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

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

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.

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.

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.

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 transfer reports.

�72.80

Other records and reports.

�72.82

Inspections and tests.

�72.84

Violations.

�72.86

Criminal penalties.

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.

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.

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.

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.

Subpart I--TRAINING AND CERTIFICATION OF PERSONNEL

�72.190

Operator requirements.

�72.192

Operator training and certification program.

�72.194

Physical requirements.

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.

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.

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.