10 CFR 52.98, Finality of Combined Licenses; Information Requests

Finality of combined licenses; information requests (a)After issuance of a combined license, the Commission may not modify, add, or delete any term or condition of the combined license, the design of the facility, the inspections, tests, analyses, and acceptance criteria contained in the license which are not derived from a referenced standard design certification or manufacturing license, except in accordance with the provisions of § 52.103 or § 50.109 of this chapter, as applicable.

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(b) If the combined license does not reference a design certification or a reactor manufactured under a subpart F of this part manufacturing license, then a licensee may make changes in the facility as described in the final safety analysis report (as updated), make changes in the procedures as described in the final safety analysis report (as updated), and conduct tests or experiments not described in the final safety analysis report (as updated) under the applicable change processes in 10 CFR part 50 (e.g., §§ 50.54, 50.59, or 50.90 of this chapter).

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(c) If the combined license references a certified design, then-

(1) Changes to or departures from information within the scope of the referenced design certification rule are subject to the applicable change processes in that rule; and

(2) Changes that are not within the scope of the referenced design certification rule are subject to the applicable change processes in 10 CFR part 50, unless they also involve changes to or noncompliance with information within the scope of the referenced design certification rule. In these cases, the applicable provisions of this section and the design certification rule apply.

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(d) If the combined license references a reactor manufactured under a subpart F of this part manufacturing license, then-

(1) Changes to or departures from information within the scope of the manufactured reactor's design are subject to the change processes in § 52.171; and

(2) Changes that are not within the scope of the manufactured reactor's design are subject to the applicable change processes in 10 CFR part 50.

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(e) The Commission may issue and make immediately effective any amendment to a combined license upon a determination by the Commission that the amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. The amendment may be issued and made immediately effective in advance of the holding and completion of any required hearing. The amendment will be processed in accordance with the procedures specified in 10 CFR 50.91.

f

(f) Any modification to, addition to, or deletion from the terms and conditions of a combined license, including any modification to, addition to, or deletion from the inspections, tests, analyses, or related acceptance criteria contained in the license is a proposed amendment to the license. There must be an opportunity for a hearing on the amendment.

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(g) Except for information sought to verify licensee compliance with the current licensing basis for that facility, information requests to the holder of a combined license must be evaluated before issuance to ensure that the burden to be imposed on the licensee is justified in view of the potential safety significance of the issue to be addressed in the requested information. Each evaluation performed by the NRC staff must be in accordance with 10 CFR 50.54(f) and must be approved by the Executive Director for Operations or his or her designee before issuance of the request.

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NRC website 10 CFR 52.98

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 52.98, Finality of Combined Licenses; Information Requests

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