ML18192B761
| ML18192B761 | |
| Person / Time | |
|---|---|
| Site: | 07109378 |
| Issue date: | 07/11/2018 |
| From: | Holtec |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML18192B756 | List: |
| References | |
| 5014851, EPID L-2018-NEW-0000 | |
| Download: ML18192B761 (3) | |
Text
NRC RSI 3-2 Provide figures of the regionalized storage arrangements (per cell allowable heat loads) of the MPC-32M, and the bare basket configurations F
-24M and F-32M, to verify the heat load profiles selected in the thermal analysis.
The applicant states, in Section 3.1.4, that "the uniform heat load case bounds all regionalized storage arrangements that meet the requirements of (i), (ii) and (iii) as shown in pages 3.1
-2 and 3.1-3." Figures of the regionalized storage arrangements (per cell allowable heat loads) for the MPC-32M, and the bare basket configurations F
-24M and F-32M, are needed to verify the per cell heat load distribution and the bounding correlation between regionalized and uniform loadings.
This information is required to determine compliance with 10 CFR 71.71 and 71.73. Holtec's Response to RSI 3-2 As justified herein figures are not necessary for implementing regionalized storage. Regionalized storage is defined in the 100MB application as an allowance for users to load hot fuel by trading heat from interior located cells to cells located at further radial distances
- 1. In this manner regionalized storage yields storage scenarios wherein heat sources are moved away from interior locations thus mitigating fuel temperatures. The proposed allowance is defined by requirements (i),
(ii) and (iii) cited by the reviewer. Regionalized storage examples constructed in accordance with these requirements are provided in supporting Calculation Package HI
-2188066 to demonstrate these yield lower than licensing basis temperatures. The Calculation Package is provided as to Letter No. 5014847.
1 Radial distance defined as the distance from basket center to cell center.
NRC Observation 6-1 Provide the sources of the material composition data used in the criticality safety analyses.
Table 6.3.5 of the application provides the material composition data of the major components of the HI-STAR 100MB packaging but does not provide the sources of such data. Because the material composition data is critical to the accuracy of the criticality safety analyses, the applicant needs to provide the sources of the data and demonstrate that the data is reliable and accurate.
This information is required to demonstrate compliance with 10 CFR 71.55(b), 71.55(d), and 71.55(e).
Holtec's Response to Observation 6-1 For all materials in Table 6.3.5, except stainless steel and carbon steel, the reference, as noted in Appendix A of the HI-STAR 100MB criticality evaluation package [6-1.1], for: the atomic weight ratios is MCNP5-1.51 xsdir data file (i.e. ENDF/B-VII [6-1.2]); the natural abundances is NEA database, such as NUBASE, accessed using the Java
-based Nuclear Data Information System (JANIS) [6-1.3]; the molecules such as B 4C and H 2O are calculated according to their respective chemical structure.
From the three items above and input parameters, such as fuel enrichment and B 4C content in Metamic-HT (both assumed values), all materials in Table 6.3.5, except stainless steel and carbon steel, are derived.
The stainless steel material used in the HI
-STAR 100MB criticality safety analysis is identical to the stainless steel material used in the previously approved HI
-STAR 100 SAR [6
-1.4] and the HI
-STORM 100 FSAR [6
-1.5]. The carbon steel material used in the HI
-STAR 100MB criticality safety analysis is referenced from [6
-1.6]. Additionally, [6
-1.7] supports both the stainless steel and carbon steel material compositions used in the HI
-STAR 100MB criticality safety analysis.
Therefore, the information in Appendix A of [6
-1.1] is sufficient to demonstrate that the material compositions considered for the HI
-STAR 100MB criticality safety analysis are reliable and accurate.
References
[6-1.1] Holtec International Report HI
-2188084, "Criticality Evaluation of HI
-STAR 100MB", Revision 0.
[6-1.2] "ENDF/B
-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology", UCRL
-JRNL-225066, October 2006, Lawrence Livermore National Laboratory.
[6-1.3] N. Soppera, M. Bossant, and E. Dupont, "JANIS 4: An Improved Version of the NEA Java
-based Nuclear Data Information System", Nuclear Data Sheets, Volume 120, June 2014, Pages 294-296. [6-1.4] Holtec International Report HI
-951251, Safety Analysis Report HI
-STAR 100 Cask System, USNRC Docket 71-9261, Revision 17.
[6-1.5] Holtec International Report HI
-2002444, Final Safety Analysis Report for the HI
-STORM 100 CASK System, USNRC Docket 72-1014, Revision 14.
[6-1.6] "Compendium of Material Composition Data for Radiation Transport Modeling," PNNL
-15870, Rev. 1, Pacific Northwest National Laboratory.
[6-1.7] "Criticality Calculations with MCNP5: A Primer", LA
-UR-09-00380, January 2009, Los Alamos National Laboratory.