Nuclear Regulatory Commission December 31, 2007 – Federal Register Recent Federal Regulation Documents

Geologic Repository Operations Area Security and Material Control and Accounting Requirements; Meeting
Document Number: E7-25415
Type: Notice
Date: 2007-12-31
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) has published a proposed rule on Geologic Repository Operations Area Security and Material Control and Accounting Requirements for public comment (72 FR 72522; December 20, 2007). The public comment period runs from December 20, 2007 thru March 4, 2008. As part of the public comment process, the NRC plans to hold a transcribed public meeting to solicit comments on the proposed rule. NRC staff will be taking comments only and will not be prepared to discuss or respond to comments or questions on the rule. The meeting is open to the public and all interested parties may attend. The meeting will be held on January 23, 2008, in the NRC Hearing Facility at the Pacific Enterprise Plaza, Building One, 3250 Pepper Lane, Las Vegas, Nevada. During the comment period, comments may also be mailed to the NRC or submitted via fax or e-mail.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 5
Document Number: E7-25414
Type: Proposed Rule
Date: 2007-12-31
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage cask regulations by revising the Holtec International 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 would include deletion of the requirement to perform thermal validation tests on thermal systems; an increase in the design basis maximum decay heat loads, namely, to 34 kilowatts (kW) for uniform loading and 36.9 kW for regionalized loading, and introduction of 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 from 700 to 730 pounds; 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, MPC-24E, 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 definitions 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.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 5
Document Number: E7-25403
Type: Rule
Date: 2007-12-31
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is amending its spent fuel storage cask regulations by revising the Holtec International 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, namely, to 34 kilowatts (kW) for uniform loading and 36.9 kW for regionalized loading, and introduction of 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 from 700 to 730 pounds; 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 16 x 16 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, MPC-24E, 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 definitions 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.
Security Officer Attentiveness
Document Number: E7-25398
Type: Notice
Date: 2007-12-31
Agency: Nuclear Regulatory Commission, Agencies and Commissions
All holders of operating licenses for nuclear power reactors, except those who have permanently ceased operation and have certified that fuel has been removed from the reactor vessel, and Category I fuel facilities. The contents of this bulletin are for information to Category III fuel facilities, independent spent fuel storage installations, conversion facilities and gaseous diffusion plants. The U.S. Nuclear Regulatory Commission (NRC) is issuing this bulletin to achieve the following three objectives: 1. The agency is notifying addressees about the NRC staff's need for information associated with licensee security program administrative and management controls as a result of security personnel inattentiveness, especially involving complicity, and related concerns with the behavior observation program (BOP). The information is needed to determine if further regulatory action is warranted, if the necessary inspection program needs to be enhanced, or if additional assessment of security program implementation is needed. 2. The NRC seeks to obtain information on licensee administrative and managerial controls to deter and address inattentiveness and complicity among licensee security personnel including contractors and subcontractors. 3. This bulletin requires that addressees provide a written response to the NRC in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(f) or 10 CFR 70.22(d). This Federal Register notice is available through the NRC's Agencywide Documents Access and Management System (ADAMS) under accession number ML073480342.