ML20049H269

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App 3C to Gessar, Computer Programs Used in Design of Seismic Category I Structures.
ML20049H269
Person / Time
Site: 05000447
Issue date: 02/12/1982
From:
GENERAL ELECTRIC CO.
To:
References
NUDOCS 8202230024
Download: ML20049H269 (20)


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GESSAR II 22A7007 238 NUCLEAR ISLAND. Rev. O i

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1 l APPENDIX 3C i

COMPUTER PROGRAMS USED IN THE DESIGN  ;

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OF SEISMIC CATEGORY I STRUCTURES

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PDR K ADOCK 05000447

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GESSAR II 22A7007-238 NUCLEAR ISLAND ~ Rev. O O -APPENDIX 3C  !

. CONTENTS t

I Section Title Page

3C ' APPENDIX 3C - COMPUTER PROGRAMS USED IN THE DESIGN i OF SEISMIC CATEGORY I STRUCTURES 3C.1-1 3C.1 INTRODUCTION 3C.1-1 3C.2 NATIONAL AERONAUTICS AND SPACE ADMINISTRATION STRUCTURAL ANALYSIS (NASTRAN) 3C.2-1
3C.2.1 . Description 3C.2-l' I

3C.2.2 Validation 3C.2-2

) 3C.2.3 Extent of Application 3C.2-2 I 3C.3 STRUCTURAL DESIGN LANGUAGE (STRUDL)

! INTEGRATED CIVIL ENGINEERING SYSTEM j (ICES) DYNAMIC ANALYSIS SYSTEM (DYNAL) 3C.3-1 3C.3.1 Description 3C.3-1 3C.3.2 Validation 3C.3-1 3C.3.3 Extent of Application: 3C.3-1

() 3C.4 3C.4.1 STRUCTURAL ANALYSIS PROGRAM (SAP)

Description 3C.4-1 3C.4-1 3C.4.2 Validation 3C.4-1

3C.4.3 Extent of Application 3C.4-1

< 3C.5 ENGINEERING ANALYSES SYSTEM (ANSYS) 3C.5-1 3C.5.1 Description 3C.5-1

, 3C.5.2 Validation 3C.5-1 i

i 3C.S.3 Extent of Application 3C.5-1

! 3C.6 STATIC AND DYNAMIC ANALYSIS OF AXISYMMETRIC STRUCTURES (AXIS) (PD52Cl) 3C.6-1 ,

i 3C.6.1 Description 3C.6-1

! 3C.6.2 Validation 3C.6-1 l 3C.6.3 Extent of Application 3C.6-2

! 3C.7 RESPONSE SPECTRA GENERATION (PD53Cl) 3C.7-1 i 3C.7.1 Description 3C.7-1

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i 3C.7.2 Validation 3C.7-1 3C.7.3 Extent of Application 3C.7-1

! 3C.8 THREE-DIMENSIONAL HEAT TRANSFER (CH 33) 3C.8-1

! 3C.8.1 Description 3C.8-1 3C-i

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. O CONTENTS (Continued)

Section Title Page 3C.8.2 Validation 3C.8-1 3C.8.3 Extent of Application 3C.8-1 3C.9 PROGRAM FOR BENDING CAPACITY DETERMIEATION (CC3000) 3C.9-1 3C.9.1 Description 3C.9-1 3C.9.2 Validation 3C.9-1 3C.9.3 Extent of Application 3C.9-1 3C.10 STORY 3C.10-1 3C.10.1 Description 3C.10-1 3C.10.2 Validation 3C.10-1 3C.10.3 Extent of Application 3C.10-1 O

O 3C-ii

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! GESSAR II 22A7007 j 238 NUCLEAR ISLAND Rev. O j.

APPENDIX 3C 1

W TABLES

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l Table Title Page

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3C-1 Validation of CH33 Program - Comparison of L

CH33 and NASTRAN - Similar Models 3C.11-1  ;

i i 3C-2 Validation of Program Story - Comparison of Program Story and Hand-Calculations 3C.ll-2 i

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ILLUSTRATIONS J

Pigure Title Page l 3C-1 Validation of Program CC3000 3C.12-1

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GESSAR II 22A7007 i 238 NUCLEAR ISLAND Rsv. 0 1 ,

Q APPENDIX 3C COMPUTER PROGRAMS USED IN THE DESIGN OF SEISMIC CATEGORY I STRUCTURES

3C.1 INTRODUCTION f The following Seismic Category I buildings and their foundations were designed using computer programs described in this appendix.

(1) Reactor Building - The Reactor Bu;1 ding includes the I

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following components, starting at the center of the ,

[ building:

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l (a) reactor vessel pedestal;

to) reactor vessel shield wall; (c) weir wall; (d) drywell;

{ (e) containment; (f) Shield Building; (g) steam tunnel embedment in the Shield Building; and i (h) Reactor Building base mat.

(2) Fuel Building

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(3) Auxiliary Building - The Fuel Building and the Auxiliary

. Building form an envelope around the Reactor Building.

(4) Diesel Generator Building, Division 1 l

} (5) Diesel Generator Building, Divisions 2 and 3 i

(6) Control Building -

() (7) Radwasta Building - The foundation of the building is Seismic Category I, the building is not. _

3C.1-1/3C.1-2

GESSAR II 22A7007 238 NUCLEAR ISLAhD Rsv. O y-'s 3C.2 NATIONAL AERONAUTICS AND SPACE ADMINISTRATION STRUCTURAL 4 Q) ANALYSIS (NAS" RAN) 3C.2.1 Description NASTRAN is a structural programming system developed by NASA in 1969 and is now within the public domain. A proprietary version of the program is kept up to date by the MacNeal-Schwendler Corporation and referred to as MSC/NASTRAN. It is serviced by the McDonnell Douglas (MCAUTO) and Control Data Corporation (CDC) service bureaus. There are three manuals describing NASTRAN use: the User's Manual, the Programmers' Manual, and the Theoretical Manual.

NASTRAN is a finite element program with the following elements, load capabilities, and rigid formats:

fs (1) elements - bar, rod, shear panel, twist panel, plate, k ,) conical shell, axisymmetric shell, scaler, and solid polyhedron; (2) loads - static, frequency dependent, time dependent, heat flow, linear and nonlinear, and transient; and (3) formats - NASTRAN provides 12 rigid formats. In addi-tion, it allows the user to provide his own matrix operations inputs either alone or in conjunction with the rigid formats. Rigid formats available are static analyses, static analyses for inertia relief, normal mode analyses, static analyses with differential stiff-ness, buckling analyses, precise linear analyses, direct complex eigenvalue analyses, direct frequency and ran-dom response, direct transient response modal, complex eigenvalue analyses, modal frequency and random response,

,~ and modal transient response. Additionally, there are k ,/ three rigid formats for heat transfer analysis available.

3C.2-1

GESSAR II 22A7007 238 NULLEAR ISLAND Rev. 0 3C.2.2 Validation In July 1975, the Dynamic Analysis System (DYNAL) and NASTRAN were compared by using identical inputs and comparing results. Results checked each other as follows: shear was within 5%, moments within it, and displacements within 2%. Also, in a letter to C. F. Braun & Co from the manager of MCAUTO, dated November 8, 1977 (on file at C. F. Braun & Co), Braun was advised that quality control procedures were used to ensure reliability and the program validateL NASTRAN has 89 classical test problems to perform validation. Additionally, in a letter to TVA from NRC, dated May 23, 1975 (on file at C. F. Braun & Co.), NRC accepted NASTRAN as a valid computer code.

3C.2.3 Extent of Application i

Yhe NASTRAN program was used for the structural analysis of the drywell, weir wall, Reactor Pressure Vessel (RPV) shield wall, RPV pedestal, Shield Building steam tunnel embedment, Reactor i

Building foundation, and for seismic analyses.

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3C.2-2

GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. 0 3

3C.3 STRUCTURAL DESIGN LANGUAGE (STRUDL)

O. -INTEGRATED CIVIL ENGINEERING SYSTEM (ICES)

DYNAMIC ANALYSIS SYSTEM (DYNAL) 3C.3.1 Description r

The original version of STRUDL was produced by the Massachusetts Institute of Technology (MIT) although MIT does not service the system. MCAUTO and Multisystems, Inc., joined together to offer ICES support and service to users. ICES STRUDL is a proprietary system considerably enhanced from the original system. The dynamic-portion of STRUDL, called STRUDL DYNAL, is produced by MCAUTO.

MCAUTO and Multisystems publish a user's manual covering STRUDL, I STRUDL DYNAL, and STRUDL Plots.

i The combined systems can perform fl2me analyses, finite-element analyses, and check conformance with the major codes (i.e., the American Institute for Steel Construction and the American Con-I i

() crete Institute). The program assumes a linear, elastic, small displacement analysis. Member properties are required and the program treats the joint displacements as unknowns.

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! 3C.3.2 Validation l

l In a letter to TVA from the NRC, dated May 23, 1975 (on file at C. F. Braun & Co.), NRC accepted the ICES STRUDL and STRUnL j

DYNAL programs as valid computer codes.

I l 3C.3.3 Extent of Application l

i The two programs were used to perform structural analyses of other Seismic Category I buildings and their foundations, except the Reactor Building. However, the Reactor Building platform system was also designed using these programs.

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. O 3C.4 STRUCTURAL ANALYSIS PROGRAM (SAP)

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3C.4.1 Description The SAP program, developed at the University of California, Berkeley, and modified at the University of Southern California j is now within the public domain. It is used to perform static and dynamic analyses of linear, elastic, three-dimensional structures using the finite-element method. The finite-element library con-tains truss and beam elements, plane and solid elements, plate and shell elements, axisymmetric (torus) elements, and special boundary (spring) elements. A user's manual was produced by U. C. Berkeley, in November 1973.

Element stresses and displacements are solved for either applied loads, pressures, or gravity loads. Temperature distributions are assigned as an appropriate uniform temperature change in each

/% element.

4 Dynamic response routines are available for solving arbitrary dynamic loads or seismic excitations using either modal super-position or direct integration. The program can also perform response spectra and time-history analyses.

3C.4.2 Validation In a letter from the NRC to TVA, dated May 23, 1975 (on file at C. F. Braun & Co.), NRC accepted the SAP program as a valid com-l puter code.

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3C.4.3 Extent of Application SAP was used for preliminary design and thermal cracking of the drywell, analysis of the Shield Building, and as a check for O

3C.4-1 4

GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 0 3C.4.3 Extent of Application (Continued) stress concentration. Cracking is handled by SAP by recycling the program manually asing orthotropic properties.

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GESSAR II 22A7007 238 NUCLEAR ISLAND R v. O i

1 3C.5 ENGINEERING ANALYSES SYSTEM (ANSYS)

3C.5.1 Description ANSYS is a finite-element program with capabilities for static and dynamic, elastic and plastic flow, and transient heat transfer analyses. The code was produced by Swanson Analyses Systems (S AS) ,

j Inc., 870 Pine View Drive, Elizabeth, Pennsylvania 15037, in j December 1971. SAS produced a user's manual dated December 1971.

3C.5.2 Validation The letter from MCAUTO to C. F. Braun ('n o file at C. F. Braun & Co.),

dated November 8, 1977, documents the procedures used for.vali-dation of ANSYS. ANSYS has 126 classical test problems to perform j validation.

3C.5.3 Extent of Application O

j The ANSYS program was used in the missile impact study and non-linear analysis of the suppression pool liner.

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rnv. 0

./~'s 3C.6 STATIC AND DYNAMIC ANALYSES OF AXISYMMETRIC STRUCTURES

( ,) (AXIS) (PD52Cl) 3C.6.1 Description The AXIS program is a special purpose, finite-element structural analysis computer program for complex axisymmetric structures. It is based on the displacement method more commonly referred to as the stiffness method. The three-diraensional axisymmetric con-tinuum is represented as an axisymmetric thin shell or as a solid of revolution, or as a combination of both.

The program is capable of both static and dynamic analyses. The dynamic version performs free vibration analysis as well as mode superposition, time-history, and response spcctra analyses. It also takes hydrodynamic effects into account.

fs The program is based on a dissertation by Sukmar Ghosh at U. C.

( ) A user's manual entitled Static and Dynamic N. ,/ Berkeley in 1969.

Analysis of Axisymmetric Structures is dated September 20, 1976.

3C.6.2 Validation Validation of the program was carried out in the following manner.

(1) It was verified that the finite elements used in the program properly represent a continuum and that the equations of equilibrium are properly assembled and solved.

(2) It was verified that the solution for mode shapes

and frequencies is correct.

(3) It was verified that the time-history mode superposition fs and response spectra analyses are correct.

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3C.6.2 Validation (Continued)

Computer programs used to verify the results were solid SAP, SAP IV, NASTRAN, and DYNAL. Forty-nine computer runs were made during the verification. Computer facilities used were the Braun Bur-roughs 6700, MCAUTO CDC 6600 at Huntington Beach, and MCAUTO IBM 370/1600 at Long Beach.

Verification description and certification are on file at C. F. Braun & Co.

3C.6.3 Extent of Application The program was used for the structural analysis of the Reactor Building.

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! GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. 0

! (~ 3C.7 RESPONSE SPECTRA GENERATION (PD53Cl) b

!. 3C.7.1 Description I

J The output from the AXIS computer program (PD52Cl) is time history which is input to PD53C1, a proprietary program. PD53Cl produces response spectra. The user's manual is dated May 1975.

3C.7.2 Validation

. .A model was subjected to a given time history and the resultant response spectra generated by PD53C1 were checked against an identical run on DYNAL. Results were essentially the same.

Documentation is on file at C. F. Braun & Co.

3C.7.3 Extent of Application This program was used for analysea of seismic and other dyramic

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GELSAR II 22A7007 d

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3C.8 THREE-DIMENSIONAL HEAT TRANSFER (CH33) 3C.8.1 Description i

The CH33 program calculates the steady state and transient temper-ature distributions in a structure of arbitrary, geometrical con-figuration. The heat transfer mechanism considered in the' program includes conduction, free and forced convection, internal heat generation, and thermal radiation. The system to be analyzed may be made of any number of materials with temperature- and time-dependent properties. The boundary of the system may be adiabatic or exposed to the surroundings called fluids. The system may be associated with an arbitrary number of fluids, each of which has its own temperature history and time- or temperature-dependent heat transfer properties.

l 3C.8.2 Validation Two models.were set up with identical geometry and heat-loadings.

, One was run on CH33 and one on NASTRAN. Results were compared and I

found to be in excellent agreement (within 1*F) in all cases (Table 3C-1).

l Documentation is on file at C. F. Braun & Co.

3C.8.3 Extent of Application l The CH33 program was used in the analysis of heat transfer in the t

drywell, Shield Building, and Reactor Building foundation.

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t GESSAR II 22A7007 i- 238 NUCLEAR ISLAND Rav. 0

! 3C.9 PROGRAM FOR BENDING CAPACITY DETERMINATION (CC3000)

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i 3C.9.1 Description I

CC3000 is a proprietary program developed to calculate shear and moment capacity of various thicknesses of foundation mats.

Geometry of section and loads are input, and-the program determines required reinforcement for the section chosen. The program also gives resulting stresses for the input values of reinforcement in l the beam section.

3C.9.2 Validation f

The program was verified by running several test cases using the NASTRAN code. Differences in results were found to be negligible I

(Figure 3C-1). Documentation is on file at C. F. Braun & Co.

() 3C.9.3 Extent of Application The program was used to assist in the design of the drywell, weir wall, and the Reactor Building foundation.

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rcv. O t's

! ) 3C.10 STORY

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3C.10.1 Description The program STORY determines the geometric characteristics of three-dimensional, linear, elastic systems descr. red by an arrange-ment of various structural elements of regular or irregular geometries. STORY also calculates shear, torque, normal and axial forces and stresses, rebar requirements, the area of steel re-quired, number of bars per feet, concrete stresses for both axial and flexural loads, and areas of steel required for axial loads.

The program is proprietary. A user's manual was prepared in October 1974.

3C.10.2 Validation The STORY program was validated by extensive hand calculations.

r' N "q ) Results were checked against computer output and found to be essentially the same as indicated by Table 3C-2. Documentation is on file at C. F. Braun & Co.

3C.10.3 Extent of Application The STORY program was used in analyses for sizing of members of other Seismic Category I buildings, except the Reactor Building.

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. O Table 3C-1 VALIDATION OF Cil33 PROGRAM -

COMPARISON OF CIl33 AND NASTRAN - SIMILAR MODELS Model* Initial Steady State Final Steady State Node Number Temperature (*F) Temperature (*F)

NASTRAN Cll33 NASTRAN Diff Cil33 NASTRAN Diff 1020 521.1 520.3 0.8 40.5 40.5 None 1017 526.6 526.6 None 40.2 40.2 None 1036 517.4 517.1 0.3 40.7 40.7 None 1033 525.1 525.2 0.1 40.3 40.3 None 1061 525.7 525.9 0.2 40.2 40.2 None 1064 522.1 522.0 0.1 40.4 40.4 None 1085 526.6 526.6 None 40.2 40.2 None 1088 523.8 523.5 0.3 40.3 40.3 None 1109 526.6 526.6 None 40.2 40.2 None 1112 523.9 523.5 0.4 40.3 40.3 None 1121 526.6 526.6 None 40.2 40.2 Nonc O 1124 524.5 526.6 524.2 0.3 None 40.3 40.2 40.3 40.1 None 0.1 1133 526.6 1136 525.2 525.1 0.1 40.2 40.2 None 1149 526.6 526.6 None 40.1 40.1 ,,None 1152 525.3 525.1 0.3 40.2 40.2 - Nonc

  • Cll33 and NASTRAN nodes occupy the same' oordinates in their respective models. ,

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. O Table 3C-2 VALIDATION OF PROGRAM STORY COMPARISON OF PROGRAM STORY AND IIAND CALCULATIONS Computer Program lland Calc Parameter Units 4-28-75 12-12-73 Difference X ft 4.97 4.97 none V ft 9.96 9.96 none 2

Area ft 66.14 66.14 none Ix ft 2383.5 2383.5 none 4

Iy ft 1809.6 1809.6 none 4

Ixy ft 54.83 54.825 none O degrees 5.408 5.408 none O

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. O te ds 43" b s 12" f'c a 4000 pel t

, M Ts Asfs Ces f's A's fy a 60 lisi Ce -- Ces Cs 19" C = 43 s N

IHg=0 Cc+Cs+Ps T IM *O A C c (2 d -j)+19 C s +19T s M d " A P M --

+ COMP

- TENSION 19" i As - T fs

  • A
  • ACCIDENT 1.OADS S: SERVICE l.OADS Es 18 FIND As & A's WITH KNOWN SF.CTION O 2sFIND f c,fs,8 t'c WITH KNOWN STEEL
    • PERCENTAGE 8Y WHICH EQUATIONS OF EQUIL18RIUM ARE NOT MET 4

ELEMENT As A's is f's fc C M P e T Cc Cs h IM3=0 * */o*

SQ .

  • SQiN SQlN KSI KSI KSI IN. IN.K K IN. K K K K IN.K OFF 2 320 3.5 387.3 67.3 0 0 .008 12.91 0 30 0 1.12 9 9.94 8748 .71 6 32.5 4.85 .878 7.64 8748 320 3.5 387.6 40.2 29.1 1.7 26.9 .003 2[$ 12 2Of A_ 9.85 0 54 0 1.87 9.25 12240 426 3.5 529.9 103.8 0 0 0 -

2O A 12.0 6.0 44.28 7.73 1.28 8.0 12240 426 3.5 531.4 61.4 46.4 2.4 47.8 .003 f 5.172 0 30 0 1.94 14.6 619 2 -14 4 3.5 155.2 169.9 0 0.3 8 .0 01 Id 6.24 3.12 24.77 15.2 2 1.49 14.0 619 2 84.4 3.5 15 4.6 12 5.2 47.5 3.7 10 0 016 28, 4.9 0 30 O l.4 ll.6 4764 49 3.5 14 7 97.44 0 0.6 9 .002 2'* 49 59.4 43.8 3 58 S-2 12 6 12.4 8 7.3 .723 13.7 4764 3 .5 14 9.2 .012 2g,9 6.3 61 0 30 0 1.14 9.94 5052 123 3.5 191.4 68 O O.5 60 .0 11 2[j 6.24 3.p2 30.7 6.44 .965 8.73 5052 12 3 3.5 191.S 50.5 20.1 2.1 33.4 .006 i

Figure 3C-1. Validation of Program CC3000 3C.12-1/3C.12-2

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