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NRC | RIN: 3150-AI24 | Publication ID: Fall 2008 |
Title: List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 5 | |
Abstract: This direct final rule amends the Commission's regulations that apply to storage of spent fuel by revising the Hi-Storm 100 cask system listing within the "List of Approved Spent Fuel Storage Casks" to include Amendment No. 5 to Certificate of Compliance (CoC) Number 1014. Amendment No. 5 includes deletion of the requirement to perform thermal validation tests on thermal systems, an increase in the design basis maximum decay heat loads and a new decay heat regionalized scheme; an increase in the maximum fuel assembly weight for boiling water reactor fuel in the Multi-Purpose Canister (MPC)-68; an increase in the maximum fuel assembly weight of up to 1,720 pounds for assemblies not requiring spacers, otherwise 1,680 pounds; changes to the assembly characteristics of 16x16 pressurized water reactor fuel assemblies to be qualified for storage in the HI-Storm 100 cask system, a change in the fuel storage locations in the MPC-32 for fuel with axial power shaping rod assemblies and in the fuel storage locations in the MPC-24 and the MPC-32 for fuel with control rod assemblies, rod cluster control assemblies, and control element assemblies; elimination of the restriction that fuel debris can only be loaded into the MPC-24EF, MPC-32F, MPC-68F, and MPC-68FF canisters; introduction of a requirement that all MPC confinement boundary components and any MPC components exposed to spent fuel pool water or the ambient environment be made of stainless steel or, for MPC internals, neutron absorber or aluminum; the addition of a threshold heat load below which operation of the Supplemental Cooling System would not be required and modification of the design criteria to simplify the system; minor editorial changes to include clarification of the description of anchored casks, correction of typographical/editorial errors, clarification of the definition of loading operations, storage operations, transport operations, unloading operations, cask loading facility, and transfer cask in various locations throughout the CoC and Final Safety Analysis Report; and modification of the definition of non-fuel hardware to include the individual parts of the items defined as non-fuel hardware. | |
Agency: Nuclear Regulatory Commission(NRC) | Priority: Substantive, Nonsignificant |
RIN Status: Previously published in the Unified Agenda | Agenda Stage of Rulemaking: Completed Actions |
Major: No | Unfunded Mandates: No |
CFR Citation: 10 CFR 72 | |
Legal Authority: 42 USC 2201 42 USC 5841 |
Legal Deadline:
None |
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Timetable:
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Regulatory Flexibility Analysis Required: No | Government Levels Affected: None |
Small Entities Affected: No | |
Included in the Regulatory Plan: No | |
RIN Data Printed in the FR: No | |
Agency Contact: Jayne M. McCausland Nuclear Regulatory Commission Office of Federal and State Materials and Environmental Management Programs, Washington, DC 20555-0001 Phone:301 415-6219 Email: jayne.mccausland@nrc.gov |