ML100950450

Calculation NUH32P+.0203, Revision 0, 32P+ Transfer Cask Impact Onto the Concrete Pad LS-DYNA Analysis (80 Inch End Drop), Attachment 1

ML100950450
Person / Time
Site:	Calvert Cliffs
Issue date:	03/31/2010
From:	Honrao A AREVA, Transnuclear
To:	Office of Nuclear Material Safety and Safeguards
References
TAC L24350 NUH32P+.0203, Rev 0
Download: ML100950450 (51)

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ATTACHMENT (1)NUH32P+.0203, REVISION 0, 32P+ TRANSFER CASK IMPACT ONTO THE CONCRETE PAD LS-DYNA ANALYSIS (80 INCH END DROP)Calvert Cliffs Nuclear Power Plant, LLC March 31, 2010

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[Hr .Ca~lculation Covor Shonvi T IP :3.2 (Revision 4)CliIa.I1No.:

l\IU H321-Oi'.2O34 Roviulol No;: 0 Pagje: 'I Ofi2/DCR [,MO (if l:picbI-)

PROJECTMNAME:

DIrl-132H Dry FI-uel Sli~orgje Project ilo CCNPP PIlarOJEnT no: NUJIH32P?+

CLIENTxl:

Czalveil C!.iff Ni.cleolr Power Plant (CCNPPD)CA-!CUIAI~iO N "fT'I..L 32P1-- T:aiisfet Q(.lý In j1a.ct onto the. .eJfiete Iaid S3-DYNA Analysis (80 in..ch. Elnd IDESCRIPTION:

'1) Calculation .Stunrimiar This calCulZiUoil deterrnines the rigid body acceleration time history of: the 32P.1 Cask during irnlpact oil a concrete pad with subgrade soil. The cask will he analyzed for the end drop with a drop height of 80".2) storage Media Descrlptrloi Slec.Ure fiitially, then re i e ilt tape I i'iji~iialisstiieis licensing review peir TIP 3.A i-equired?

Yes fl No FA (explain Ihelbw) LlcensliljnRevlýW No;: This calculation is pieiaredto suplport a Site Specific License Application by CCNPP that will be reviewed and al~proved by the, NRC. There0ore-a "IOCFR72i48 licensing review per TIP 3.5 is not applicable.

Software Utilized (sublje-t to tsst recluirements oi TIP .3.3): Version: LS-DYNA Is971s R14.2'Rev. 50638 Calculation is5com'npiete:

Abhijit I-Ionrao bate: 2 Originatbor Name and Signature:, Calculation has been-checked foir consistency, completeness and, correctness:

DeVon Wiison., Date:_Checler Name'and Signature:

Calculation is approved fo'"is t M: i ae ~Da/e: PoetEiigine&

Naneia nd igitui:A-__________________

________

--Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 3 of 24 TABLE OF CONTENTS I P U R P O S E .......................................................................................................................................

5 2 R E F E R E N C E S ...............................................................................................................................

5 3 .A S .S .U M P T IO N S ............

...................................................................................................................................

...............

6_6 _4 M E T H O D O LO G Y ...........................................................................................................................

6 5 C O M P U T A T IO N S ...........................................................................................................................

7 5.1 M ATER IA L PR O PERTIES ................................................................................................

7 5.1.1 CASK MATERIAL 7 5.1.2 DSC STRUCTURE MATERIAL 8 5.1.3 SOIL MATERIAL 9 5.1.4 CONCRETE MATERIAL 9 5.2 BO U N DA RY C O ND ITIO NS ............................................................................................

11 5.3 INITIAL CONDITIONS AND LOADING ...........................................................................

12 6 D A T A R E D U C T IO N ......................................................................................................................

16 6.1 CASK NODAL ACCELERATION SECTIONS EVALUATED

..........................................

16 6.2 RAW DATA FILTERING

..................

..............................

16 7 R E S U LT S ..........................

..........................

.........................................

18 8 LISTING OF ANSYS COMPUTER FILES ........................................

18 9 APPENDIX A -BUTTERWORTH FILTER VERIFICATION

..........................

23

--A--,- -Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 4 of 24 LIST OF TABLES TABLE 5-1 MATERIAL PROPERTIES OF STAINLESS STEEL SA 240 TYPE 304 ............................

7 TABLE 5-2 MATERIAL PROPERTIES OF STAINLESS STEEL SA 182 TYPE F304N .........................

7 TABLE 5-3 MATERIAL PROPERTIES OF CARBON STEEL SA 516 TYPE 70 ...................................

7 TABLE 5-4: CASK MATERIAL PROPERTIES

.......................................................................................

8 TABLE 5-5: EFFECTIVE PLASTIC STRAIN VS.- SCALE FACTOR FOR CONCRETE MATERIAL ........ 10 TABLE 5-6: TABULATED PRESSURES VS. VOLUMETRIC STRAIN FOR CONCRETE M A T E R IA L .................

............................................................................................................

1 1 TABLE 7-1: FILTERED RESULTS SUM MARY ...................................................................................

18 LIST OF FIGURES FIGURE 5-1: OVERVIEW OF 32P+ CASK FINITE ELEMENT MODEL ..............................................

13 FIGURE 5-2: 32P+ CASK FINITE ELEMENT MODEL ............................................

14 FIGURE 5-3: 32P+ FINITE ELEMENT MODEL SYMMETRY PLANE END DROP CONDITION

...... 15 FIGURE 6-1: PARTS ANALYZED FOR ACCELERATION TIME HISTORY..

.......................

17 FIGURE 8-1: END DROP CASK SHELL ACCELERATION (G) TIME HISTORY 180HZ FILTER ..........

19 FIGURE 8-2: END DROP CASK BOTTOM PLATES AND RESIN ACCELERATION (G) TIME H IS T O R Y 180H Z F ILT E R .......................................................................................................

20 FIGURE 8-3: END DROP CASK SHELL FOURIER SPECTRAL ANALYSIS BEFORE AND A F T E R F ILT E R ......................................................................................................................

2 1 FIGURE 8-4: END DROP CASK BOTTOM PLATES + RESIN FOURIER SPECTRAL ANALYSIS BEFO RE A ND A FTER FILTER ..........................................................................................

22

--Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 5 of 24 I PURPOSE This calculation analyzes the rigid body acceleration time histories for the 32P+ cask in the end drop with a drop height of 80". A dynamic finite element analysis program is used to determine the time histories.

Rigid body time histories of the cask body and cask bottom plates/resin are extracted from the results.2 REFERENCES 2.1. LS-DYNA Keyword User's Manual, Volumes 1 & 2, Version Is971s R4.2, Livermore Software Technology Corporation.

2.2. U.S. Nuclear Regulatory Commision NUREG/CR-6608, "Summary and Evaluation of Low-Velocity Impact Tests of Solid Steel Billet Onto Concrete Pads", February 1998.2.3. ASME Boiler and Pressure Vessel Code,Section II, "Materials Specifications," Parts A, B, C and D, 1998 edition with all addenda up to and including 1999 Addenda.2.4. TN Calculation No. 1095-1, Rev. 1, "NUHOMS 32P -Weight Calculation of DSC/TC System".2.5. TN Calculation 10494-66, Rev. 0, "NUHOMS-32PTH, OS187H Transfer Cask Dynamic Impact Analysis".

2.6. Structural

Design of Concrete Storage Pads for Spent Fuel Casks, Electric Power Research Institute, EPRI NP-7551, RP 2813-28, April 1993.2.7. BNL-NUREG-71196-2003-CP, "Impact Analysis of Spent Fuel Dry Casks Under Accidental Drop Scenarios," Brookhaven National Laboratory, 2003.

-A- Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 6 of 24 3 ASSUMPTIONS 3.1 NUH32P+ DSC design is identical to NUH32P DSC design. NUH32P weight properties are used for NUH32P+ weight.-3.2-tatic-anddynamic-coefficient -offriction-of-0-251s-assumed-between-a I sliding-surfaces-

3.3 Strain

rate effects on all material properties are neglected.

3.4 Mass of DSC is evenly distributed as a homogenous solid.3.5 A uniform temperature of 350OF is used for the end drop analysis.4 METHODOLOGY LS-DYNA, a dynamic finite element analysis program, is used to determine the rigid body acceleration time history of the NUH32P+ cask caused by a hypothetical accident end drop condition.

Because of the complexity of the analysis, a simplified model of the cask and DSC isnecessary.

The cask model does not include trunnions and other details; however, the mass of these unmodeled items is accounted for.The DSC structure is modeled as an isotropic elastic material with properties approximately equivalent to that of the structure as a whole. This is the same method used in Reference

[2.2].The model consists of the cask, the simplified DSC structure, a concrete impact pad, and the subgrade soil. Only 1/2 of the cask, DSC structure, concrete and soil are modeled as the entire arrangement is symmetric about the X-Y plane. The section of concrete modeled is 16'-8" long, 6'-8" wide, and 3' thick.The soil section is 66'-8" long, 18'-9" wide, and 39'-2" deep. The concrete and soil dimensions are based on the dimensions used in Reference

[2.2]. All lower faces of the soil are fixed except for the symmetry plane. All elements are modeled with fully integrated S/R solid elements.The finite element model is developed with ANSYS Rev. 11.0 and transferred to LS-DYNA. Modifications were made to the LS-DYNA input files to add the material definitions, non-reflecting boundaries and initial conditions into LS-DYNA, since these input variables are not available through ANSYS. The end drop is analyzed at 350 0 F. The 32P+ Cask finite element model is shown in Figures 5-1.

Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 7 of 24 5 COMPUTATIONS

5.1 MATERIAL

PROPERTIES The following tables, Table 5-1 through Table 5-3, list stainless steel or carbon .steel material properties available in the model material database.

Thematerial properties are based on ASME BPV Code,-Section II, 1992 [2.3].Table 5-1 Material Properties of Stainless Steel SA 240 Type 304 Sti~inIp~

Ste~I SA 240 Tvn~ ~04 I1Rt~r-Rni~ -ASME IQQ2 Temperature

[IF] 0 70 200 300 400 500 600 700 Sy [psi] 30000 30000 25000 22500 20700 19400 18200 17700 Su [psi] 75000 75000 71000 66000 64400 63500 63500 63500 Sm rps 20000 20000 20000 20000 18700 17500 16400 16000 E [psi] 2.87E+07 2.83E+07 2.76E+07 2.70E+07 2.65E+07 2.58E+07 2.53E+07 2.48E+07 Table 5-2 Material Properties of Stainless Steel SA 182 Type F304N Stainless Steel SA 182 Type F304N (18cr-8ni-n)-ASME 1992 Temperature

[IF] 0 70 200 300 400 500 600 700 SY [psi] 35000 35000 28700 25000 22500 20900 19800 19100 Su [psi] 80000 80000 80000 75900 73200 71200 69700 68600 Sm [psi] 23300 23300 23300 22500 20300 18800 17800 17200 E [ si] 2.87E+07 2.83E+07 2.76E+07 2.70E+07 2.65E+07 2.58E+07 2.53E+07 2.48E+07 Table 5-3 Material Properties of Carbon Steel SA 516 Type 70 Carbon Steel SA516 Type 70 -ASME 1992 Temperature

[IF] 0 70 200 300 400 500 600 700 Sy [psi] 38000 38000 34600 33700 32600 30700 28100 27400 Su [psi] 70000 70000 70000 70000 70000 70000 70000 70000 Sm [psi] 23300 23300 23100 22500 21700 20500 18700 18300 E [psi] 2.98E+07 2.95E+07 2.88E+07 2.83E+07 2.77E+07 2.73E+07 2.67E+07 2.55E+07 5.1.1 CASK MATERIAL The cask material properties are the same at those used in Section 5.1 except the outer shell density is adjusted to account for unmodeled cask parts. The cask weight is calibrated to the weight computed in Reference

[2.4]. All cask materials are modeled as elastic.

---A-- Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 8 of 24 Table 5-4: Cask Material Properties Cask Component Elastic Modulus (psi) Density (Ib-sec 2/in4) Poisson's Ratio Top Lid 26.75X10 6 9.7878x10'

0.3 Shell

Flanges and 26.75X10 6 7.4017x10-4 0.3 Ram Access Ring.QuteLrShell-

.-.........

.28,.OX 06- ... ..15.1.33x1.0.

-0.3 Lead 1.91X10 6 10.637x10-4 0.45 Inner Shell 26.75X10 6 11.102x10-4 0.3 Bottom Plates 26.75X10 6 7.4017X10-4 0.3 Resin 1.6X10 5 1.646X10-4 0.2 The modeled weight of the empty cask is 61,099 lbs since it is a half model, therefore the total modeled weight is 122,198 lbs. The total calculated empty cask weight (121,458 Ibs) in Reference

[2.4]. The percentage difference in calculated weight and the modeled weight is 0.58%5.1.2 DSC STRUCTURE MATERIAL The DSC structure material properties are the same as those used in Reference

[2.2] except for the density. The density of the DSC structure is adjusted to calibrate the overall weight of the canister, basket, and fuel assembly [2.4]. The DSC structure is modeled as elastic.E = 2.8x10 6 psi v=0.3 p = 4.0062x10-4 lb sec 2/in 4 Total modeled weight of the DSC structure is 47,390 lbs since it is a half model. Therefore the total modeled weight is 94,780 lbs. Total actual weight of the DSC per Reference

[2.4] is 90,976 lbs.

-A---- -Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 9 of 24 5.1.3 SOIL MATERIAL The Lawrence Livermore National Labs report [2.2] and Brookhaven National Laboratory report [2.7]indicates that the stiffness of the soil has little impact on the peak accelerations predicted in the cask.Thus, the same soil model as that used in the Livermore report [2.2] is assumed. The soil is modeled as elastic.E =6,000 psi v =0.45 p = 2.0368x10-4 lb sec 2/in 4 5.1.4 CONCRETE MATERIAL The concrete is modeled using Material Law 16 in LS-DYNA [Ref. 2.1], which was developed specifically for granular type materials.

All properties are the same as those used in Reference

[2.2] except when noted. A summary of the input used in the analysis is as follows.Yield stress versus pressure: P ( .max + a l +a 1 + a 2 P P afailed = a 0 f +-alf + a 2 P p = 2.0 9 6 7 5 x10-4 lb. sec: 2 I in.4 v = 0.22 ao = 1606 psi [2.5]a, = 0.418 a 2 = 8.35x10 5 psi1 b, 0 aof 0.0 psi.a= 0.385 The yield stress versus pressure curve is defined by c'yield = Ofailed ++/- -'0max --Ofailed)The scale factor q is shown in Table 5-2. The values listed in Table 5-2 are taken directly from Reference[2.2] and not scaled.

AR EVA TRANSNUCLEAR INC.Calculation No.: NUH32P+.0203 Calculation Revision No.: 0 Page: 10of24 Table 5-5: Effective Plastic Strain vs. Scale Factor for Concrete Material Effective Plastic Strain Scale Factor, i 0 0 0.00094 0.289 0.00296 0.465 0.00837 .. .. 0.629.0.01317 0.774 0.0234 0.893 0.04034 1.0 1.0 1.0 The maximum principal stress tensile failure cutoff is set at 870 psi [2.2]. Strain rate effects are neglected in the analysis.The pressure-volume behavior of the concrete is modeled with the following tabulated pressure versus volumetric strain relationship shown in Table 5-3 using the equation of state feature in LS-DYNA [Ref. 2.2].

~ ~-Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 11 of 24 Table 5-6: Tabulated pressures vs. volumetric strain for concrete material Volumetric Strain, E Pressure (psi) [2.2]0 0-0.006 4,600-0.0075 5,400-0.0. .6,200-0.012 6,600-0.02 7,800-0.038 10,000-0.06 12,600-0.0755 15,000-0.097 18,700 An unloading bulk modulus of 700,000 psi is assumed to be constant at any volumetric strain, as was assumed in Reference

[2.2].One percent deformation is assumed in the concrete pad to account for the pad reinforcement.

The one percent reinforcement is also used in the analyses presented in EPRI [2.6].The material properties used for the reinforcing bar are as follows.E= 30x10 6 psi v=0.3 Sy = 30,000 psi Tangent Modulus, ET = 30x0l psi 5.2 BOUNDARY CONDITIONS Only 1/2 of the cask is modeled with symmetry boundary conditions used to simulate the full structure.

Non-reflecting boundaries are applied to the bottom and sides of the modeled soil not aligned with the plane of symmetry (bottom, left side, right side, and back) to prevent artificial stress waves from reflecting back into the model. Both dilatation and shear waves are damped as described in the LS-DYNA *BOUNDARY command [Ref. 2.1].An automatic surface to surface (contactautomatic single-surface) contact definition is applied between all parts except the soil. The contact definition has a 0.5 penalty stiffness scale factor to prevent excessive contact stiffness leading to unrealistic part accelerations.

A surface to surface (contactsurface to surface) contact definition is applied between the concrete and the soil. Both contact definitions have soft contact option 2 as this is necessary for contact between materials that have very different material stiffness.

A conservatively low coefficient of friction (static and kinetic) of 0.25 is applied between all contact surfaces.

It is conservative to use a low value for the coefficient of friction because less energy is absorbed due to friction resulting in greater impact acceleration forces.

-A- ---Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 12 of 24 5.3 INITIAL CONDITIONS AND LOADING The analysis begins with a 1.5" gap between the cask and concrete to allow for at least 5 ms of zero acceleration other than gravity (this allows for appropriate filtering of the data). An initial velocity is applied to all parts of the cask model. The initial velocity is computed by equating potential and kinetic energies.Due to the initial 1.5" gap and gravitational acceleration, initial velocities are computed 1.5" shorter than the total 80" drop height. .. .. .V = potential energy = mgh T = kinetic energy = 1/21mv 2 For a 80" Drop: mgh = 1/2my 2=> v = 2gh = 2-(386.4)(80

-1.5) = 246.3 in./sec.A gravitational acceleration of 386.4 in/sec 2 is applied to the cask and DSC model.

A Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 13 of 24 Figure 5-1: Overview of 32P+ Cask Finite Element Model Calculation No.: NUH32P+.0203 Revision No.: 0 Page: 14 of 24 IN Figure 5-2: 32P+ Cask Finite Element Model Calculation No.: NUH32P+.0203 Revision No.: 0 Page: 15 of 24 4 I Figure 5-3: 32P+ Finite Element Model Symmetry Plane End Drop Condition

---Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 16 of 24 6 DATA REDUCTION The analyses are run for a duration of 0.08 seconds. The time step was set at 1 .17x10-6 which resulted in a negligible weight increase of about 9 lbs.6.1 CASK NODAL ACCELERATION SECTIONS EVALUATED The resulting rigid body acceleration time histories are computed by LS-DYNA. The rigid body accelerations are computed for the bottom plates + resin and the circumferential shell. The parts can be seen in Figure 6-1.6.2 RAW DATA FILTERING LS-DYNA reports the nodal accelerations at 100 jsec intervals.

Therefore, by the Nyquist theorem, the frequency content of the nodal acceleration data, refined by LS-DYNA, ranges from zero Hz, up to the following maximum frequency, fmax.1 1 fmax 5 kHz 2 10 X 10-6 sec The natural frequencies of the 32P+ cask model, which can be excited by an impact event, are much lower than this. These natural modes of the cask involve small displacements (and therefore low stresses) at frequencies higher than that of the rigid body motion of the cask. These high frequency accelerations mask the true rigid body motion of the cask, because both the low frequency rigid body acceleration and the high frequency natural vibration accelerations superimpose.

The net acceleration is contained in the raw data computed by LS-DYNA. Therefore, filtering is necessary to remove these high frequency accelerations.

The rigid body acceleration for each part is filtered using an 8 th order low pass Butterworth filter forwards and backwards with a cutoff frequency of 180Hz. This frequency is based on Fourier spectral analyses shown in Figures 7-1 through 7-4. The figures show that the 180Hz cutoff will still conservatively include some of the cask's natural modes. The impact durations are all over 0.03 seconds, so the minimum 1 frequency to capture rigid body motion would be 2 X -= 66.67 Hz.0.03 A Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 17 of 24 Top Plate Shell Bottom Plates+ Resin Figure 6-1: Parts Analyzed for Acceleration Time History

--A- Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 18 of 24 7 RESULTS Table 7-1 lists the peak filtered accelerations and corresponding time history plot for different parts of the 32P+ cask. All results are filtered with an 8 th order low pass butterworth filter with a 180Hz cutoff frequency.

Figure 8-1 through 8-2 shows the filtered acceleration time histories.

Figure 8-3 through 8-4the. Eourier spectral analyses o.fjhe-acceleration time histories before and after filtering.

Table 7-1: Filtered Results Summary Time History Drop Scenario Part Peak Acceleration (g) Figure Number End Drop Circumferential Shell 43.5 7-1 EndDrop Bottom Plates + Resin 48.8 7-2 8 LISTING OF ANSYS COMPUTER FILES Below is a listing of all files used in LS-DYNA, all Analysis performed on Computer HEA0105A, Dual Intel Xeon 3.2GHz, Windows XP SP2, LS-DYNA ver. Is971s R4.2 Revision 50638.Run Description File Names Date Stam p Ansys Model 32PHB.db 7/9/09 9:15 AM 8th Order Butterworth Filter low-passbutter.m 10/6/09 5:08PM 32PHBEndDrop.k 7/10/09 1:37 PM Constraints.k 7/9/09 9:22 PM 80" End Drop Elements.k 9/16/09 1:13 PM Input Files Nodes.k 9/16/09 1:20 PM NodeSets.k 7/9/09 2:27 PM SegSets.k 7/9/09 10:19 AM d3plot 9/19/09 9:58 PM d3ot01-d3ot162 9/19/09 10:01 PM-80" End Drop d ot o 9/20/09 6:41 AM Output Files messag 9/20/09 6:41 AM End Shell.csv 10/7/09 10:26 AM EndBottom.csv 10/7/09 10:24 AM Note: Date & time (EST) for main runs are from the listing at the end of the output file. For other files (e.g.,.db files), dates & times are reported by the OS on the report issue date, these values may be changed by Windows depending on time of the year (e.g., daylight savings time) and time zones.

Calculation No.: NUH32P+.0203 Revision No.: 0 Page: 19of24 50 40 30 0.E C 20 10 0-10 0 0.01 0.02 0.03 0.04 Time (sec)0.05 0.06 0.07 0.08 Figure 8-1: End Drop Cask Shell Acceleration (g) Time History 180Hz Filter Calculation No.: NUH32P+.0203 Revision No.: 0 Page: 20 of 24 50 40 30 E 20 10 0-10-20 0 0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 Time (sec)Figure 8-2: End Drop Cask Bottom Plates and Resin Acceleration (g) Time History 180Hz Filter Calculation No.: NUH32P+.0203 Revision No.: 0 Page: 21 of 24 E 8000 7000 6000 5000 4000 3000 2000 1000 0 0 200 400 600 800 Frequency (Hz)Figure 8-3: End Drop Cask Shell Fourier Spectral Analysis Before and After Filter 1000 PCalculation No.: NUH32P+.0203 REVA Calculation Revision No.: 0 ANSNUCLEAR INC. Page: 22 of 24 12000 T nffltered data filtered data 10 0 0 0 .................

0 0.. 0 .. ..........

0. ........ ...... .. .8 0 0 0 ...................

........ .E 4000 ------- ----. ... .200 0 200 400 600 800 1000 Frequery (Hz)Figure 8-4: End Drop Cask Bottom Plates + Resin Fourier Spectral Analysis Before and After Filter

-A----,- Calculation No.: NUH32P+.0203 AREVA Calculation Revision No.: 0 TRANSNUCLEAR INC. Page: 23 of 24 9 APPENDIX A -BUTTERWORTH FILTER VERIFICATION

" The butterworth filter used in this analysis is based on the program Octave, an open source code program used for solving linear and nonlinear problems.

An 8 th order low pass butterworth filter is run forward and backwardas described in NUREG/CR-j6608.

To. verify the filter functions properly, the filtered and_unfiltered fourier spectrum plot of the NUREG/CR-6608 is compared to the fourier spectrum plots of this analysis.

Figure Al shows a NUREG/CR-6608 data set which was filtered at 450Hz. The plots of this analysis show good correlation to Figure Al. In addition, Figure A2 shows the frequency response of the 8th order butterworth filter at 450Hz run forward and backward in this analysis.

It can be seen that the frequency response coincides with the attenuation pattern seen in the NUREG/CR-6608 data set.15-0" unfiltered filtered Figure Al -Impulse Response of 8 th Order Butterworth Filter Forward and Backward Calculation No.: NUH32P+.0203 Revision No.: 0 Page: 24 of 24 I 0.8 0.6 E 0.4 0.2 0 0 200 400 600 800 1000 Frequency (Hz)Figure A2 -Frequency Response of 8 th Order Butterworth Filter Forward and Backward ENCLOSURE (1)The File Listing for Three DVDs Containing LS-DYNA Files for NUH32P+.0203 These DVDs have been provided to J. M. Goshen (NRC, NMSS)d3plot d3plotl d3plot2 d3plot3 d3plot4 d3plot5 d3plot6 d3plot7 d3plot8 d3plot9 d3plotlO d3plotll d3plotl2 d3plotl3 d3pIotl4 d3plotl5 d3plotl6 d3plotl7 d3plotl8 d3plotl9 d3plot2O d3plot21 d3plot22 d3plot23 d3plot24 d3plot25 d3plot26 d3plot27 d3plot28 d3plot29 d3plot3O Disk 1 d3plot31 d3pIot32 d3pIot33 d3plot34 d3plot35 d3plot36 d3plot37 d3plot38 d3plot39 d3plot4O d3plot4l d3plot42 d3plot43 d3plot44 d3plot45 d3plot46 d3plot47 d3plot48 d3plot49 d3plot5O d3plot5l d3plot52 d3plot53 d3plot54 d3plot55 d3plot56 d3plot57 d3plot58 d3plot59 d3pIot6O d3plot6l d3plot62 d3pIot63 d3plot64 d3plot65 d3plot66 d3plot67 d3plot68 d3plot69 d3plot7O d3plot7l d3plot72 d3plot73 d3plot74 d3plot75 d3plot76 d3plot77 d3plot78 d3plot79 d3plot8O d3plot8l d3plot82 d3plot83 d3plot84 d3plot85 d3plot86 d3plot87 d3plot88 d3plot89 d3plot9O Disk 2 d3plot9l d3plot92 d3plot93 d3plot94 d3plot95 d3plot96 d3plot97 d3plot98 d3plot99 d3plotlOO d3pIotlO1 d3plotl02 d3plotl03 d3plotl04 d3plotl05 d3plotl06 d3plotl07 d3plotl08 d3plotl09 d3plotl10 d3plotll d3plotl12 d3plotl13 d3plotl14 d3plotl15 d3plotl16 d3plotl17 d3plotl18 d3plotl19 d3plotl20 d3plotl21 d3plot122 d3plot123 d3plot124 d3plotl25 d3plot126 d3plot127 d3plot128 d3plot129 d3plotl30 d3plotl31 d3plot132 d3plot133 d3plot134 d3plot135 d3plot136 d3plot137 d3plot138 d3plot139 d3plotl40 d3plotl4l d3plot142 d3plot143 d3plot144 d3plot145 d3plot146 d3plot147 d3plot148 d3plot149 d3plotl50 Disk 3 d3plot151 d3plot152 d3plot153 d3plot154 d3plot155 d3plot156 d3plot157 d3plotl58 d3plot159 d3plotl60 d3plotl6l d3plot162 32PHBEnd Drop.k Constraints.k Elements.k Messag Nodes.k NodeSets.k SegSets.k Calvert Cliffs Nuclear Power Plant, LLC March 31, 2010 ATTACHMENT (2)NUH32P+.0204, REVISION 0, FUEL END DROP ANALYSIS FOR NUH32P+ USING LS-DYNA, NON-PROPRIETARY VERSION Calvert Cliffs Nuclear Power Plant, LLC March 31, 2010 Non-PROPRIETARY Version A Form 3,241 CnIcuhatlon No.: NUH32P+.0204 r !- E V11 Calculation Cover Sheet Revision No,, 0 TRANSNUCLEAR INC. TTP 3.2 (Revisin ') Page: [ of 24 DCR NO (irappltclne):

N/A PROJECT NAME: NIJIH32P+

Dry Fuel Storage Project ror CCNPP PROJECT NO: NUH32P+ CLiENT'CENG

-Calvert CliffNuclear Power Plant (CCNPP)CALCULATION TITLE: IFtuel End Drop Analysis for NUH32P+ Using LS-DYNA

SUMMARY

DESCRIPI'ION:

I) CaIcuintion Summary The purpose of this calculation is to evaluate the structural adequacy ofNWH32P+

14xt4 filel assembly Zircaloy-4 olad exposed to 80 inch end drop event conditions.

2) Storago Medin Description Secure nietwork server initially, then redundant tape backup.If original Issue, is licensing review per TIll 3.5 requihed?Yes 17 No 0 (explain below) Licensing Review No.: This calculation is prepared to support a Site Specific License Application by CCNPP that will be reviewed and approved by the NRC. Therolboro, a I OCFR72.48 licensing review per TIP 3.5 is aot applicable.

Software Utilized (subject to test requircincits of TIP 3.3): Version: LS-DYNA 1s971s R2 7600,1224 Calculation is complete: 1-luan Li J Originator Name and S.ignure: .Doe: Calculation has been checked for consistency, completeness and correctness:

Raheel aroon Date: Checker Name and Signature:

Calculation is approved for use: Project Engincer Name and Signature:

• REVISIONS A Caic. No.: NUH32P+.0204 ARE VA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 3 of 24 Table of Contents 1.0 Purpose...................................................................................................S 2.0 R~eferences

...................................................................................................

5 3.0 MVethiodology................................................................................................

6 4.0 Assumiptions.................................................................................................

6 5.0 Mlaterial Properties of Fuel Cladding........................................................

...... 7 6.0 Analysis ......................................................................................................

8 6.1 Model Geometry and Details ...... 1-....1.........................I.............................Il...

8 6.2 Fuel cladding ............................................................................................

8 6.3 Cask......................................................................................................

8 6.4 Fuel Pellet Spring.............................I...........................................................

9 6.5 Spacer Grid..........................

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I ..........................

9 6.6 Fuel Compartment......................................................................................

9 6.7 Pin to Cask Spring.....................................................................................

10 6.8 Cask to Ground Interaction.........................................................

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10 6.9 Boundary and Initial Conditions

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10 7.0 Results .........................................................................

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10 8.0 Conclusions

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10 A Calc. No.: NUH32P+.0204 AREVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 4 of 24 List of Tables Page Table 1. Geometry Data for PWR 14x14 Fuel Rod ....... ................................

12 List of Figures Page Figure 1. Schematic of PWR Fuel Cladding Geometry ............................................................................

13 Figure 2. Schematic of the Single Fuel Rod Model .....................................................................................

14 Figure 3. The Details of Single Fuel Rod Model .........................................................................................

15 Figure 4. The Spring Force-Deflection Curve for Fuel Pellets .................................................................

16 Figure 5. The Spring Force-Deflection Curve for Spacer Grids .................................................................

17 Figure 6. The Displacement Time-History of the Cask Bottom Plate ............................................................

18 Figure 7. Displacement Time-History of the Cask in the End Drop Analysis ...........................................

19 Figure 8. The Spring Force-Deflection Curve for Concrete .......................................................................

20 Figure 9. Principal Strain Time-History Response .......................................

21.....Figure 10. Principal Strain Contour Plot .....................................................................................................

22 Figure 11. Fuel Rod and Cask Axial Velocity Time History ......................................................................

23 Figure 12. Fuel Rod and Cask Axial Deceleration Time History ..................................................................

24 A Calc. No.: NUH32P+.0204 AR EVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 5 of 24 1.0 Purpose The purpose of this calculation is to evaluate the structural adequacy of 32P+ 14x 14 fuel assembly Zircaloy-4 clad fuel rod exposed to 80 inch end drop event conditions with an initial gap of 0.04" between the pin bottom and the cask using LS-DYNA model [2.41 developed according to References

[2.1, 2.51.2.0 References

2.1. Harold

E. Adldns, Jr., Brain J. Koeppel and David T. Tang, "Spent Nuclear Fuel Structural Response when Subject to An End Impact Accident", PVP-Vol. 483, Transportation Storage and Disposal of Radioactive Materials, July 25-29, 2004, San Diego, CA, USA.2.2. Not used.2.3. TN Calculation, NUH32P-1095-1, Rev. 0, "NUHOMS 0 32P Weight Calculation of DSC/TC System".2.4. TN Calculation, TN40HT-0217, Rev. 0, "TN40HT Fuel End Drop Analysis Using LS-DYNA".2.5. NUREG- 1864, "A Pilot Probabilistic Risk Assessment Of a Dry Cask Storage System At a Nuclear Power Plant". Date published in March 2007.2.6. TN Calculation, NUH32P+-0203, Rev. 0, "32P+ Transfer Cask Impact onto the Concrete Pad LS-DYNA Analysis (80 inch End Drop)".2,7. DOE/RW-0184, Vol 3 of 6, "Characteristics of Spent Fuel, High Level Waste and other Radioactive Wastes which require Long Term Isolation-Physical Descriptions of LWR Fuel Assemblies," Appendix 2A, U.S.DOE, December, 1987.2.8. Not used.2.9. TN Calculation No. 972-179, Rev. 0, "TN-68 High Burnup Cladding Mechanical Properties".

2.10. CCNPP Calculation, DCALC No. CA06758, "Fuel Performance Data for Calvert Cliffs Dry Storage (ISFS1) Analysis for Batches CIN Through CIT and C2M Through C2S", October 19°', 2006.2.11. Eric R. Siegmann, J. Kevin McCoy, Robert Howard, "Cladding Evaluation in the Yucca Mountain Repositoly Performance Assessment," Material Research Society Symp. Proc. Vol. 608, 2000.

A Calc. No.: NUH32P+,0204 AREVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 6 of 24 Proprietary Information Withheld Pursuant to io CFR 2.390 A Calc. No.: NUH32P+.0204 AREVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 7 of 24 Proprietary Information Withheld Pursuant to Lo CFR 2.390 A Calc. No,: NUH32P+.0204 AREVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 8 of 24 6.0 Analysis 6.1 Model Geometry and Details Figure 2 illustrates thie finite elemient model, which is composed ofa single Fuel rod, a lumped cask mass, springs representing the spacer grids, contact surfaces representing the basket compartment wall, and a spring representing tile target stififess.

Several views of the actual finite element mesh are shown in Figure 3, In this figure, the views shown are: (a) the entire model, (b) top of rod with basket compartment walls and spacer grid spring, (c) top of rod with fuel pellet springs, and (d) bottom of rod with nodes representing the cask and target (concrete).

6.2 Fuel cladding The fuel cladding geometry and other physical properties are presented in Table I and Figure 1.Proprietary Information Withheld .Pursuant to io CFR 2.390 A Calc, No.: NUH32P+.0204 AR EVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 9 of 24 Proprietary Information Withheld Pursuant to io CFR 2.390o A Caic. No.: NUH32P+.0204 AREVA Calculation Rev. No.: 0 TRANSNUCLEAR INC, Page: 10 of 24 Proprietary Information Withheld Pursuant to lo CFR 2.390 7.0 Results The analysis results show that the maximum principal strain of fuel rod is 0.89 %, which is less than the yield strain of 0.92%. The maximum principal strain time-history is shown in Figure 9; and correspondingly the maximum principal strain profile is shown in Figure 10.In addition, the fuel rod and cask velocity and deceleration time histories are shown in Figure 11 and Figure 12, respectively.

8.0 Conclusions

From the above results, the maximum principal stain for the fuel cladding is 0.Wit taUj UV q.AILiLU,UUU tilat LLIV1V 20 &AV jJlaO&J UWkLVJ ictural integrity during the 80 inch end drop event, 1g;0111.1 nnLi Cakc. No.: NUH32P+.0204 AREVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 11 of 24 Proprietary Information Withheld Pursuant to io CFR 2.390 A Cate, No.: NUH32P+.0204 AR EVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 12 of 24 Proprietary Information Withheld Pursuant to io CFR 2.390 A Calc. No.: NUH32P+.0204 AREVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 13 of 24 Proprietary Information Withheld Pursuant to 1o CFR 2.390 A Caic. No.: NUH32P+.0204 AR EVA Calculation Rev. No.: 0 TRANSNUCLEAR INC. Page: 14 of 24 Proprietary Information Withheld Pursuant to ao CFR 2.390/

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