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2010-09-22
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List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 5
Rules and Regulations
D09002ee1bdd9af14
D09002ee1bdd9af90
United States
Nuclear Regulatory Commission
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United States Government Agency or Subagency
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.
72 FR 74162
https://www.govinfo.gov/app/details/FR-2007-12-31/E7-25403
E7-25403
fr31de07-2
RIN 3150-AI24
7590-01-P
https://www.govinfo.gov/app/details/FR-2007-12-31/E7-25403
https://www.govinfo.gov/content/pkg/FR-2007-12-31/html/E7-25403.htm
https://www.govinfo.gov/content/pkg/FR-2007-12-31/pdf/E7-25403.pdf
Administrative Practice and Procedure
Criminal Penalties
Manpower Training Programs
Nuclear Materials
Occupational Safety and Health
Penalties
Radiation Protection
Reporting and Recordkeeping Requirements
Security Measures
Spent Fuel
Whistleblowing
5 p.
74162
74166
72 FR 74162
Code of Federal Regulations
Title 10 Part 72
10 CFR Part 72
Regulation Identification Number 3150-AI24
RIN 3150-AI24
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 5; Federal Register Vol. 72, Issue
RULE
E7-25403
NUCLEAR REGULATORY COMMISSION
2008-03-17
2008-01-30
7590-01-P
E7-25403
Direct final rule.
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.
The final rule is effective March 17, 2008, unless significant adverse comments are received by January 30, 2008. A significant adverse comment is a comment where the commenter explains why the rule would be inappropriate, including challenges to the rule's underlying premise or approach, or would be ineffective or unacceptable without a change. If the rule is withdrawn, timely notice will be published in the Federal Register.
Jayne M. McCausland, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415- 6219, e-mail jmm2@nrc.gov.
Administrative Practice and Procedure
Criminal Penalties
Manpower Training Programs
Nuclear Materials
Occupational Safety and Health
Penalties
Radiation Protection
Reporting and Recordkeeping Requirements
Security Measures
Spent Fuel
Whistleblowing
Spent nuclear fuel and high-level radioactive waste; independent storage; licensing requirements:
Approved spent fuel storage casks; list,
jmm2@nrc.gov
pdr@nrc.gov
SECY@nrc.gov
http://www.nrc.gov/NRC/ADAMS/index.html
http://www.regulations.gov
Federal Register
Vol. 72, no. 249
Office of the Federal Register, National Archives and Records Administration
2007-12-31
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271 p.
Table of Contents:
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https://www.govinfo.gov/app/details/FR-2007-12-31
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https://www.govinfo.gov/app/details/FR-2007-12-31
https://www.govinfo.gov/content/pkg/FR-2007-12-31/pdf/FR-2007-12-31.pdf
https://www.govinfo.gov/content/pkg/FR-2007-12-31/xml/FR-2007-12-31.xml
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