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Home Page > Executive Branch > Code of Federal Regulations > Electronic Code of Federal Regulations

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e-CFR Data is current as of November 19, 2009

TITLE 10--Energy

CHAPTER I--NUCLEAR REGULATORY COMMISSION

PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE

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Subpart A--GENERAL PROVISIONS

§72.1
Purpose.
§72.2
Scope.
§72.3
Definitions.
§72.4
Communications.
§72.5
Interpretations.
§72.6
License required; types of licenses.
§72.7
Specific exemptions.
§72.8
Denial of licensing by Agreement States.
§72.9
Information collection requirements: OMB approval.
§72.10
Employee protection.
§72.11
Completeness and accuracy of information.
§72.12
Deliberate misconduct.
§72.13
Applicability.
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Subpart B--LICENSE APPLICATION, FORM, AND CONTENTS

§72.16
Filing of application for specific license.
§72.18
Elimination of repetition.
§72.20
Public inspection of application.
§72.22
Contents of application: General and financial information.
§72.24
Contents of application: Technical information.
§72.26
Contents of application: Technical specifications.
§72.28
Contents of application: Applicant's technical qualifications.
§72.30
Financial assurance and recordkeeping for decommissioning.
§72.32
Emergency Plan.
§72.34
Environmental report.
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Subpart C--ISSUANCE AND CONDITIONS OF LICENSE

§72.40
Issuance of license.
§72.42
Duration of license; renewal.
§72.44
License conditions.
§72.46
Public hearings.
§72.48
Changes, tests, and experiments.
§72.50
Transfer of license.
§72.52
Creditor regulations.
§72.54
Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas.
§72.56
Application for amendment of license.
§72.58
Issuance of amendment.
§72.60
Modification, revocation, and suspension of license.
§72.62
Backfitting.
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Subpart D--RECORDS, REPORTS, INSPECTIONS, AND ENFORCEMENT

§72.70
Safety analysis report updating.
§72.72
Material balance, inventory, and records requirements for stored materials.
§72.74
Reports of accidental criticality or loss of special nuclear material.
§72.75
Reporting requirements for specific events and conditions.
§72.76
Material status reports.
§72.78
Nuclear material transaction reports.
§72.79
Facility information and verification.
§72.80
Other records and reports.
§72.82
Inspections and tests.
§72.84
Violations.
§72.86
Criminal penalties.
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Subpart E--SITING EVALUATION FACTORS

§72.90
General considerations.
§72.92
Design basis external natural events.
§72.94
Design basis external man-induced events.
§72.96
Siting limitations.
§72.98
Identifying regions around an ISFSI or MRS site.
§72.100
Defining potential effects of the ISFSI or MRS on the region.
§72.102
Geological and seismological characteristics for applications before October 16, 2003 and applications for other than dry cask modes of storage.
§72.103
Geological and seismological characteristics for applications for dry cask modes of storage on or after October 16, 2003.
§72.104
Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.
§72.106
Controlled area of an ISFSI or MRS.
§72.108
Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation.
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Subpart F--GENERAL DESIGN CRITERIA

§72.120
General considerations.
§72.122
Overall requirements.
§72.124
Criteria for nuclear criticality safety.
§72.126
Criteria for radiological protection.
§72.128
Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste, and other radioactive waste storage and handling.
§72.130
Criteria for decommissioning.
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Subpart G--QUALITY ASSURANCE

§72.140
Quality assurance requirements.
§72.142
Quality assurance organization.
§72.144
Quality assurance program.
§72.146
Design control.
§72.148
Procurement document control.
§72.150
Instructions, procedures, and drawings.
§72.152
Document control.
§72.154
Control of purchased material, equipment, and services.
§72.156
Identification and control of materials, parts, and components.
§72.158
Control of special processes.
§72.160
Licensee and certificate holder inspection.
§72.162
Test control.
§72.164
Control of measuring and test equipment.
§72.166
Handling, storage, and shipping control.
§72.168
Inspection, test, and operating status.
§72.170
Nonconforming materials, parts, or components.
§72.172
Corrective action.
§72.174
Quality assurance records.
§72.176
Audits.
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Subpart H--PHYSICAL PROTECTION

§72.180
Physical protection plan.
§72.182
Design for physical protection.
§72.184
Safeguards contingency plan.
§72.186
Change to physical security and safeguards contingency plans.
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Subpart I--TRAINING AND CERTIFICATION OF PERSONNEL

§72.190
Operator requirements.
§72.192
Operator training and certification program.
§72.194
Physical requirements.
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Subpart J--PROVISION OF MRS INFORMATION TO STATE GOVERNMENTS AND INDIAN TRIBES

§72.200
Provision of MRS information.
§72.202
Participation in license reviews.
§72.204
Notice to States.
§72.206
Representation.
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Subpart K--GENERAL LICENSE FOR STORAGE OF SPENT FUEL AT POWER REACTOR SITES

§72.210
General license issued.
§72.212
Conditions of general license issued under 72.210.
§72.214
List of approved spent fuel storage casks.
§72.216
[Reserved]
§72.218
Termination of licenses.
§72.220
Violations.
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Subpart L--APPROVAL OF SPENT FUEL STORAGE CASKS

§72.230
Procedures for spent fuel storage cask submittals.
§72.232
Inspection and tests.
§72.234
Conditions of approval.
§72.236
Specific requirements for spent fuel storage cask approval and fabrication.
§72.238
Issuance of an NRC Certificate of Compliance.
§72.240
Conditions for spent fuel storage cask reapproval.
§72.242
Recordkeeping and reports.
§72.244
Application for amendment of a certificate of compliance.
§72.246
Issuance of amendment to a certificate of compliance.
§72.248
Safety analysis report updating.
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