Nuclear Regulatory Commission July 21, 2010 – Federal Register Recent Federal Regulation Documents

List of Approved Spent Fuel Storage Casks: NAC-MPC System, Revision 6
Document Number: 2010-17848
Type: Rule
Date: 2010-07-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International Inc. (NAC) NAC-MPC System listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 6 to Certificate of Compliance (CoC) Number 1025. Amendment No. 6 to the NAC-MPC System CoC will include the following changes to the configuration of the NAC-MPC storage system as noted in Appendix B of the Technical Specifications (TS): Incorporation of a single closure lid with a welded closure ring for redundant closure into the Transportable Storage Canister (TSC) design; modification of the TSC and basket design to accommodate up to 68 La Crosse Boiling Water Reactor (LACBWR) spent fuel assemblies (36 undamaged Exxon fuel assemblies and up to 32 damaged fuel cans (in a preferential loading pattern)) that may contain undamaged Exxon fuel assemblies and damaged Exxon and Allis Chalmers fuel assemblies and/or fuel debris; the addition of zirconium alloy shroud compaction debris to be stored with undamaged and damaged fuel assemblies; minor design modifications to the Vertical Concrete Cask (VCC) incorporating design features from the MAGNASTOR system for improved operability of the system while adhering to as low as is reasonably achievable (ALARA) principles; an increase in the concrete pad compression strength from 4,000 psi to 6,000 psi; added justification for the 6-ft soil depth as being conservative; and other changes to incorporate minor editorial corrections in CoC No. 1025 and Appendices A and B of the TS. Also, the Definitions in TS 1.1 will be revised to include modifications and newly defined terms; the Limiting Conditions for Operation and associated Surveillance Requirements in TS 3.1 and 3.2 will be revised; and editorial changes will be made to TS 5.2 and 5.4.
List of Approved Spent Fuel Storage Casks: NAC-MPC System, Revision 6
Document Number: 2010-17847
Type: Proposed Rule
Date: 2010-07-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage cask regulations by revising the NAC International, Inc. (NAC), NAC-MPC System listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 6 to Certificate of Compliance (CoC) Number 1025. Amendment No. 6 would include the following changes to the configuration of the NAC-MPC storage system as noted in Appendix B of the Technical Specifications (TS): incorporation of a single closure lid with a welded closure ring for redundant closure into the Transportable Storage Canister (TSC) design; modification of the TSC and basket design to accommodate up to 68 La Crosse Boiling Water Reactor spent fuel assemblies (36 undamaged Exxon fuel assemblies and up to 32 damaged fuel cans (in a preferential loading pattern)) that may contain undamaged Exxon fuel assemblies and damaged Exxon and Allis Chalmers fuel assemblies and/or fuel debris; the addition of zirconium alloy shroud compaction debris to be stored with undamaged and damaged fuel assemblies; minor design modifications to the Vertical Concrete Cask (VCC) incorporating design features from the MAGNASTOR system for improved operability of the system while adhering to as low as is reasonably achievable (ALARA) principles; an increase in the concrete pad compression strength from 4000 psi to 6000 psi; added justification for the 6-ft soil depth as being conservative; and other changes to incorporate minor editorial corrections in CoC No. 1025 and Appendices A and B of the TS. Also, the Definitions in TS 1.1 will be revised to include modifications and newly defined terms; the Limiting Conditions for Operation and associated Surveillance Requirements in TS 3.1 and 3.2 will be revised; and editorial changes will be made to TS 5.2 and 5.4.
Firstenergy Nuclear Operating Company; Request for Licensing Action
Document Number: 2010-17834
Type: Notice
Date: 2010-07-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Notice of Availability of Draft Environmental Impact Statement and Public Meeting for the AREVA Enrichment Services, LLC Proposed Eagle Rock Uranium Enrichment Facility
Document Number: 2010-17788
Type: Notice
Date: 2010-07-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment the Draft Environmental Impact Statement (EIS) for the proposed AREVA Enrichment Services LLC (AES) Eagle Rock Enrichment Facility (EREF). On December 30, 2008, AES submitted a license application to the NRC that proposes the construction, operation, and decommissioning of a gas centrifuge-based uranium enrichment facility on a presently undeveloped site near Idaho Falls in Bonneville County, Idaho (the ``proposed action''). The license application included an Environmental Report (ER) regarding the proposed action.