ML23005A006
| ML23005A006 | |
| Person / Time | |
|---|---|
| Site: | Holtec |
| Issue date: | 01/04/2023 |
| From: | Holtec |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML23005A000 | List: |
| References | |
| 5014954, EPID L-2021-LLA-0039 | |
| Download: ML23005A006 (1) | |
Text
1.IV.5 Licensing Drawings:
The licensing drawing package for the Version UVH overpack is provided in this section. The licensing drawing package in this section also contains the ITS category for Version UVH components and contains dimensions of safety significant parts and subassemblies.
Drawing Number Title Revision 12233 HI-STORM 100 UVH Overpack 0
Critical dimensions for the HI-STORM 100 UVH Overpack are recorded in report [1.IV.1].
[PROPRIETARY DRAWINGS WITHHELD IN ACCORDANCE WITH 10CFR2.390]
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Proposed Revision 21D 1.IV-16
1.IV.6
References:
[1.IV.1] HI-STORM 100 UVH CRITICAL DIMENSION REPORT, Holtec Report No.
HI-2210277, Latest Revision (Holtec Proprietary)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Proposed Revision 21D 1.IV-17
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Table 3.IV.4.6, summarizes the maximum plastic strain results, along with the corresponding material failure stain. Further details pertaining this analysis are presented in [3.IV.15].
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3.IV.4.3.5 Snow Load
The stress analysis of the overpack lid under snow load condition is performed using ANSYS
[3.IV.9]. The finite element model used is essentially the same as shown in Figure 3.IV.4.1 apart from the loads and the boundary conditions. The normal snow pressure of 100 lb/ft2 is used per HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-16
Table 2.2.8 of the FSAR [3.IV.1]. The resulting stress distribution in the steel structure of the overpack lid under the applied snow load is shown in Figure 3.IV.4.2726. The maximum stresses and the corresponding safety factors are summarized in Table 3.IV.4.8 per [3.IV.10]. For conservatism, the maximum primary stress in the lid is compared against the primary membrane and primary bending stress limits per Subsection NF (class 3 structures) of the ASME Code for Level A conditions. The allowable stresses are taken at bounding temperature, which exceeds the maximum operating temperature for the overpack top lid under normal operating conditions.
3.IV.4.3.6 Design Basis Earthquake
As noted in Table 2.IV.2.1, because the outer diameter (OD) and height of the CG of Version UVH cask are essentially identical to the reference cask analyzed in Chapter 3, the discussion in Section 3.4.7 per [3.IV.1] is applicable to Version UVH cask. Hence, no new analysis for the design basis earthquake is warranted.
3.IV.4.3.7 Cold
The value of the ambient temperature has two principal effects on the HI-STORM 100 Version UVH system, namely:
- i. The steady-state temperature of all material points in the cask system will go up or down by the amount of change in the ambient temperature.
ii. As the ambient temperature drops, the absolute temperature of the contained helium will drop accordingly, producing a proportional reduction in the internal pressure in accordance with the Ideal Gas Law.
In other words, the temperature gradients in the system under steady-state conditions will remain the same regardless of the value of the ambient temperature. The internal pressure, on the other hand, will decline with the lowering of the ambient temperature. Since the stresses under normal storage condition arise principally from pressure and thermal gradients, it follows that the stress field in the MPC under the limiting cold ambient condition (-40 degree F) would be smaller than the "heat" condition of storage, treated in the preceding subsection. Additionally, the allowable stress limits tend to increase as the component temperatures decrease.
Therefore, the stress margins computed in the foregoing subsection can be conservatively assumed to apply to the "cold" condition as well.
Finally, as discussed below, the system is engineered to withstand cold temperatures (-40 degrees F) without impairment of its storage function.
Unlike the MPC, the HI-STORM storage overpack is subject to very low internal pressure as noted in Table 2.IV.2.3. Its stress field is unaffected by the ambient temperature, unless low temperatures produce brittle fracture due to the small stresses which develop from self-weight of the structure and from the minute difference in the thermal expansion coefficients in the constituent parts of the equipment (steel and concrete). To prevent brittle fracture, all structural steel material in the HI-STORM overpack is qualified by impact testing pursuant to the ASME Code.
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-17
Table 3.IV.4.6: Maximum Local True Plastic Strain Results (MPC-32M)
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Table 3.IV.4.7: Maximum Local True Plastic Strain Results (MPC-68M)
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HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-25
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Figure 3.IV.4.15: Maximum Plastic Strain - MPC 32M Fuel Basket
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-41
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Figure 3.IV.4.16: Maximum Plastic Strain - MPC 32M Enclosure Vessel
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-42
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Figure 3.IV.4.17: Maximum Plastic Strain - MPC 32M HI-STORM Overpack (Excluding Concrete)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-43
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Figure 3.IV.4.18: Maximum Plastic Strain - MPC 32M HI-STORM Overpack Closure Lid Bolts
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-44
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Figure 3.IV.4.19: Maximum Plastic Strain - MPC 32M HI-STORM Overpack Lid (lid is not be dislodged, and primary strains are within the failure limit of the material)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-45
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Figure 3.IV.4.20: Finite element model of the cross-section for MPC-68M internals with Orientation No. 1 (0 degree)
Vertical Rigid Body Deceleration Time History - Fuel assemblies (Top of Fuel)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-46
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PROPRIETARY INFORMATION WITHHELD IN ACCORDANCE WITH 10CFR2.390
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Figure 3.IV.4.21: Finite element model of the cross-section for MPC-68M internals with Orientation No. 2 (45 degree)Finite element model of MPC-68M with Orientation No. 1
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Figure 3.IV.4.22: Finite element model of MPC-68M with Orientation No. 2Maximum Plastic Strain - MPC 68M Fuel Basket
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-47
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PROPRIETARY INFORMATION WITHHELD IN ACCORDANCE WITH 10CFR2.390
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Figure 3.IV.4.23: Deceleration of the SFA (Orientation No. 1)Maximum Plastic Strain - MPC 68M Enclosure Vessel
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-48
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Figure 3.IV.4.24: Maximum Plastic Strain - MPC 68M HI-STORM Overpack (Excluding Concrete) in MPC-68M Basket (Orientation No. 1)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-49
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Figure 3.IV.4.25: Maximum Plastic Strain - MPC 68M HI-STORM Overpack Closure Lid BoltsPlastic Strain in MPC-68M Basket (Orientation No. 1)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-50
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Figure 3.IV.4.26: Maximum Plastic Strain - MPC 68M HI-STORM Overpack Lid (The primary strains are within the material's failure limit; hence the lid will not dislodge)
(lid is not dislodged, and primary strains are within the failure limit of the material)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-51
Figure 3.IV.4.276: Principal Stress in HI-STORM 100 Version UVH Lid under snow load
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-52
3.IV.6 References
[3.IV.1] HI-STORM 100 FSAR, Holtec Report No.2002444, latest Revision.
[3.IV.2] HI-STORM FW FSAR, Holtec Report No.2114830, latest Revision.
[3.IV.3] NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants," United States Nuclear Regulatory Commission.
[3.IV.4] Regulatory Guide 3.61 (Task CE306-4) Standard Format for a Topical Safety Analysis Report for a Spent Fuel Storage Cask, USNRC, February 1989.
[3.IV.5] ASME Boiler & Pressure Vessel Code,Section III, Sub-section NB, 1995 Edition with addenda up to and including 2010.
[3.IV.6] ASME Boiler & Pressure Vessel Code,Section III, Sub-section NF, 1995 Edition with addenda up to and including 2010.
[3.IV.7] Crane Manufacturer's Association of America (CMAA), Specification#70, 1988, Section 3.3.
[3.IV.8] Structural Calculation Package for HI-STORM Overpack, Holtec Report No. HI-2012769, Revision 18.
[3.IV.9] ANSYS 17.1, ANSYS, Inc., 2016.
[3.IV.10] Structural Calculation Package for HI-STORM 100 Version UVH Storage Cask, Holtec Report No. HI-2210241, Revision 0.
[3.IV.11] Bechtel Topical Report BC-TOP-9A, Design of Structures for Missile Impact, Revision 2 (September 1974).
[3.IV.12] 10CFR71, Waste Confidence Decision Review, USNRC, September 11, 1990.
[3.IV.13] LS-DYNA, Version 971, Livermore Software Technology, 2006.
[3.IV.14] Witte, M., et al., "Evaluation of Low-Velocity Impacts Tests of Solid Steel Billet onto Concrete Pads, and Application to Generic ISFSI Storage Cask for Tipover and Side Drop," Lawrence Livermore National Laboratory, UCRL-ID-126295, Livermore, California, March 1997.
[3.IV.15] Analysis of the Non-Mechanistic Tipover Event of the Loaded HI-STORM 100 Version UVH Storage Cask, Holtec Report No. HI-2210290, Revision 10.
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2002444 Proposed Rev. 21D 3.IV-53