ML24310A057
| ML24310A057 | |
| Person / Time | |
|---|---|
| Site: | 07109378 |
| Issue date: | 10/29/2024 |
| From: | Holtec |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| Download: ML24310A057 (1) | |
Text
HI-STAR 100MB Type B(U)F Transportation Package Pre-Application Presentation to NRC October 29th, 2024 Presentation Agenda Introduction Summary of Proposed Changes www.holtecinternational.com
l Page 2 - Holtec Information Design Overview Summary and Licensing Schedule Questions and Discussion
l Page 3 - Holtec Information Introduction Holtec is preparing a license amendment request for the HI-STAR 100MB transportation package.
The HI-STAR 100MB transportation package is engineered to serve as a type B(U)F-96 package for spent nuclear fuel.
The HI-STAR 100MB transportation package is currently licensed under USNRC Docket No. 71-9378.
l Page 4 - Holtec Information Summary of Proposed Changes Introduction of monolithic shield cylinder (MSC) variants of the existing HI-STAR 100MB cask embodiments, with modified impact limiter designs.
Inclusion of MPC-24, 32, 32DC, 32M, 32MCBS, 68, 68M, and 68MCBS canisters already designed for storage in the HI-STORM 100 system.
Introduction of continuous basket shim (CBS) variants of the F-24M and F-32M bare basket designs already approved for transportation in the HI-STAR 100MB system.
Allowance for metallic seals at additional containment boundary sealing surfaces.
Additional loading flexibility using thermal and shielding topical approaches.
l Page 5 - Holtec Information Design Overview Top Impact Limiter Bottom Trunnions Bottom Impact Limiter MSC Cask Body Top Trunnions
l Page 6 - Holtec Information Structural Safety Overview Safety analysis predominantly following that currently approved for the HI-STAR 100MB Containment Integrity: continued compliance with stress intensity limits per ASME B&PV Code Division 1 Subsection NB Closure Lid Seal Joint: satisfy leak rate acceptance criteria under NCT and HAC specified in currently approved HI-STAR 100MB SAR Stainless Steel Baskets: continued compliance with stress intensity limits per ASME P&BV Code Subsection NG Metamic HT Baskets: new acceptance criteria utilizing stress-based approach consistent with HI-STORM FW Amendment 7 (approved by the USNRC)
Thermal Safety Overview Methodology identical to that currently approved for the HI-STAR 100MB 3-Dimensional thermal models developed using ANSYS-FLUENT
l Page 7 - Holtec Information Models for MPC-24, 32, 32DC, 32M, 32MCBS, 68, 68M, and 68MCBS canisters adopted from HI-STORM 100 storage system New models for CBS variants of F-24M and F-32M bare baskets Peak Cladding Temperature (PCT) demonstrated to be within NUREG-2216 temperature limit Cask component temperatures and cask cavity pressures demonstrated to be within design limits Flexibility in loading configuration using topical approach Containment Safety Overview Methodology identical to that currently approved for the HI-STAR 100MB Continued compliance with the radionuclide release rates specified in 10CFR71.51.
Continued compliance with containment-related general standards for all packages as enumerated in 10CFR71.43 (c), (d), (e), and (f).
l Page 8 - Holtec Information Shielding Safety Overview Methodology identical to that currently approved for the HI-STAR 100MB Normal Conditions of Transport: continued compliance with dose rates specified in 10CFR71.47 Hypothetical Accident Conditions: continued compliance with dose rates specified in 10CFR71.51(a)(2)
Flexibility in loading configuration using topical approach
l Page 9 - Holtec Information Criticality Safety Overview MPC-24, 32, 32DC, and 68 demonstrated by reference to HI-STAR 100 licensed under USNRC Docket No. 71-9261 MPC-32M, 32MCBS, 68M, and 68MCBS demonstrated by reference to HISTORM 100 licensed under USNRC Docket No. 72-1014 CBS variants of F-24M and F-32M bare baskets to be evaluated using methodology identical to that currently approved for the HI-STAR 100MB Damaged fuel and/or fuel debris to be evaluated using methodology currently approved for the HI-STAR 190 under USNRC Docket No. 71-9373
l Page 10 - Holtec Information Summary and Licensing Schedule Design details, materials and safety analyses approaches are essentially identical to those for HI-STAR and HI-STORM family of casks or based on proven practice and/or techniques which supports an efficient licensing process Planned Submittal January 2025 Requesting standard review priority and approval by Summer 2026
l Page 11 - Holtec Information Questions and Discussion