior Structure, First Four Horizontal Mode Shapes, East-West Direction MODE 4
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+1 = J_I (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-32 (Page 1 of 1) Figure 3-32. Containment Interior Structure - First Two Vertical Mode Shapes [Historical information, not required to be revised.] 48.09 CPS MODE 2 tz = I CPS MODE
+1 =- 19.65 (14 OCT 2000)
Figure 3-33. Containment Interior Structure Response Loads Due to SSE in the North-South McGuire Nuclear Station WT_lJ_ 6Z7 0.604 0.0 Tl 63Q s,01 WTII B3 15,452 29,906
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Figure 3-34. Containment Interior Structure Response Loads Due to SSE in the East-West McGuire Nuclear Station WT 13 6-45 O.6ZI O 0093 644 0.0
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McGuire Nuclear Station UFSAR Figure 3-35 (Page 1 of 1) Figure 3-35. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 738.22
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McGuire Nuclear Station UFSAR Figure 3-42 (Page 1 of 1) Figure 3-42. Reactor Building Second Horizontal Mode
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McGuire Nuclear Station UFSAR Figure 3-43 (Page 1 of 1) Figure 3-43. Reduced Model of Interior Building Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, East-West Direction, Elevation 738.22 0 0 0 I r::, J C, I i/
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Figure 3-85. Layout of Containment Shell McGuire Nuclear Station 25 TOP OF I ~ 9 II 12 l l ~ 15 18 2I 24
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[HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED] Figure 3-86. Civil-Environmental Division Partial Organizational Chart McGuire Nuclear Station Chief Engineer I r C ivi 1-Envi ronmental Division I I I
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McGuire Nuclear Station UFSAR Figure 3-87 (Page 1 of 1) Figure 3-87. Reactor Building, First Horizontal Mode, f = 4.96478 cps (Kalnin's) i-------- -----.... ..iiEL.722+6 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-88 (Page 1 of 1) Figure 3-88. Reactor Building, First Horizontal Mode, f = 4.97 cps (Finite Elements) EL 72; +6 r*------ (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-89 (Page 1 of 1) Figure 3-89. Containment Vessel, First Horizontal Mode, f = 9.284 cps (Kalnin's) EL.725 +0 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-90 (Page 1 of 1) Figure 3-90. Containment Vessel, First Horizontal Mode, f = 9.3234 cps (Finite Elements) (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-91 (Page 1 of 1) Figure 3-91. Containment Vessel, Second Horizontal Mode, f = 25.69 cps (Kalnin's) EL 725+C' (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-92 (Page 1 of 1) Figure 3-92. Containment Vessel, Second Horizontal Mode, f = 25.660 cps (Finite Elements)
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McGuire Nuclear Station UFSAR Figure 3-94 (Page 1 of 1) Figure 3-94. Containment Vessel, First Vertical Mode EL.7.-:7 5+0 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-95 (Page 1 of 1) Figure 3-95. Portion of the Operating Deck (14 OCT 2000)
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FULL OPERATING DECK Amendment 4 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-97 (Page 1 of 1) Figure 3-97. Comparison of Program Results Fixed Boundary Conditions
..c.i,. 20 1- ~ - -- ......
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SECTION A-A
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< -30 ___ STRUDL l-z -40 _ELA S w
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McGuire Nuclear Station UFSAR Figure 3-98 (Page 1 of 1) Figure 3-98. Comparison of Program Results Pinned Boundry Conditions
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1- ___ STRUDL ffi _ELAS
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McGuire Nuclear Station UFSAR Figure 3-99 (Page 1 of 1) Figure 3-99. Pressure Seals and Gaskets 4r*~ ~
~
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REACTORSUILDIN!l-UNIT!lo2 PRESSURESEALSIGASICET5 StiEET*I FIG.NO. 3-99 l4A?RIL21illil5 (14 APR 2005)
McGuire Nuclear Station UFSAR Figure 3-100 (Page 1 of 1) 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. (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-101 (Page 1 of 1) Figure 3-101. Pressure Seals and Gaskets
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McGuire Nuclear Station UFSAR Figure 3-102 (Page 1 of 1) 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 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-103 (Page 1 of 1) Figure 3-103. Diesel Generator Area, General Arrangement Cross Section Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-104 (Page 1 of 1) Figure 3-104. Auxiliary Building, Fuel Building, General Arrangement Plan at El. 760+6 Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-105 (Page 1 of 1) Figure 3-105. Auxiliary Building, Fuel Building, General Arrangement Plan at El. 778+10 Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-106 (Page 1 of 1) Figure 3-106. Auxiliary Building, Fuel Building, General Arrangement, Longitudinal Section Thru Fuel Pool Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-107 (Page 1 of 1) Figure 3-107. Auxiliary Building, Fuel Building, General Arrangement, Transverse Section at Cask Area Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-108 (Page 1 of 1) Figure 3-108. Auxiliary Building, Floor El. 733 + 0, General Arrangement, Battery Room Plan Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-109 (Page 1 of 1) Figure 3-109. Auxiliary Building, El. 750 + 0, General Arrangement, Cable Room Plan Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-110 (Page 1 of 1) Figure 3-110. Auxiliary Building, El. 767 + 0, General Arrangement, Control Room Plan Security-Related Information - Figure Withheld Under 10 CFR 2.390 (05 APR 2011)
McGuire Nuclear Station UFSAR Figure 3-111 (Page 1 of 1) Figure 3-111. Reactor Building Foundation and Its Connection to Reactor Building Shell and Crane Wall (Reinforcement Details)
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McGuire Nuclear Station UFSAR Figure 3-112 (Page 1 of 1) Figure 3-112. Reinforcement Arrangement Between the Auxiliary Building Foundation and a Typical Vertical Wall I
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McGuire Nuclear Station UFSAR Figure 3-113 (Page 1 of 1) Figure 3-113. Vibration Checkout Functional Test Inspection Points
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McGuire Nuclear Station UFSAR Figure 3-114 (Page 1 of 1) 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. (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-115 (Page 1 of 1) 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 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-116 (Page 1 of 1) Figure 3-116. Theoretical Solution [Historical information, not required to be revised.] FU) R,,,=45 3 *!ps
~w-,c,;, .
K = 83. 4 kip/in. 2 M = 0, 0259 kip-sec /in. f(t) j I
/ '
/ :
I 1 max - ':l min 02 Significa nt response pa1*ameters, calculate d in a.ccorda.nce '1.ith Biggs' solution with intermed iate steps to 5 significa nt figures:
.'i m -
- o. 3041:,
t == 0.066S sec. m Tn = 0.1107 sec. y -v max ~ min *-= o. 36'39 sec. Referenc e: John M. Biggs, Introduc tion to Structur al Dynamics, McGraw-Hill, Figure 2.22, 1964 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-117 (Page 1 of 1) Figure 3-117. PWhip Verification Example Inelastic Pipe Element [Historical information, not required to be revised.] Struc ture: F (t) l 2
,I _/Z\I = 0. 0259 kip-s ec /in
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I (,_ ____________ ______ ---- -~i 1:,1)'-Q 20'-0 Resis tance
/
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n 1'-
/
dbpla ceme nt i:.t t-eam Cf. Appli ed Force ~ F (t)+
~------------ 30 ki.p I
-. *:ime t 1 =
- 001 sec PW HIP Model : M/2 EI=2. 40 x lOi ktp**tn2
.4
. -- - ---_- ------ -1 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-118 (Page 1 of 1) Figure 3-118. PWhip Verification Example Inelastic Yield (U-Bar) Element Plastic Behavior [Historical information, not required to be revised.] R Struc ture: R = 45. 3 kip.
,.-~----m
/
(_JK"" 83. 4 kip/in . JL.I_ _ _ _ _ _ _ _ _ _ -'
/ ~*
y r F(ti t 30 kip. l:-- --- -- --- -- 1 I I
!_,___ ___ ___ ""::'=
time T I jK R tL_L_ _R_m_-= _-!:_5_.3__
= 83. 4 kip/in .
';d_p_.--y Inelas tic I , .. --
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Yield (U-:~~-;:),., Eleme nt ,,J-, ~ ...6.= o. I I 000~;) 11
~ i\l (inltht .l g.:a.p) y 1
t F'{t) F(t) f 30 klp, I
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+- O, 001 sec,
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time
'l 11 ~ .:.;J9 kip-s ec*/in .
0
- 0"~
(14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-119 (Page 1 of 1) Figure 3-119. Theoretical Solution [Historical information, not required to be revised.] K: 1973, 92 lb/Ln m = O* .5 lbwsec2 /ln g = 386. in/se-..:2
*Th<::Joretic.:al Soiurion:
Time of initial impact, t 0 = 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, (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-120 (Page 1 of 1) Figure 3-120. PWhip Verification Example Inelastic Yield (U-Bar) Element Initial Gap Effect [Historical information, not required to be revised.] PWHIP Model: R4 ..(
/
(Flgure 3. 9, 2. 3-d) ~ I I /
, U-Bar I
..-: m
~
h
*:----- -'""-1 y (init i.al ,q.1p J i:; (t)
F<t)
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time r 1 =
- 001 sec U-Bar st:iifne ss, k::: 19i3.9 2 lb/in Nfa.ss, m :.: : O. 5 lb-se,:2 /in 2
Gravita rion:,l acceler ation, g = 3b6 in/sec Initial gap, h "' 1. D (14 OCT 2000)
Figure 3-121. Test Chamber Temperature Profile for Accident Environment Simulation McGuire Nuclear Station 340 i 1 l I l l I J l i ,1 320 ~ l, !INDICATES CYCLING iVALVE ACTUATOR OF
- 1. P,. 70 ps I g
- 2. P.a 40 pslg
- 3. P~ 25 pslg
- 4. p;r, 10 pslg CHEMICAL SPAAV COMPOSITION:
250 - 1.5% boric acid , by weig ht
/-~ --- .-- . Buff ered with sodium hydr oxid e to pH of 7,7-8.o at Bo F.
200
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UFSAR Figure 3-121 (Page 1 of 1) I I I I I 10 I / ")
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HR 5 HR
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DAYS 1J I 21 3h DAYS DAYS DAYS
-* 5 HR-10 SEC TIME (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-122 (Page 1 of 1) Figure 3-122. Reactor Coolant Loop Model for Steam Generator Replacement I I
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McGuire Nuclear Station UFSAR Figure 3-123 (Page 1 of 1) Figure 3-123. Reactor Coolant Loop Model for Steam Generator Replacement m g Ill "11 m g Ill "11 (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-124 (Page 1 of 1) Figure 3-124. Reactor Coolant Loop Model for Steam Generator Replacement (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-125 (Page 1 of 1) Figure 3-125. Reactor Coolant Loop Model for Steam Generator Replacement w ii
-z .
ii (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-126 (Page 1 of 1) Figure 3-126. Time-History Dynamic Solution for LOCA Loading Reactor Coolant Equipment L0CA Forcing Loop Support Structure Functions I I Loop Geometry and Model
- Support Structure Stiffness Matrices I ;
t I Def1ne Initial - Oefl ect ion of
~
the System ./ \., I) I t Natural Frequencies ..._ and Nonrial Modes I t Dynamic Displacement Response at _Mass -- Points I I t Compute Time-History forces, Stresses and Displacements I , t 1 Piping Stress Evaluation Support Member EvaluationJ (14 OCT 2000)
McGuire Nuclear Station UFSAR Figure 3-127 (Page 1 of 1) Figure 3-127. Loop Layout and Global Coordinates CROSSOVER LEG REAC'C C0OL.:.N PUMP _COLO LEG REACTOR COOLANT PUMP (27 MAR 2002)
McGuire Nuclear Station UFSAR Figure 3-128 (Page 1 of 1) Figure 3-128. RPV Shell Submodel 1 UPPER HEAD
-C.G.
z _ INTERNALS SUPPORT LEDGE: 3 25 TYPICALLY UNSUPPORTED NOZZLE (4) TYPICAL SUPPORTED NOZZLE (4) 17 (K] STIFFNESS MATRIX 19 ~Lt-ff- LINEAR IMPACT 4 LOWER RADIAL
- SUPPORT
_ LOWER DOME 8 C.G. (27 MAR 2002)
McGuire Nuclear Station UFSAR Figure 3-129 (Page 1 of 1) Figure 3-129. Core Barrel Submodel i~~~:L~~~EL --H-f cf-N- CONCE.IITRlC IMPACT Q DENOTES NOOES ON ~ r . ~ LINEAR IMPACT INTERNALS SUBHOOEl
~Ckl\llo..,...
_ RPV NOZZl£
- CENTERLIHE UPPER CORE
- PLATE Typical representation of the concentric Impact elements between the fuel assembly grids and the core barrel CORE t.G.
lOWER CORE
-PLATE LMR RADIAL
- SUPPORT*
(27 MAR 2002)
McGuire Nuclear Station UFSAR Figure 3-130 (Page 1 of 1) Figure 3-130. Reactor Internals Submodel DENOTES NODES ON RPV SHELL SUBMOOEL 0 CORE DENOTES NODES ON SARREL SUBMOOEL UPPER SUPPORT 15 - PLATE SUPPORT COLUMNS ~ LI-ff- LINEAR IMPACT ANO GUIDE TUBES UPPER CORE 16 - PLATE L TOP FUEL L NOZZLE 1 CORE
- C.G.
FUEL BOTTOM FUEL NOZZLE LOWER CORE
- PLATE (27 MAR 2002)
McGuire Nuclear Station UFSAR Figure 3-131 (Page 1 of 1) Figure 3-131. Hydrodynamic Masses in Vessel/Barel Downcomer Annulus 0 - Node. num~er CJ *:N.Y-1~dynami!SM*~JElemenf* (27 MAR 2002)
McGuire Nuclear Station UFSAR Figure 3-132 (Page 1 of 1) Figure 3-132. Containment Vessel Mathematical Model 690" T= 11 i6
- 8 l..n z
C) r z fTI 9@ 12d'= 1osd' 4 1341" T= 3 8 I= i" 35 (13 APR 2008)}}