10 CFR 52.109, Continuation of Combined License

Continuation of combined license Each combined license for a facility that has permanently ceased operations, continues in effect beyond the expiration date to authorize ownership and possession of the production or utilization facility, until the Commission notifies the licensee in writing that the license is terminated. During this period of continued effectiveness the licensee shall-
(1) Take actions necessary to decommission and decontaminate the facility and continue to maintain the facility, including, where applicable, the storage, control and maintenance of the spent fuel, in a safe condition; and
(2) Conduct activities in accordance with all other restrictions applicable to the facility in accordance with the NRC's regulations and the provisions of the combined license for the facility.

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NRC website 10 CFR 52.109

v t e Code of Federal Regulations
Title 10 Part 52 - LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS
10 CFR: 1 2 4 5 7 9 10 11 12 13 14 15 16 19 20 21 25 26 30 31 32 33 34 35 36 37 39 40 50 51 52 54 55 60 61 62 63 70 71 72 73 74 75 76 81 95 100 140 150 160 170 171
0, General Provisions, Scope; applicability of 10 CFR Chapter I provisions 1, Definitions 2, 3, Written communications 4, Deliberate misconduct 5, Employee protection 6, Completeness and accuracy of information 7, Specific exemptions 8, Combining licenses; elimination of repetition 9, Jurisdictional limits 10, Attacks and destructive acts 11, Information collection requirements: OMB approval 12, Early Site Permits, Scope of subpart 13, Relationship to other subparts 15, Filing of applications 16, Contents of applications; general information 17, Contents of applications; technical information 18, Standards for review of applications 21, Administrative review of applications; hearings 23, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 24, Issuance of early site permit 25, Extent of activities permitted 26, Duration of permit 27, Limited work authorization after issuance of early site permit 28, Transfer of early site permit 29, Application for renewal 31, Criteria for renewal 33, Duration of renewal 35, Use of site for other purposes 39, Finality of early site permit determinations 41, Standard Design Certifications, Scope of subpart 43, Relationship to other subparts 45, Filing of applications 46, Contents of applications; general information 47, Contents of applications; technical information 48, Standards for review of applications 51, Administrative review of applications 53, Referral to the Advisory Committeeon Reactor Safeguards (ACRS) 54, Issuance of standard design certification 55, Duration of certification 57, Application for renewal 59, Criteria for renewal 61, Duration of renewal 63, Finality of standard design certifications 71, Combined Licenses, Scope of subpart 73, Relationship to other subparts 75, Filing of applications 77, Contents of applications; general information 79, Contents of applications; technical information in final safety analysis report 80, Contents of applications; additional technical information 81, Standards for review of applications 83, Finality of referenced NRC approvals; partial initial decision on site suitability 85, Administrative review of applications; hearings 87, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 89, 91, Authorization to conduct limited work authorization activities 93, Exemptions and variances 97, Issuance of combined licenses 98, Finality of combined licenses; information requests 99, Inspection during construction 103, Operation under a combined license 104, Duration of combined license 105, Transfer of combined license 107, Application for renewal 109, Continuation of combined license 110, Termination of license 131, Standard Design Approvals, Scope of subpart 133, Relationship to other subparts 135, Filing of applications 136, Contents of applications; general information 137, Contents of applications; technical information 139, Standards for review of applications 141, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 143, Staff approval of design 145, Finality of standard design approvals; information requests 147, Duration of design approval 151, Manufacturing Licenses, Scope of subpart 153, Relationship to other subparts 155, Filing of applications 156, Contents of applications; general information 157, Contents of applications; technical information in final safety analysis report 158, Contents of application; additional technical information 159, Standards for review of application 161, Reserved 163, Administrative review of applications; hearings 165, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 167, Issuance of manufacturing license 169, 171, Finality of manufacturing licenses; information requests 173, Duration of manufacturing license 175, Transfer of manufacturing license 177, Application for renewal 179, Criteria for renewal 181, Duration of renewal 301, Enforcement, Violations 303, Criminal penalties Appendices: 10 CFR 52 Appendix B, Appendix B to Part 52-Design Certification Rule for the System 80+ Design 10 CFR 52 Appendix C, Appendix C to Part 52-Design Certification Rule for the Ap600 Design 10 CFR 52 Appendix D, Appendix D to Part 52-Design Certification Rule for the Ap1000 Design 10 CFR 52 Appendix E, Appendix E to Part 52-Design Certification Rule for the Esbwr Design 10 CFR 52 Appendix F, Appendices F Through M to Part 52 Reserved 10 CFR 52 Appendix N, 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

10 CFR 52.109, Continuation of Combined License

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