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Home Page > Executive Branch > Code of Federal Regulations > Electronic Code of Federal Regulations
e-CFR Data is current as of November 19, 2009
TITLE 10--Energy
CHAPTER I--NUCLEAR REGULATORY COMMISSION
PART 52--LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS
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| Scope; applicability of 10 CFR Chapter I provisions. |
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| Completeness and accuracy of information. |
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| Combining licenses; elimination of repetition. |
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| Attacks and destructive acts. |
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| Information collection requirements: OMB approval. |
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Subpart A--EARLY SITE PERMITS
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| Relationship to other subparts. |
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| Contents of applications; general information. |
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| Contents of applications; technical information. |
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| Standards for review of applications. |
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| Administrative review of applications; hearings. |
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| Referral to the Advisory Committee on Reactor Safeguards (ACRS). |
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| Issuance of early site permit. |
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| Extent of activities permitted. |
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| Limited work authorization after issuance of early site permit. |
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| Transfer of early site permit. |
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| Use of site for other purposes. |
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| Finality of early site permit determinations. |
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Subpart B--STANDARD DESIGN CERTIFICATIONS
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| Relationship to other subparts. |
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| Contents of applications; general information. |
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| Contents of applications; technical information. |
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| Standards for review of applications. |
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| Administrative review of applications. |
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| Referral to the Advisory Committee on Reactor Safeguards (ACRS). |
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| Issuance of standard design certification. |
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| Duration of certification. |
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| Finality of standard design certifications. |
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Subpart C--COMBINED LICENSES
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| Relationship to other subparts. |
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| Contents of applications; general information. |
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| Contents of applications; technical information in final safety analysis report. |
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| Contents of applications; additional technical information. |
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| Standards for review of applications. |
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| Finality of referenced NRC approvals; partial initial decision on site suitability. |
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| Administrative review of applications; hearings. |
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| Referral to the Advisory Committee on Reactor Safeguards (ACRS). |
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| Authorization to conduct limited work authorization activities. |
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| Exemptions and variances. |
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| Issuance of combined licenses. |
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| Finality of combined licenses; information requests. |
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| Inspection during construction. |
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| Operation under a combined license. |
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| Duration of combined license. |
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| Transfer of combined license. |
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| Continuation of combined license. |
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Subpart D--[RESERVED]
Subpart E--STANDARD DESIGN APPROVALS
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| Relationship to other subparts. |
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| Contents of applications; general information. |
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| Contents of applications; technical information. |
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| Standards for review of applications. |
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| Referral to the Advisory Committee on Reactor Safeguards (ACRS). |
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| Staff approval of design. |
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| Finality of standard design approvals; information requests. |
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| Duration of design approval. |
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Subpart F--MANUFACTURING LICENSES
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| Relationship to other subparts. |
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| Contents of applications; general information. |
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| Contents of applications; technical information in final safety analysis report. |
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| Contents of application; additional technical information. |
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| Standards for review of application. |
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| Administrative review of applications; hearings. |
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| Referral to the Advisory Committee on Reactor Safeguards (ACRS). |
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| Issuance of manufacturing license. |
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| Finality of manufacturing licenses; information requests. |
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| Duration of manufacturing license. |
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| Transfer of manufacturing license. |
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Subpart G--[RESERVED]
Subpart H--ENFORCEMENT
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| Appendix N to Part 52
--Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites |
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