ML25211A200

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List of Changes for Magnastor FSAR, Amendment 17 - Initial Submittal, Revision 25C & FSAR Changed Pages for Magnastor FSAR, Amendment 17 - Initial Submittal, Revision 25C
ML25211A200
Person / Time
Site: 07201031
Issue date: 07/30/2025
From:
Kanadevia Group, NAC International
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML25211A197 List:
References
ED20250099
Download: ML25211A200 (1)


Text

Atlanta Corporate Headquarters: 2 Sun Court, Suite 220, Norcross, Georgia 30092 USA Phone 770-447-1144, www.nacintl.com July 2025 Docket No. 72-1031 MAGNASTOR (Modular Advanced Generation Nuclear All-purpose STORage)

FINAL SAFETY ANALYSIS REPORT Amendment 17 Initial Submittal NON-PROPRIETARY VERSION Revision 25C

to ED20250099 Page 1 of 2 Supporting Calculations for MAGNASTOR FSAR, Amendment 17 Initial Submittal Revision 25C (Docket No 72-1031)

NAC International July 2025 to ED20250099 Page 2 of 2 List of Calculations:

1. 71160-2026 Rev. 2
2. 71160-2049 Rev. 4 CALCULATIONS WITHHELD IN THEIR ENTIRETY PER 10 CFR 2.390 to ED20250099 Page 1 of 2 List of Changes for MAGNASTOR FSAR Amendment 17 Initial Submittal Revision 25C (Docket No 72-1031)

NAC International July 2025 to ED20250099 Page 2 of 2 List of Changes for the MAGNASTOR FSAR, Revision 25C Chapters 1 thru 2 No Changes Chapter 3 Page 3.8-3, revised text where indicated.

Page 3.8-8 thru 3.8-9, revised text where indicated.

Page 3.9-3, deleted reference 35.

Chapter 4 thru 15 No Changes to ED20250099 Page 1 of 1 FSAR Changed Pages for MAGNASTOR FSAR, Amendment 17 Initial Submittal Revision 25C (Docket No 72-1031)

NAC International July 2025

Atlanta Corporate Headquarters: 2 Sun Court, Suite 220, Norcross, Georgia 30092 USA Phone 770-447-1144, www.nacintl.com July 2025 Docket No. 72-1031 MAGNASTOR (Modular Advanced Generation Nuclear All-purpose STORage)

FINAL SAFETY ANALYSIS REPORT NON-PROPRIETARY VERSION Revision 25C

MAGNASTOR System FSAR July 2025 Docket No. 72-1031 Revision 25C NAC International 3.8-3 In all cases, the thickness of the clad was reduced by 120 microns (0.0047 inch). Cases 1 through 4 require a separate ANSYS model and LS-DYNA model to represent unique coordinates or boundary conditions (geometry of Case 5 is the same as for Case 3). The LS-DYNA model employs the same nodes and elements as the ANSYS model (with the incorporation of the 0.55-inch bow). Elastic properties are used in the ANSYS model and the bilinear properties are employed in the LS-DYNA model. An initial downward velocity of 136 in/sec (corresponding to a 24-inch end drop for the storage condition) is assigned to all nodes in the model. The deceleration time history is applied to the nodes of the brick elements representing the fuel tube. The side walls of the fuel tube are restrained in the lateral direction to maximize the effect of the fuel rods impacting the fuel tube side wall.

The LS-DYNA analyses for Cases 1 through 4 were performed for the duration of 0.08 second to capture the response of the fuel after the 0.02 second loading duration. Post-processing each analysis result identifies the maximum shear stress occurring at the shell surface. The maximum shear stress result from LS-DYNA is factored by two to determine the maximum stress intensity.

The following table contains the maximum stress intensity for the five cases.

Maximum Stress Intensity for the Five LS-DYNA Analyses Case Maximum Stress Intensity (ksi)

Factor of Safety Against Yield Strength 1

25.4 2.36 2

21.8 2.75 3

41.9 1.43 4

34.7 1.73 5

22.0 2.72 The case using the 60-inch spacing in conjunction with the minimal cross-section (Case 3) is identified as the bounding case. All stresses were shown to be less than the yield strength of 59.9 ksi. This yield strength corresponds to high burnup M5 cladding at a temperature of 350°C based on published test data [34]. The reported factors of safety are bounding for other cladding materials, as the yield strength of high burnup Zircaloy-4 and ZIRLO at 350°C exceeds that of M5.

The results confirm that high burnup PWR fuel with a maximum distance of 60 inches from the bottom to the first grid will remain structurally adequate for the storage design basis cask end drop load conditions.

MAGNASTOR System FSAR July 2025 Docket No. 72-1031 Revision 25C NAC International 3.8-8 3.8.4 Tip-over Evaluation A structural evaluation is performed for PWR and BWR high burnup fuel rods for the non-mechanistic tip-over accident of the MAGNASTOR Storage Cask (Concrete or MSO).

NAC PROPRIETARY INFORMATION REMOVED

MAGNASTOR System FSAR July 2025 Docket No. 72-1031 Revision 25C NAC International 3.8-9 NAC PROPRIETARY INFORMATION REMOVED

MAGNASTOR System FSAR July 2025 Docket No. 72-1031 Revision 25C NAC International 3.9-3

32. Volterra, Enrico and Gaines, J. H., Advanced Strength of Materials, Prentice-Hall, Inc.,

Englewood Cliffs, NJ, 1971.

33. U.S. Department of Energy, PNNL-17700, PNNL Stress/Strain Correlation for Zircaloy, Geelhood, K.J, et al., July 2008.
34. B. Cazalis, C., et al., The PROMETRA Program: A Reliable Material Database for Highly Irradiated ZIRCALOY-4, ZIRLOTM, and M5TM Fuel Claddings, Proceedings of the 18th International Conference on Structural Mechanics in Reactor Technology, Beijing, China, August 2005.
35. [Deleted]