10 CFR 72.216, Reserved
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[[name::[Reserved]]]
Federal Register
68 FR 33617, June 5, 2003
]
External Links
NRC website 10 CFR 72.216
v
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Code of Federal Regulations
Title 10
Part 72
- LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR- RELATED GREATER THAN CLASS C WASTE
10 CFR
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1, General Provisions, Purpose
2, Scope
3, Definitions
4, Communications
5, Interpretations
6, License required; types of licenses
7, Specific exemptions
8, Denial of licensing by Agreement States
9, Information collection requirements: OMB approval
10, Employee protection
11, Completeness and accuracy of information
12, Deliberate misconduct
13, Applicability
16, License Application, Form, and Contents, Filing of application for specific license
18, Elimination of repetition
20, Public inspection of application
22, Contents of application: General and financial information
24, Contents of application: Technical information
26, Contents of application: Technical specifications
28, Contents of application: Applicant's technical qualifications
30, Financial assurance and recordkeeping for decommissioning
32, Emergency Plan
34, Environmental report
40, Issuance and Conditions of License, Issuance of license
42, Duration of license; renewal
44, License conditions
46, Public hearings
48, Changes, tests, and experiments
50, Transfer of license
52, Creditor regulations
54, Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas
56, Application for amendment of license
58, Issuance of amendment
60, Modification, revocation, and suspension of license
62, Backfitting
70, Records, Reports, Inspections, and Enforcement, Safety analysis report updating
72, Material balance, inventory, and records requirements for stored materials
74, Reports of accidental criticality or loss of special nuclear material
75, Reporting requirements for specific events and conditions
76, Material status reports
78, Nuclear material transaction reports
79, §72.79 Facility information and
verification.
80, Other records and reports
82, Inspections and tests
84, Violations
86, Criminal penalties
90, Siting Evaluation Factors, General considerations
92, Design basis external natural events
94, Design basis external man-induced events
96, Siting limitations
98, Identifying regions around an ISFSI or MRS site
100, Defining potential effects of the ISFSI or MRS on the region
102, Geological and seismological characteristics for applications before October 16, 2003 and applications for other than dry cask modes of storage
103, Geological and seismological characteristics for applications for dry cask modes of storage on or after October 16, 2003
104, Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS
106, Controlled area of an ISFSI or MRS
108, Spent fuel or high-level radioactive waste transportation
120, General Design Criteria, General considerations
122, Overall requirements
124, Criteria for nuclear criticality safety
126, Criteria for radiological protection
128, Criteria for spent fuel, high-level radioactive waste, and other radioactive waste storage and handling
130, Criteria for decommissioning
140, Quality Assurance, Quality assurance requirements
142, Quality assurance organization
144, Quality assurance program
146, Design control
148, Procurement document control
150, Instructions, procedures, and drawings
152, Document control
154, Control of purchased material, equipment, and services
156, Identification and control of materials, parts, and components
158, Control of special processes
160, Licensee inspection
162, Test control
164, Control of measuring and test equipment
166, Handling, storage, and shipping control
168, Inspection, test, and operating status
170, Nonconforming materials, parts, or components
172, Corrective action
174, Quality assurance records
176, Audits
180, Physical Protection, Physical protection plan
182, Design for physical protection
184, Safeguards contingency plan
186, Change to physical security and safeguards contingency plans
190, Training and Certification of Personnel, Operator requirements
192, Operator training and certification program
194, Physical requirements
200, Provision of MRS Information to State Governments and Indian Tribes, Provision of MRS information
202, Participation in license reviews
204, Notice to States
206, Representation
210, General License for Storage of Spent Fuel at Power Reactor Sites, General license issued
212, Conditions of general license issued under § 72.210
214, List of approved spent fuel storage casks
216,
218, Termination of licenses
220, Violations
230, Approval of Spent Fuel Storage Casks, Procedures for spent fuel storage cask submittals
further results
Appendices:
Category
:
10 CFR 72
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