Nuclear Regulatory Commission October 13, 2009 – Federal Register Recent Federal Regulation Documents

Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB) Review; Comment Request
Document Number: E9-24589
Type: Notice
Date: 2009-10-13
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. The NRC published a Federal Register Notice with a 60-day comment period on this information collection on June 30, 2009.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 7
Document Number: E9-24562
Type: Proposed Rule
Date: 2009-10-13
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 Holtec International (Holtec) HI-STORM 100 dry storage cask system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 7 to Certificate of Compliance (CoC) Number 1014. Amendment No. 7 would modify the CoC to add the HI-STORM 100U system to the HI-STORM 100 cask system. The HI-STORM 100U system allows for the underground storage of dry spent nuclear fuel (SNF) by utilizing an underground vertical ventilated module (VVM) that can accept certain multipurpose canisters (MPCs) previously certified for storage of SNF in the Holtec aboveground HI-STORM system. In addition, the amendment would reinstate the decay heat limits for damaged fuel and fuel debris in Appendix B, Technical Specification (TS) 2.4, for the aboveground system that had been inadvertently deleted from Amendment Nos. 5 and 6; incorporate separate TS Appendices A and B for the aboveground system (Apps. A and B) and for the HI-STORM 100U system (Apps. A-100U and B- 100U); revise Appendix B, TS 3.4.5, to be consistent with the required system thermal boundary conditions, as submitted in the applicant's safety analysis report for a fire accident condition, and with Holtec's original (i.e., initial certificate application or Amendment 0) submittal and the NRC's original safety evaluation report; and revise and add certain definitions in Appendix A, TS 1.1, to include the VVM. The amendment will also incorporate minor editorial corrections in the TS for the aboveground system.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 7
Document Number: E9-24561
Type: Rule
Date: 2009-10-13
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International (Holtec) HI-STORM 100 dry cask storage system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 7 to Certificate of Compliance (CoC) Number 1014. Amendment No. 7 will modify the CoC to add the HI-STORM 100U system to the HI-STORM 100 cask systems. The HI-STORM 100U system allows for the underground storage of dry spent nuclear fuel (SNF) by utilizing an underground vertical ventilated module (VVM) that can accept certain Holtec multipurpose canisters (MPCs) previously certified for storage of SNF in the aboveground HI-STORM system. The amendment also incorporates a mandatory radiation protection perimeter around the loaded VVMs. In addition, the amendment will reinstate the decay heat limits for damaged fuel and fuel debris in Appendix B, Technical Specification (TS) 2.4, for the aboveground system that had been inadvertently deleted from Amendment Nos. 5 and 6; incorporate separate TS Appendices A and B for the aboveground system (Apps. A and B) and for the HI-STORM 100U system (Apps. A-100U and B-100U); revise Appendix B, TS 3.4.5, to be consistent with the required system thermal boundary conditions, as submitted in the applicant's safety analysis report for a fire accident condition, and with Holtec's original (i.e., initial certificate application or Amendment 0) submittal and the NRC's original safety evaluation report; and revise and add certain definitions in Appendix A, TS 1.1, to include the VVM. The amendment will also incorporate minor editorial corrections in the TS for the aboveground system.
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