cfr_sections
Data license: Public Domain (U.S. Government data) · Data source: Federal Register API & Regulations.gov API
89 rows where part_number = 50 and title_number = 10 sorted by section_id
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| section_id ▼ | title_number | title_name | chapter | subchapter | part_number | part_name | subpart | subpart_name | section_number | section_heading | agency | authority | source_citation | amendment_citations | full_text |
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| 10:10:1.0.1.1.30.0.103.1 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.1 Basis, purpose, and procedures applicable. | NRC | [63 FR 1897, Jan. 13, 1998] | The regulations in this part are promulgated by the Nuclear Regulatory Commission pursuant to the Atomic Energy Act of 1954, as amended (68 Stat. 919), and Title II of the Energy Reorganization Act of 1974 (88 Stat. 1242), to provide for the licensing of production and utilization facilities. This part also gives notice to all persons who knowingly provide to any licensee, applicant, contractor, or subcontractor, components, equipment, materials, or other goods or services, that relate to a licensee's or applicant's activities subject to this part, that they may be individually subject to NRC enforcement action for violation of § 50.5. | ||||||
| 10:10:1.0.1.1.30.0.103.2 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.2 Definitions. | NRC | [21 FR 355, Jan. 19, 1956] | As used in this part, Act means the Atomic Energy Act of 1954 (68 Stat. 919) including any amendments thereto. Alternate ac source means an alternating current (ac) power source that is available to and located at or nearby a nuclear power plant and meets the following requirements: (1) Is connectable to but not normally connected to the offsite or onsite emergency ac power systems; (2) Has minimum potential for common mode failure with offsite power or the onsite emergency ac power sources; (3) Is available in a timely manner after the onset of station blackout; and (4) Has sufficient capacity and reliability for operation of all systems required for coping with station blackout and for the time required to bring and maintain the plant in safe shutdown (non-design basis accident). Applicant means a person or an entity applying for a license, permit, or other form of Commission permission or approval under this part or part 52 of this chapter. Atomic energy means all forms of energy released in the course of nuclear fission or nuclear transformation. Atomic weapon means any device utilizing atomic energy, exclusive of the means for transporting or propelling the device (where such means is a separable and divisible part of the device), the prinicipal purpose of which is for use as, or for development of, a weapon, a weapon prototype, or a weapon test device. Basic component means, for the purposes of § 50.55(e) of this chapter: (1) When applied to nuclear power reactors, any plant structure, system, component, or part thereof necessary to assure (i) The integrity of the reactor coolant pressure boundary, (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition, or (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in § 50.34(a)(1), § 50.67(b)(2), or § 100.11 of this chapter, as applicable. (2) When applied to other types of facilities or portions of such fa… | ||||||
| 10:10:1.0.1.1.30.0.103.3 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.3 Interpretations. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 90 FR 55630, Dec. 3, 2025] | Except as specifically authorized by the Commission in writing, no interpretation of the meaning of the regulations in this part by any officer or employee of the Commission other than a written interpretation by the General Counsel will be recognized to be binding upon the Commission. This section shall cease to have effect on January 8, 2027, unless the NRC determines that the cessation deadline should be extended to a date not more than 5 years in the future after offering the public an opportunity to provide input on the costs and benefits of this section and considering that input. The NRC will publish a document in the Federal Register announcing its determination and revising or removing this section accordingly. | ||||||
| 10:10:1.0.1.1.30.0.103.4 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.4 Written communications. | NRC | [68 FR 58808, Oct. 10, 2003, as amended at 74 FR 62682, Dec. 1, 2009; 80 FR 74979, Dec. 1, 2015; 88 FR 57878, Aug. 24, 2023] | (a) General requirements. All correspondence, reports, applications, and other written communications from the applicant or licensee to the Nuclear Regulatory Commission concerning the regulations in this part or individual license conditions must be sent either by mail addressed: ATTN: Document Control Desk, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; by hand delivery to the NRC's offices at 11555 Rockville Pike, Rockville, Maryland 20852-2738, between the hours of 8:15 a.m. and 4 p.m. eastern time; or, where practicable, by electronic submission, for example, via Electronic Information Exchange, e-mail, or CD-ROM. Electronic submissions must be made in a manner that enables the NRC to receive, read, authenticate, distribute, and archive the submission, and process and retrieve it a single page at a time. Detailed guidance on making electronic submissions can be obtained by visiting the NRC's Web site at http://www.nrc.gov/site-help/e-submittals.html; by e-mail to MSHD.Resource@nrc.gov; or by writing the Office of the Chief Information Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. The guidance discusses, among other topics, the formats the NRC can accept, the use of electronic signatures, and the treatment of nonpublic information. If the communication is on paper, the signed original must be sent. If a submission due date falls on a Saturday, Sunday, or Federal holiday, the next Federal working day becomes the official due date. (b) Distribution requirements. Copies of all correspondence, reports, and other written communications concerning the regulations in this part or individual license conditions must be submitted to the persons listed below (addresses for the NRC Regional Offices are listed in appendix D to part 20 of this chapter). (1) Applications for amendment of permits and licenses; reports; and other communications. All written communications (including responses to: generic letters, bulletins, information notices, regulatory information summa… | ||||||
| 10:10:1.0.1.1.30.0.103.5 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.5 Deliberate misconduct. | NRC | [63 FR 1897, Jan. 13, 1998] | (a) Any licensee, applicant for a license, employee of a licensee or applicant; or any contractor (including a supplier or consultant), subcontractor, employee of a contractor or subcontractor of any licensee or applicant for a license, who knowingly provides to any licensee, applicant, contractor, or subcontractor, any components, equipment, materials, or other goods or services that relate to a licensee's or applicant's activities in this part, may not: (1) Engage in deliberate misconduct that causes or would have caused, if not detected, a licensee or applicant to be in violation of any rule, regulation, or order; or any term, condition, or limitation of any license issued by the Commission; or (2) Deliberately submit to the NRC, a licensee, an applicant, or a licensee's or applicant's contractor or subcontractor, information that the person submitting the information knows to be incomplete or inaccurate in some respect material to the NRC. (b) A person who violates paragraph (a)(1) or (a)(2) of this section may be subject to enforcement action in accordance with the procedures in 10 CFR part 2, subpart B. (c) For the purposes of paragraph (a)(1) of this section, deliberate misconduct by a person means an intentional act or omission that the person knows: (1) Would cause a licensee or applicant to be in violation of any rule, regulation, or order; or any term, condition, or limitation, of any license issued by the Commission; or (2) Constitutes a violation of a requirement, procedure, instruction, contract, purchase order, or policy of a licensee, applicant, contractor, or subcontractor. | ||||||
| 10:10:1.0.1.1.30.0.103.6 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.7 Employee protection. | NRC | [58 FR 52410, Oct. 8, 1993, as amended at 60 FR 24551, May 9, 1995; 61 FR 6765, Feb. 22, 1996; 68 FR 58809, Oct. 10, 2003; 72 FR 63974, Nov. 14, 2007; 73 FR 30458, May 28, 2008; 79 FR 66603, Nov. 10, 2014; 83 FR 58465, Nov. 20, 2018] | (a) Discrimination by a Commission licensee, an applicant for a Commission license, or a contractor or subcontractor of a Commission licensee or applicant against an employee for engaging in certain protected activities is prohibited. Discrimination includes discharge and other actions that relate to compensation, terms, conditions, or privileges of employment. The protected activities are established in section 211 of the Energy Reorganization Act of 1974, as amended, and in general are related to the administration or enforcement of a requirement imposed under the Atomic Energy Act or the Energy Reorganization Act. (1) The protected activities include but are not limited to: (i) Providing the Commission or his or her employer information about alleged violations of either of the statutes named in paragraph (a) introductory text of this section or possible violations of requirements imposed under either of those statutes; (ii) Refusing to engage in any practice made unlawful under either of the statutes named in paragraph (a) introductory text or under these requirements if the employee has identified the alleged illegality to the employer; (iii) Requesting the Commission to institute action against his or her employer for the administration or enforcement of these requirements; (iv) Testifying in any Commission proceeding, or before Congress, or at any Federal or State proceeding regarding any provision (or proposed provision) of either of the statutes named in paragraph (a) introductory text. (v) Assisting or participating in, or is about to assist or participate in, these activities. (2) These activities are protected even if no formal proceeding is actually initiated as a result of the employee assistance or participation. (3) This section has no application to any employee alleging discrimination prohibited by this section who, acting without direction from his or her employer (or the employer's agent), deliberately causes a violation of any requirement of the Energy Reorganization Act of 1974, as a… | ||||||
| 10:10:1.0.1.1.30.0.103.7 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.8 Information collection requirements: OMB approval. | NRC | [49 FR 19627, May 9, 1984, as amended at 58 FR 68731, Dec. 29, 1993; 60 FR 65468, Dec. 19, 1995; 61 FR 65172, Dec. 11, 1996; 62 FR 52187, Oct. 6, 1997; 67 FR 67099, Nov. 4, 2002; 68 FR 19727, Apr. 22, 2003; 69 FR 68046, Nov. 22, 2004; 70 FR 61887, Oct. 27, 2005; 73 FR 78605, Dec. 23, 2008; 74 FR 28145, June 12, 2009; 75 FR 22, Jan. 4, 2010; 77 FR 39907, July 6, 2012; 83 FR 58465, Nov. 20, 2018; 84 FR 39718, Aug. 9, 2019; 85 FR 65662, Oct. 16, 2020; 88 FR 80074, Nov. 16, 2023; 89 FR 106250, Dec. 30, 2024] | (a) The Nuclear Regulatory Commission has submitted the information collection requirements contained in this part to the Office of Management and Budget (OMB) for approval as required by the Paperwork Reduction Act (44 U.S.C. 3501 et seq. ). The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. OMB has approved the information collection requirements contained in this part under control number 3150-0011. (b) The approved information collection requirements contained in this part appear in §§ 50.12, 50.30, 50.33, 50.34, 50.34a, 50.35, 50.36, 50.36a, 50.36b, 50.44, 50.46, 50.47, 50.48, 50.49, 50.54, 50.55, 50.55a, 50.59, 50.60, 50.61, 50.61a, 50.62, 50.63, 50.64, 50.65, 50.66, 50.68, 50.69, 50.70, 50.71, 50.72, 50.74, 50.75, 50.80, 50.82, 50.90, 50.91, 50.120, 50.135, 50.150, 50.155, 50.160, and appendices A, B, E, G, H, I, J, K, M, N,O, Q, R, and S to this part. (c) This part contains information collection requirements in addition to those approved under the control number specified in paragraph (a) of this section. These information collection requirements and the control numbers under which they are approved are as follows: (1) In § 50.73, NRC Form 366 is approved under control number 3150-0104. (2) In § 50.78, IAEA Design Information Questionnaire forms are approved under control number 3150-0056. (3) In § 50.78, DOC/NRC Forms AP-1, AP-A, and associated forms are approved under control numbers 0694-0135. | ||||||
| 10:10:1.0.1.1.30.0.103.8 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.9 Completeness and accuracy of information. | NRC | [52 FR 49372, Dec. 31, 1987] | (a) Information provided to the Commission by an applicant for a license or by a licensee or information required by statute or by the Commission's regulations, orders, or license conditions to be maintained by the applicant or the licensee shall be complete and accurate in all material respects. (b) Each applicant or licensee shall notify the Commission of information identified by the applicant or licensee as having for the regulated activity a significant implication for public health and safety or common defense and security. An applicant or licensee violates this paragraph only if the applicant or licensee fails to notify the Commission of information that the applicant or licensee has identified as having a significant implication for public health and safety or common defense and security. Notification shall be provided to the Administrator of the appropriate Regional Office within two working days of identifying the information. This requirement is not applicable to information which is already required to be provided to the Commission by other reporting or updating requirements. | ||||||
| 10:10:1.0.1.1.30.0.104.10 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.11 Exceptions and exemptions from licensing requirements. | NRC | [40 FR 8788, Mar. 3, 1975, as amended at 65 FR 54950, Sept. 12, 2000] | Nothing in this part shall be deemed to require a license for: (a) The manufacture, production, or acquisition by the Department of Defense of any utilization facility authorized pursuant to section 91 of the Act, or the use of such facility by the Department of Defense or by a person under contract with and for the account of the Department of Defense; (b) Except to the extent that Administration facilities of the types subject to licensing pursuant to section 202 of the Energy Reorganization Act of 1974 are involved; (1)(i) The processing, fabrication or refining of special nuclear material or the separation of special nuclear material, or the separation of special nuclear material from other substances by a prime contractor of the Department under a prime contract for: (A) The performance of work for the Department at a United States government-owned or controlled site; (B) Research in, or development, manufacture, storage, testing or transportation of, atomic weapons or components thereof; or (C) The use or operation of a production or utilization facility in a United States owned vehicle or vessel; or (ii) By a prime contractor or subcontractor of the Commission or the Department under a prime contract or subcontract when the Commission determines that the exemption of the prime contractor or subcontractor is authorized by law; and that, under the terms of the contract or subcontract, there is adequate assurance that the work thereunder can be accomplished without undue risk to the public health and safety; (2)(i) The construction or operation of a production or utilization facility for the Department at a United States government-owned or controlled site, including the transportation of the production or utilization facility to or from such site and the performance of contract services during temporary interruptions of such transportation; or the construction or operation of a production or utilization facility for the Department in the performance of research in, or development, manufacture, storag… | ||||||
| 10:10:1.0.1.1.30.0.104.11 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.12 Specific exemptions. | NRC | [37 FR 5748, Mar. 21, 1972, as amended at 40 FR 8789, Mar. 3, 1975; 50 FR 50777, Dec. 12, 1985] | (a) The Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of the regulations of this part, which are— (1) Authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. (2) The Commission will not consider granting an exemption unless special circumstances are present. Special circumstances are present whenever— (i) Application of the regulation in the particular circumstances conflicts with other rules or requirements of the Commission; or (ii) Application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule; or (iii) Compliance would result in undue hardship or other costs that are significantly in excess of those contemplated when the regulation was adopted, or that are significantly in excess of those incurred by others similarly situated; or (iv) The exemption would result in benefit to the public health and safety that compensates for any decrease in safety that may result from the grant of the exemption; or (v) The exemption would provide only temporary relief from the applicable regulation and the licensee or applicant has made good faith efforts to comply with the regulation; or (vi) There is present any other material circumstance not considered when the regulation was adopted for which it would be in the public interest to grant an exemption. If such condition is relied on exclusively for satisfying paragraph (a)(2) of this section, the exemption may not be granted until the Executive Director for Operations has consulted with the Commission. (b) Any person may request an exemption permitting the conduct of activities prior to the issuance of a construction permit prohibited by § 50.10. The Commission may grant such an exemption upon considering and balancing the following factors: (1) Whether conduct of the proposed activities wil… | ||||||
| 10:10:1.0.1.1.30.0.104.12 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.13 Attacks and destructive acts by enemies of the United States; and defense activities. | NRC | [32 FR 13445, Sept. 26, 1967] | An applicant for a license to construct and operate a production or utilization facility, or for an amendment to such license, is not required to provide for design features or other measures for the specific purpose of protection against the effects of (a) attacks and destructive acts, including sabotage, directed against the facility by an enemy of the United States, whether a foreign government or other person, or (b) use or deployment of weapons incident to U.S. defense activities. | ||||||
| 10:10:1.0.1.1.30.0.104.9 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.10 License required; limited work authorization. | NRC | [72 FR 57441, Oct. 9, 2007; 84 FR 65644, Nov. 29, 2019; 88 FR 80074, Nov. 16, 2023; 89 FR 57719, July 16, 2024] | (a) Definitions. As used in this section, construction means the activities in paragraph (a)(1) of this section, and does not mean the activities in paragraph (a)(2) of this section. (1) Activities constituting construction are the driving of piles, subsurface preparation, placement of backfill, concrete, or permanent retaining walls within an excavation, installation of foundations, or in-place assembly, erection, fabrication, or testing, which are for: (i) Safety-related structures, systems, or components (SSCs) of a facility, as defined in 10 CFR 50.2; (ii) SSCs relied upon to mitigate accidents or transients or used in plant emergency operating procedures; (iii) SSCs whose failure could prevent safety-related SSCs from fulfilling their safety-related function; (iv) SSCs whose failure could cause a reactor scram or actuation of a safety-related system; (v) SSCs necessary to comply with 10 CFR part 73; (vi) SSCs necessary to comply with 10 CFR 50.48 and criterion 3 of 10 CFR part 50, appendix A; and (vii) Onsite emergency facilities necessary to comply with either § 50.160 or § 50.47 and appendix E to this part, as applicable. (2) Construction does not include: (i) Changes for temporary use of the land for public recreational purposes; (ii) Site exploration, including necessary borings to determine foundation conditions or other preconstruction monitoring to establish background information related to the suitability of the site, the environmental impacts of construction or operation, or the protection of environmental values; (iii) Preparation of a site for construction of a facility, including clearing of the site, grading, installation of drainage, erosion and other environmental mitigation measures, and construction of temporary roads and borrow areas; (iv) Erection of fences and other access control measures; (v) Excavation; (vi) Erection of support buildings (such as, construction equipment storage sheds, warehouse and shop facilities, utilities, concrete mixing plants, docking and unlo… | ||||||
| 10:10:1.0.1.1.30.0.105.13 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.20 Two classes of licenses. | NRC | Licenses will be issued to named persons applying to the Commission therefor, and will be either class 104 or class 103. | |||||||
| 10:10:1.0.1.1.30.0.105.14 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.21 Class 104 licenses; for medical therapy and research and development facilities. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 31 FR 15145, Dec. 2, 1966; 35 FR 19659, Dec. 29, 1970; 38 FR 11446, May 8, 1973; 43 FR 6924, Feb. 17, 1978] | A class 104 license will be issued, to an applicant who qualifies, for any one or more of the following: to transfer or receive in interstate commerce, manufacture, produce, transfer, acquire, possess, or use. (a) A utilization facility for use in medical therapy; or (b)(1) A production or utilization facility the construction or operation of which was licensed pursuant to subsection 104b of the Act prior to December 19, 1970; (2) A production or utilization facility for industrial or commercial purposes constructed or operated under an arrangement with the Administration entered into under the Cooperative Power Reactor Demonstration Program, except as otherwise specifically required by applicable law; and (3) A production or utilization facility for industrial or commercial purposes, when specifically authorized by law. (c) A production or utilization facility, which is useful in the conduct of research and development activities of the types specified in section 31 of the Act, and which is not a facility of the type specified in paragraph (b) of this section or in § 50.22. | ||||||
| 10:10:1.0.1.1.30.0.105.15 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.22 Class 103 licenses; for commercial and industrial facilities. | NRC | [38 FR 11446, May 8, 1973, as amended at 43 FR 6924, Feb. 17, 1978] | A class 103 license will be issued, to an applicant who qualifies, for any one or more of the following: To transfer or receive in interstate commerce, manufacture, produce, transfer, acquire, possess, or use a production or utilization facility for industrial or commercial purposes; Provided, however, That in the case of a production or utilization facility which is useful in the conduct of research and development activities of the types specified in section 31 of the Act, such facility is deemed to be for industrial or commercial purposes if the facility is to be used so that more than 50 percent of the annual cost of owning and operating the facility is devoted to the production of materials, products, or energy for sale or commercial distribution, or to the sale of services, other than research and development or education or training. | ||||||
| 10:10:1.0.1.1.30.0.105.16 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.23 Construction permits. | NRC | [72 FR 49490, Aug. 28, 2007, as amended at 81 FR 86909, Dec. 2, 2016] | A construction permit for the construction of a production or utilization facility will be issued before the issuance of a license if the application is otherwise acceptable, and will be converted upon completion of the facility and Commission action, into a license as provided in § 50.56. However, if a combined license for a nuclear power reactor is issued under part 52 of this chapter, the construction permit and operating license are deemed to be combined in a single license. A construction permit for the alteration of a production or utilization facility will be issued before the issuance of an amendment of a license, if the application for amendment is otherwise acceptable, as provided in § 50.92. | ||||||
| 10:10:1.0.1.1.30.0.106.17 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.30 Filing of application; oath or affirmation. | NRC | [23 FR 3115, May 10, 1958, as amended at 33 FR 10924, Aug. 1, 1968; 34 FR 6307, Apr. 3, 1969; 35 FR 19660, Dec. 29, 1970; 37 FR 5749, Mar. 21, 1972; 51 FR 40307, Nov. 6, 1986; 64 FR 48951, Sept. 9, 1999; 68 FR 58809, Oct. 10, 2003; 72 FR 49490, Aug. 28, 2007; 73 FR 5721, Jan. 31, 2008; 84 FR 65644, Nov. 29, 2019; 89 FR 57719, July 16, 2024] | (a) Serving of applications. (1) Each filing of an application for a standard design approval or license to construct and/or operate, or manufacture, a production or utilization facility (including an early site permit, combined license, and manufacturing license under part 52 of this chapter), and any amendments to the applications, must be submitted to the U.S. Nuclear Regulatory Commission in accordance with § 50.4 or § 52.3 of this chapter, as applicable. (2) The applicant shall maintain the capability to generate additional copies of the general information and the safety analysis report, or part thereof or amendment thereto, for subsequent distribution in accordance with the written instructions of the Director, Office of Nuclear Reactor Regulation, or Director, Office of Nuclear Material Safety and Safeguards, as appropriate. (3) Each applicant for a construction permit under this part, or an early site permit, combined license, or manufacturing license under part 52 of this chapter, shall, upon notification by the Atomic Safety and Licensing Board appointed to conduct the public hearing required by the Atomic Energy Act, update the application and serve the updated copies of the application or parts of it, eliminating all superseded information, together with an index of the updated application, as directed by the Atomic Safety and Licensing Board. Any subsequent amendment to the application must be served on those served copies of the application and must be submitted to the U.S. Nuclear Regulatory Commission as specified in § 50.4 or § 52.3 of this chapter, as applicable. (4) The applicant must make a copy of the updated application available at the public hearing for the use of any other parties to the proceeding, and shall certify that the updated copies of the application contain the current contents of the application submitted in accordance with the requirements of this part. (5) At the time of filing an application, the Commission will make available at the NRC Web site, http://www.nrc.gov … | ||||||
| 10:10:1.0.1.1.30.0.106.18 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.31 Combining applications. | NRC | An applicant may combine in one his several applications for different kinds of licenses under the regulations in this chapter. | |||||||
| 10:10:1.0.1.1.30.0.106.19 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.32 Elimination of repetition. | NRC | In his application, the applicant may incorporate by reference information contained in previous applications, statements or reports filed with the Commission: Provided, That such references are clear and specific. | |||||||
| 10:10:1.0.1.1.30.0.106.20 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.33 Contents of applications; general information. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 35 FR 19660, Dec. 29, 1970; 38 FR 3956, Feb. 9, 1973; 45 FR 55408, Aug. 19, 1980; 49 FR 35752, Sept. 12, 1984; 53 FR 24049, June 27, 1988; 69 FR 4448, Jan. 30, 2004; 72 FR 49490, Aug. 28, 2007; 88 FR 80074, Nov. 16, 2023; 89 FR 57719, July 16, 2024; 89 FR 106250, Dec. 30, 2024] | Each application shall state: (a) Name of applicant; (b) Address of applicant; (c) Description of business or occupation of applicant; (d)(1) If applicant is an individual, state citizenship. (2) If applicant is a partnership, state name, citizenship and address of each partner and the principal location where the partnership does business. (3) If applicant is a corporation or an unincorporated association, state: (i) The state where it is incorporated or organized and the principal location where it does business; (ii) The names, addresses and citizenship of its directors and of its principal officers; (iii) Whether it is owned, controlled, or dominated by an alien, a foreign corporation, or foreign government, and if so, give details. (4) If the applicant is acting as agent or representative of another person in filing the application, identify the principal and furnish information required under this paragraph with respect to such principal. (e) The class of license applied for, the use to which the facility will be put, the period of time for which the license is sought, and a list of other licenses, except operator's licenses, issued or applied for in connection with the proposed facility. (f) Except for an electric utility applicant for a license to operate a utilization facility of the type described in § 50.21(b) or § 50.22, information sufficient to demonstrate to the Commission the financial qualification of the applicant to carry out, in accordance with regulations in this chapter, the activities for which the permit or license is sought. As applicable, the following should be provided: (1) If the application is for a construction permit, the applicant shall submit information that demonstrates that the applicant possesses or has reasonable assurance of obtaining the funds necessary to cover estimated construction costs and related fuel cycle costs. The applicant shall submit estimates of the total construction costs of the facility and related fuel cycle costs, and shall indicate the sour… | ||||||
| 10:10:1.0.1.1.30.0.106.21 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.34 Contents of applications; technical information. | NRC | [33 FR 18612, Dec. 17, 1968] | (a) Preliminary safety analysis report. Each application for a construction permit shall include a preliminary safety analysis report. The minimum information 1 to be included shall consist of the following: 1 The applicant may provide information required by this paragraph in the form of a discussion, with specific references, of similarities to and differences from, facilities of similar design for which applications have previously been filed with the Commission. (1) Stationary power reactor applicants for a construction permit who apply on or after January 10, 1997, shall comply with paragraph (a)(1)(ii) of this section. All other applicants for a construction permit shall comply with paragraph (a)(1)(i) of this section. (i) A description and safety assessment of the site on which the facility is to be located, with appropriate attention to features affecting facility design. Special attention should be directed to the site evaluation factors identified in part 100 of this chapter. The assessment must contain an analysis and evaluation of the major structures, systems and components of the facility which bear significantly on the acceptability of the site under the site evaluation factors identified in part 100 of this chapter, assuming that the facility will be operated at the ultimate power level which is contemplated by the applicant. For non-power production or utilization facilities not subject to 10 CFR part 100, the assessment must provide an evaluation of the applicable radiological consequences that demonstrates with reasonable assurance that any individual located in the unrestricted area following the onset of a postulated accident, including consideration of experiments, would not receive a radiation dose in excess of 1 rem (0.01 Sv) 2 TEDE for the duration of the accident. With respect to operation at the projected initial power level, the applicant is required to submit information prescribed in paragraphs (a)(2) through (a)(8) of this section, as well as the information requir… | ||||||
| 10:10:1.0.1.1.30.0.106.22 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.34a Design objectives for equipment to control releases of radioactive material in effluents—nuclear power reactors. | NRC | [72 FR 49492, Aug. 28, 2007] | (a) An application for a construction permit shall include a description of the preliminary design of equipment to be installed to maintain control over radioactive materials in gaseous and liquid effluents produced during normal reactor operations, including expected operational occurrences. In the case of an application filed on or after January 2, 1971, the application shall also identify the design objectives, and the means to be employed, for keeping levels of radioactive material in effluents to unrestricted areas as low as is reasonably achievable. The term “as low as is reasonably achievable” as used in this part means as low as is reasonably achievable taking into account the state of technology, and the economics of improvements in relation to benefits to the public health and safety and other societal and socioeconomic considerations, and in relation to the use of atomic energy in the public interest. The guides set out in appendix I to this part provide numerical guidance on design objectives for light-water-cooled nuclear power reactors to meet the requirements that radioactive material in effluents released to unrestricted areas be kept as low as is reasonably achievable. These numerical guides for design objectives and limiting conditions for operation are not to be construed as radiation protection standards. (b) Each application for a construction permit shall include: (1) A description of the preliminary design of equipment to be installed under paragraph (a) of this section; (2) An estimate of: (i) The quantity of each of the principal radionuclides expected to be released annually to unrestricted areas in liquid effluents produced during normal reactor operations; and (ii) The quantity of each of the principal radionuclides of the gases, halides, and particulates expected to be released annually to unrestricted areas in gaseous effluents produced during normal reactor operations. (3) A general description of the provisions for packaging, storage, and shipment offsite of solid waste conta… | ||||||
| 10:10:1.0.1.1.30.0.106.23 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.35 Issuance of construction permits. | NRC | [27 FR 12915, Dec. 29, 1962, as amended at 31 FR 12780, Sept. 30, 1966; 35 FR 5318, Mar. 31, 1970; 35 FR 6644, Apr. 25, 1970; 35 FR 11461, July 7, 1970] | 1 The Commission may issue a provisional construction permit pursuant to the regulations in this part in effect on March 30, 1970, for any facility for which a notice of hearing on an application for a provisional construction permit has been published on or before that date. (a) When an applicant has not supplied initially all of the technical information required to complete the application and support the issuance of a construction permit which approves all proposed design features, the Commission may issue a construction permit if the Commission finds that (1) the applicant has described the proposed design of the facility, including, but not limited to, the principal architectural and engineering criteria for the design, and has identified the major features or components incorporated therein for the protection of the health and safety of the public; (2) such further technical or design information as may be required to complete the safety analysis, and which can reasonably be left for later consideration, will be supplied in the final safety analysis report; (3) safety features or components, if any, which require research and development have been described by the applicant and the applicant has identified, and there will be conducted, a research and development program reasonably designed to resolve any safety questions associated with such features or components; and that (4) on the basis of the foregoing, there is reasonable assurance that, (i) such safety questions will be satisfactorily resolved at or before the latest date stated in the application for completion of construction of the proposed facility, and (ii) taking into consideration the site criteria contained in part 100 of this chapter, the proposed facility can be constructed and operated at the proposed location without undue risk to the health and safety of the public. When an applicant has supplied initially all of the technical information required to complete the application, including the final design of the facility, the findings r… | ||||||
| 10:10:1.0.1.1.30.0.106.24 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.36 Technical specifications. | NRC | [33 FR 18612, Dec. 17, 1968, as amended at 48 FR 33860, July 26, 1983; 51 FR 40308, Nov. 6, 1986; 53 FR 19249, May 27, 1988; 60 FR 36959, July 19, 1995; 61 FR 39299, July 29, 1996; 72 FR 49493, Aug. 28, 2007; 73 FR 54932, Sept. 24, 2008; 84 FR 63568, Nov. 18, 2019; 89 FR 106251, Dec. 30, 2024] | (a)(1) Each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications. (2) Each applicant for a design certification or manufacturing license under part 52 of this chapter shall include in its application proposed generic technical specifications in accordance with the requirements of this section for the portion of the plant that is within the scope of the design certification or manufacturing license application. (b) Each license authorizing operation of a production or utilization facility of a type described in § 50.21 or § 50.22 will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34. The Commission may include such additional technical specifications as the Commission finds appropriate. (c) Technical specifications will include items in the following categories: (1) Safety limits, limiting safety system settings, and limiting control settings. (i)(A) Safety limits for nuclear reactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. If any safety limit is exceeded, the reactor must be shut down. The licensee shall notify the Commission, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. Operation must not be resumed until authorized by the Commission. The licensee shall retain the record of the results of each review until the Co… | ||||||
| 10:10:1.0.1.1.30.0.106.25 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.36a Technical specifications on effluents from nuclear power reactors. | NRC | [61 FR 39299, July 29, 1996, as amended at 72 FR 49493, Aug. 28, 2007] | (a) To keep releases of radioactive materials to unrestricted areas during normal conditions, including expected occurrences, as low as is reasonably achievable, each licensee of a nuclear power reactor and each applicant for a design certification or a manufacturing license will include technical specifications that, in addition to requiring compliance with applicable provisions of § 20.1301 of this chapter, require that: (1) Operating procedures developed pursuant to § 50.34a(c) for the control of effluents be established and followed and that the radioactive waste system, pursuant to § 50.34a, be maintained and used. The licensee shall retain the operating procedures in effect as a record until the Commission terminates the license and shall retain each superseded revision of the procedures for 3 years from the date it was superseded. (2) Each holder of an operating license, and each holder of a combined license after the Commission has made the finding under § 52.103(g) of this chapter, shall submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months, including any other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from effluent releases. The report must be submitted as specified in § 50.4, and the time between submission of the reports must be no longer than 12 months. If quantities of radioactive materials released during the reporting period are significantly above design objectives, the report must cover this specifically. On the basis of these reports and any additional information the Commission may obtain from the licensee or others, the Commission may require the licensee to take action as the Commission deems appropriate. (b) In establishing and implementing the operating procedures described in paragraph (a) of this section, the licensee shall be guided by the following co… | ||||||
| 10:10:1.0.1.1.30.0.106.26 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.36b Environmental conditions. | NRC | [72 FR 49493, Aug. 28, 2007, as amended at 89 FR 57719, July 16, 2024] | (a) Each construction permit under this part, each early site permit under part 52 of this chapter, and each combined license under part 52 of this chapter may include conditions to protect the environment during construction. These conditions are to be set out in an attachment to the permit or license, which is incorporated in and made a part of the permit or license. These conditions will be derived from information contained in the environmental report submitted pursuant to § 51.50 of this chapter as analyzed and evaluated in the NRC record of decision, and will identify the obligations of the licensee in the environmental area, including, as appropriate, requirements for reporting and keeping records of environmental data, and any conditions and monitoring requirement for the protection of the nonaquatic environment. (b) Each license authorizing operation of a production or utilization facility, including a combined license under part 52 of this chapter, and each license for a nuclear power reactor facility that no longer authorizes operation of the reactor under § 50.82(a)(1) or § 52.110(a) of this chapter has been submitted, which is of a type described in § 50.21(b)(2) or (3) or § 50.22 or is a testing facility, may include conditions to protect the environment during operation and decommissioning. These conditions are to be set out in an attachment to the license, which is incorporated in and made a part of the license. These conditions will be derived from information contained in the environmental report or the supplement to the environmental report submitted pursuant to §§ 51.50 and 51.53 of this chapter as analyzed and evaluated in the NRC record of decision, and will identify the obligations of the licensee in the environmental area, including, as appropriate, requirements for reporting and keeping records of environmental data, and any conditions and monitoring requirement for the protection of the nonaquatic environment. | ||||||
| 10:10:1.0.1.1.30.0.106.27 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.37 Agreement limiting access to Classified Information. | NRC | [89 FR 57719, July 16, 2024] | As part of its application and in any event before the receipt of Restricted Data or classified National Security Information or the issuance of a license, construction permit, early site permit, or standard design approval, or before the Commission has adopted a final standard design certification rule under part 52 of this chapter, the applicant shall agree in writing that it will not permit any individual to have access to, or any facility to possess, Restricted Data or classified National Security Information until the individual and/or facility has been approved for access under the provisions of 10 CFR parts 25 and/or 95. The agreement of the applicant becomes part of the license, or construction permit, or standard design approval. | ||||||
| 10:10:1.0.1.1.30.0.106.28 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.38 Ineligibility of certain applicants. | NRC | [21 FR 355, Jan. 16, 1956, as amended at 43 FR 6924, Feb. 17, 1978] | Any person who is a citizen, national, or agent of a foreign country, or any corporation, or other entity which the Commission knows or has reason to believe is owned, controlled, or dominated by an alien, a foreign corporation, or a foreign government, shall be ineligible to apply for and obtain a license. | ||||||
| 10:10:1.0.1.1.30.0.106.29 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.39 Public inspection of applications. | NRC | Applications and documents submitted to the Commission in connection with applications may be made available for public inspection in accordance with the provisions of the regulations contained in part 2 of this chapter. | |||||||
| 10:10:1.0.1.1.30.0.107.30 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.40 Common standards. | NRC | [72 FR 49493, Aug. 28, 2007] | In determining that a construction permit or operating license in this part, or early site permit, combined license, or manufacturing license in part 52 of this chapter will be issued to an applicant, the Commission will be guided by the following considerations: (a) Except for an early site permit or manufacturing license, the processes to be performed, the operating procedures, the facility and equipment, the use of the facility, and other technical specifications, or the proposals, in regard to any of the foregoing collectively provide reasonable assurance that the applicant will comply with the regulations in this chapter, including the regulations in part 20 of this chapter, and that the health and safety of the public will not be endangered. (b) The applicant for a construction permit, operating license, combined license, or manufacturing license is technically and financially qualified to engage in the proposed activities in accordance with the regulations in this chapter. However, no consideration of financial qualification is necessary for an electric utility applicant for an operating license for a utilization facility of the type described in § 50.21(b) or § 50.22 or for an applicant for a manufacturing license. (c) The issuance of a construction permit, operating license, early site permit, combined license, or manufacturing license to the applicant will not, in the opinion of the Commission, be inimical to the common defense and security or to the health and safety of the public. (d) Any applicable requirements of subpart A of 10 CFR part 51 have been satisfied. | ||||||
| 10:10:1.0.1.1.30.0.107.31 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.41 Additional standards for class 104 licenses. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 35 FR 19660, Dec. 29, 1970; 73 FR 44620, July 31, 2008] | In determining that a class 104 license will be issued to an applicant, the Commission will, in addition to applying the standards set forth in § 50.40 be guided by the following considerations: (a) The Commission will permit the widest amount of effective medical therapy possible with the amount of special nuclear material available for such purposes. (b) The Commission will permit the conduct of widespread and diverse research and development. (c) [Reserved] | ||||||
| 10:10:1.0.1.1.30.0.107.32 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.42 Additional standard for class 103 licenses. | NRC | [73 FR 44620, July 31, 2008] | In determining whether a class 103 license will be issued to an applicant, the Commission will, in addition to applying the standards set forth in § 50.40, consider whether the proposed activities will serve a useful purpose proportionate to the quantities of special nuclear material or source material to be utilized. | ||||||
| 10:10:1.0.1.1.30.0.107.33 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.43 Additional standards and provisions affecting class 103 licenses and certifications for commercial power. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 35 FR 19660, Dec. 29, 1970; 63 FR 50480, Sept. 22, 1998; 72 FR 49494, Aug. 28, 2007; 82 FR 52825, Nov. 15, 2017; 89 FR 57719, July 16, 2024] | In addition to applying the standards set forth in §§ 50.40 and 50.42, paragraphs (a) through (e) of this section apply in the case of a class 103 license for a facility for the generation of commercial power. For a design certification under part 52 of this chapter, only paragraph (e) of this section applies. (a) The NRC will: (1) Give notice in writing of each application to the regulatory agency or State as may have jurisdiction over the rates and services incident to the proposed activity; (2) Publish notice of the application in trade or news publications as it deems appropriate to give reasonable notice to municipalities, private utilities, public bodies, and cooperatives which might have a potential interest in the utilization or production facility; and (3) Publish notice of the application once each week for 4 consecutive weeks in the Federal Register. No license will be issued by the NRC prior to the giving of these notices and until 4 weeks after the last notice is published in the Federal Register. (b) If there are conflicting applications for a limited opportunity for such license, the Commission will give preferred consideration in the following order: First, to applications submitted by public or cooperative bodies for facilities to be located in high cost power areas in the United States; second, to applications submitted by others for facilities to be located in such areas; third, to applications submitted by public or cooperative bodies for facilities to be located in other than high cost power areas; and, fourth, to all other applicants. (c) The licensee who transmits electric energy in interstate commerce, or sells it at wholesale in interstate commerce, shall be subject to the regulatory provisions of the Federal Power Act. (d) Nothing shall preclude any government agency, now or hereafter authorized by law to engage in the production, marketing, or distribution of electric energy, if otherwise qualified, from obtaining a construction permit or operating license under this part, or … | ||||||
| 10:10:1.0.1.1.30.0.107.34 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.44 Combustible gas control for nuclear power reactors. | NRC | [68 FR 54141, Sept. 16, 2003] | (a) Definitions —(1) Inerted atmosphere means a containment atmosphere with less than 4 percent oxygen by volume. (2) Mixed atmosphere means that the concentration of combustible gases in any part of the containment is below a level that supports combustion or detonation that could cause loss of containment integrity. (b) Requirements for currently-licensed reactors. Each boiling or pressurized water nuclear power reactor with an operating license on October 16, 2003, except for those facilities for which the certifications required under § 50.82(a)(1) have been submitted, must comply with the following requirements, as applicable: (1) Mixed atmosphere. All containments must have a capability for ensuring a mixed atmosphere. (2) Combustible gas control. (i) All boiling water reactors with Mark I or Mark II type containments must have an inerted atmosphere. (ii) All boiling water reactors with Mark III type containments and all pressurized water reactors with ice condenser containments must have the capability for controlling combustible gas generated from a metal-water reaction involving 75 percent of the fuel cladding surrounding the active fuel region (excluding the cladding surrounding the plenum volume) so that there is no loss of containment structural integrity. (3) Equipment survivability. All boiling water reactors with Mark III containments and all pressurized water reactors with ice condenser containments that do not rely upon an inerted atmosphere inside containment to control combustible gases must be able to establish and maintain safe shutdown and containment structural integrity with systems and components capable of performing their functions during and after exposure to the environmental conditions created by the burning of hydrogen. Environmental conditions caused by local detonations of hydrogen must also be included, unless such detonations can be shown unlikely to occur. The amount of hydrogen to be considered must be equivalent to that generated from a metal-water reaction… | ||||||
| 10:10:1.0.1.1.30.0.107.35 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.45 Standards for construction permits, operating licenses, and combined licenses. | NRC | [72 FR 49494, Aug. 28, 2007] | (a) An applicant for an operating license or an amendment of an operating license who proposes to construct or alter a production or utilization facility will be initially granted a construction permit if the application is in conformity with and acceptable under the criteria of §§ 50.31 through 50.38, and the standards of §§ 50.40 through 50.43, as applicable. (b) A holder of a combined license who proposes, after the Commission makes the finding under § 52.103(g) of this chapter, to alter the licensed facility will be initially granted a construction permit if the application is in conformity with and acceptable under the criteria of §§ 50.30 through 50.33, § 50.34(f), §§ 50.34a through 50.38, the standards of §§ 50.40 through 50.43, as applicable, and §§ 52.79 and 52.80 of this chapter. | ||||||
| 10:10:1.0.1.1.30.0.107.36 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.46 Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors. | NRC | [39 FR 1002, Jan. 4, 1974, as amended at 53 FR 36004, Sept. 16, 1988; 57 FR 39358, Aug. 31, 1992; 61 FR 39299, July 29, 1996; 62 FR 59276, Nov. 3, 1997; 72 FR 49494, Aug. 28, 2007] | (a)(1)(i) Each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding must be provided with an emergency core cooling system (ECCS) that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents conforms to the criteria set forth in paragraph (b) of this section. ECCS cooling performance must be calculated in accordance with an acceptable evaluation model and must be calculated for a number of postulated loss-of-coolant accidents of different sizes, locations, and other properties sufficient to provide assurance that the most severe postulated loss-of-coolant accidents are calculated. Except as provided in paragraph (a)(1)(ii) of this section, the evaluation model must include sufficient supporting justification to show that the analytical technique realistically describes the behavior of the reactor system during a loss-of-coolant accident. Comparisons to applicable experimental data must be made and uncertainties in the analysis method and inputs must be identified and assessed so that the uncertainty in the calculated results can be estimated. This uncertainty must be accounted for, so that, when the calculated ECCS cooling performance is compared to the criteria set forth in paragraph (b) of this section, there is a high level of probability that the criteria would not be exceeded. Appendix K, Part II Required Documentation, sets forth the documentation requirements for each evaluation model. This section does not apply to a nuclear power reactor facility for which the certifications required under § 50.82(a)(1) have been submitted. (ii) Alternatively, an ECCS evaluation model may be developed in conformance with the required and acceptable features of appendix K ECCS Evaluation Models. (2) The Director of Nuclear Reactor Regulation may impose restrictions on reactor operation if it is found that the evaluations of ECCS cooling performance submitted are not consistent with parag… | ||||||
| 10:10:1.0.1.1.30.0.107.37 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.46a Acceptance criteria for reactor coolant system venting systems. | NRC | [68 FR 54142, Sept. 16, 2003] | Each nuclear power reactor must be provided with high point vents for the reactor coolant system, for the reactor vessel head, and for other systems required to maintain adequate core cooling if the accumulation of noncondensible gases would cause the loss of function of these systems. High point vents are not required for the tubes in U-tube steam generators. Acceptable venting systems must meet the following criteria: (a) The high point vents must be remotely operated from the control room. (b) The design of the vents and associated controls, instruments and power sources must conform to appendix A and appendix B of this part. (c) The vent system must be designed to ensure that: (1) The vents will perform their safety functions; and (2) There would not be inadvertent or irreversible actuation of a vent. | ||||||
| 10:10:1.0.1.1.30.0.107.38 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.47 Emergency plans. | NRC | [45 FR 55409, Aug. 8, 1980, as amended at 47 FR 30235, July 13, 1982; 47 FR 40537, Sept. 15, 1982; 49 FR 27736, July 6, 1984; 50 FR 19324, May 8, 1985; 52 FR 42085, Nov. 3, 1987; 53 FR 36959, Sept. 23, 1988; 56 FR 64976, Dec. 13, 1991; 61 FR 30132, June 14, 1996; 66 FR 5440, Jan. 19, 2001; 72 FR 49495, Aug. 28, 2007; 76 FR 72595, Nov. 23, 2011; 78 FR 34248, June 7, 2013; 88 FR 80075, Nov. 16, 2023] | (a)(1)(i) Except as provided in paragraph (d) of this section, no initial operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. No finding under this section is necessary for issuance of a renewed nuclear power reactor operating license. (ii) No initial combined license under part 52 of this chapter will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. No finding under this section is necessary for issuance of a renewed combined license. (iii) If an application for an early site permit under subpart A of part 52 of this chapter includes complete and integrated emergency plans under 10 CFR 52.17(b)(2)(ii), no early site permit will be issued unless a finding is made by the NRC that the emergency plans provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. (iv) If an application for an early site permit proposes major features of the emergency plans under 10 CFR 52.17(b)(2)(i), no early site permit will be issued unless a finding is made by the NRC that the major features are acceptable in accordance with the applicable standards of either this section and appendix E to this part, or the applicable requirements of § 50.160, within the scope of emergency preparedness matters addressed in the major features. (2) The NRC will base its finding on a review of the Federal Emergency Management Agency (FEMA) findings and determinations as to whether State and local emergency plans are adequate and whether there is reasonable assurance that they can be implemented, and on the NRC assessment as to whether the applicant's onsite emergency plans are adequate and whether there is reasonable assurance that they can be implemented. A FEMA finding will pri… | ||||||
| 10:10:1.0.1.1.30.0.107.39 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.48 Fire protection. | NRC | [65 FR 38190, June 20, 2000, as amended at 69 FR 33550, June 16, 2004; 72 FR 49495, Aug. 28, 2007] | (a)(1) Each holder of an operating license issued under this part or a combined license issued under part 52 of this chapter must have a fire protection plan that satisfies Criterion 3 of appendix A to this part. This fire protection plan must: (i) Describe the overall fire protection program for the facility; (ii) Identify the various positions within the licensee's organization that are responsible for the program; (iii) State the authorities that are delegated to each of these positions to implement those responsibilities; and (iv) Outline the plans for fire protection, fire detection and suppression capability, and limitation of fire damage. (2) The plan must also describe specific features necessary to implement the program described in paragraph (a)(1) of this section such as— (i) Administrative controls and personnel requirements for fire prevention and manual fire suppression activities; (ii) Automatic and manually operated fire detection and suppression systems; and (iii) The means to limit fire damage to structures, systems, or components important to safety so that the capability to shut down the plant safely is ensured. (3) The licensee shall retain the fire protection plan and each change to the plan as a record until the Commission terminates the reactor license. The licensee shall retain each superseded revision of the procedures for 3 years from the date it was superseded. (4) Each applicant for a design approval, design certification, or manufacturing license under part 52 of this chapter must have a description and analysis of the fire protection design features for the standard plant necessary to demonstrate compliance with Criterion 3 of appendix A to this part. (b) Appendix R to this part establishes fire protection features required to satisfy Criterion 3 of appendix A to this part with respect to certain generic issues for nuclear power plants licensed to operate before January 1, 1979. (1) Except for the requirements of Sections III.G, III.J, and III.O, the provisions of Append… | ||||||
| 10:10:1.0.1.1.30.0.107.40 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.49 Environmental qualification of electric equipment important to safety for nuclear power plants. | NRC | [48 FR 2733, Jan. 21, 1983, as amended at 49 FR 45576, Nov. 19, 1984; 51 FR 40308, Nov. 6, 1986; 51 FR 43709, Dec. 3, 1986; 52 FR 31611, Aug. 21, 1987; 53 FR 19250, May 27, 1988; 61 FR 39300, July 29, 1996; 61 FR 65173, Dec. 11, 1996; 62 FR 47271, Sept. 8, 1997; 64 FR 72001, Dec. 23, 1999; 66 FR 64738, Dec. 14, 2001; 72 FR 49495, Aug. 28, 2007; 80 FR 45843, Aug. 3, 2015] | (a) Each holder of or an applicant for an operating license issued under this part, or a combined license or manufacturing license issued under part 52 of this chapter, other than a nuclear power plant for which the certifications required under § 50.82(a)(1) or § 52.110(a)(1) of this chapter have been submitted, shall establish a program for qualifying the electric equipment defined in paragraph (b) of this section. For a manufacturing license, only electric equipment defined in paragraph (b) which is within the scope of the manufactured reactor must be included in the program. (b) Electric equipment important to safety covered by this section is: (1) Safety-related electric equipment. 3 3 Safety-related electric equipment is referred to as “Class 1E” equipment in IEEE 323-1974. Copies of this standard may be obtained from the Institute of Electrical and Electronics Engineers, Inc., 345 East 47th Street, New York, NY 10017. (i) This equipment is that relied upon to remain functional during and following design basis events to ensure— (A) The integrity of the reactor coolant pressure boundary; (B) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (C) The capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guidelines in § 50.34(a)(1), § 50.67(b)(2), or § 100.11 of this chapter, as applicable. (ii) Design basis events are defined as conditions of normal operation, including anticipated operational occurrences, design basis accidents, external events, and natural phenomena for which the plant must be designed to ensure functions (b)(1)(i) (A) through (C) of this section. (2) Nonsafety-related electric equipment whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions specified in subparagraphs (b)(1)(i)(A) through (C) of this section by the safety-related equipment. (3) Certain post-accident monitoring equipment. 4 4 Specif… | ||||||
| 10:10:1.0.1.1.30.0.108.41 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.50 Issuance of licenses and construction permits. | NRC | Upon determination that an application for a license meets the standards and requirements of the act and regulations, and that notifications, if any, to other agencies or bodies have been duly made, the Commission will issue a license, or if appropriate a construction permit, in such form and containing such conditions and limitations including technical specifications, as it deems appropriate and necessary. | |||||||
| 10:10:1.0.1.1.30.0.108.42 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.51 Continuation of license. | NRC | [56 FR 64976, Dec. 13, 1991, as amended at 61 FR 39300, July 29, 1996; 89 FR 106251, Dec. 30, 2024] | (a) Except as noted in § 50.51(c), each license will be issued for a fixed period of time to be specified in the license but in no case to exceed 40 years from date of issuance. Where the operation of a facility is involved, the Commission will issue the license for the term requested by the applicant or for the estimated useful life of the facility if the Commission determines that the estimated useful life is less than the term requested. Where construction of a facility is involved, the Commission may specify in the construction permit the period for which the license will be issued if approved pursuant to § 50.56. Licenses may be renewed by the Commission upon the expiration of the period. Renewal of operating licenses for nuclear power plants is governed by 10 CFR part 54. Application for termination of license is to be made pursuant to § 50.82. (b) Each 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 such 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 regulations and the provisions of the specific 10 CFR part 50 license for the facility. (c) Each non-power production or utilization facility license issued under § 50.21(a) or (c), other than a testing facility license, after January 29, 2025, will be issued with no fixed license term. | ||||||
| 10:10:1.0.1.1.30.0.108.43 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.52 Combining licenses. | NRC | The Commission may combine in a single license the activities of an applicant which would otherwise be licensed severally. | |||||||
| 10:10:1.0.1.1.30.0.108.44 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.53 Jurisdictional limitations. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 43 FR 6924, Feb. 17, 1978] | No license under this part shall be deemed to have been issued for activities which are not under or within the jurisdiction of the United States. | ||||||
| 10:10:1.0.1.1.30.0.108.45 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.54 Conditions of licenses. | NRC | [21 FR 355, Jan. 19, 1956] | The following paragraphs of this section, with the exception of paragraphs (r) and (gg), and the applicable requirements of 10 CFR 50.55a, are conditions in every nuclear power reactor operating license issued under this part. The following paragraphs with the exception of paragraph (r), (s), and (u) of this section are conditions in every combined license issued under part 52 of this chapter, provided, however, that paragraphs (i) introductory text, (i)(1), (j), (k), (l), (m), (n), (w), (x), (y), (z), and (hh) of this section are only applicable after the Commission makes the finding under § 52.103(g) of this chapter. (a)(1) Each nuclear power plant or fuel reprocessing plant licensee subject to the quality assurance criteria in appendix B of this part shall implement, under § 50.34(b)(6)(ii) or § 52.79 of this chapter, the quality assurance program described or referenced in the safety analysis report, including changes to that report. However, a holder of a combined license under part 52 of this chapter shall implement the quality assurance program described or referenced in the safety analysis report applicable to operation 30 days prior to the scheduled date for the initial loading of fuel. (2) Each licensee described in paragraph (a)(1) of this section shall, by June 10, 1983, submit to the appropriate NRC Regional Office shown in appendix D of part 20 of this chapter the current description of the quality assurance program it is implementing for inclusion in the Safety Analysis Report, unless there are no changes to the description previously accepted by NRC. This submittal must identify changes made to the quality assurance program description since the description was submitted to NRC. (Should a licensee need additional time beyond June 10, 1983 to submit its current quality assurance program description to NRC, it shall notify the appropriate NRC Regional Office in writing, explain why additional time is needed, and provide a schedule for NRC approval showing when its current quality assurance program… | ||||||
| 10:10:1.0.1.1.30.0.108.46 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.55 Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 32 FR 4055, Mar. 15, 1967; 35 FR 11461, July 17, 1970; 35 FR 19661, Dec. 29, 1970; 36 FR 11424, June 12, 1971; 37 FR 6460, Mar. 30, 1972; 38 FR 1272, Jan. 11, 1973; 41 FR 16446, Apr. 19, 1976; 42 FR 43385, Aug. 29, 1977; 48 FR 1029, Jan. 10, 1983; 51 FR 40309, Nov. 6, 1986; 56 FR 36091, July 31, 1991; 59 FR 14087, Mar. 25, 1994; 68 FR 58809, Oct. 10, 2003; 72 FR 49497, Aug. 28, 2007; 78 FR 34248, June 7, 2013; 79 FR 65798, Nov. 5, 2014; 88 FR 15880, Mar. 14, 2023; 89 FR 57719, July 16, 2024] | Each construction permit for a utilization facility is subject to the following terms and conditions and the applicable requirements of § 50.55a; each construction permit for a production facility is subject to the following terms and conditions with the exception of paragraph (i); each early site permit is subject to the terms and conditions in paragraph (f) of this section; each manufacturing license is subject to the terms and conditions in paragraphs (e), (f), and (i) of this section and the applicable requirements of § 50.55a; and each combined license is subject to the terms and conditions in paragraphs (e), (f), and (i) of this section and the applicable requirements of § 50.55a until the date that the Commission makes the finding under § 52.103(g) of this chapter: (a) The construction permit shall state the earliest and latest dates for completion of the construction or modification. (b) If the proposed construction or modification of the facility is not completed by the latest completion date, the construction permit shall expire and all rights are forfeited. However, upon good cause shown, the Commission will extend the completion date for a reasonable period of time. The Commission will recognize, among other things, developmental problems attributable to the experimental nature of the facility or fire, flood, explosion, strike, sabotage, domestic violence, enemy action, an act of the elements, and other acts beyond the control of the permit holder, as a basis for extending the completion date. (c) Except as modified by this section and § 50.55a, the construction permit shall be subject to the same conditions to which a license is subject. (d) At or about the time of completion of the construction or modification of the facility, the applicant will file any additional information needed to bring the original application for license up to date, and will file an application for an operating license or an amendment to an application for a license to construct and operate the facility for the issuance … | ||||||
| 10:10:1.0.1.1.30.0.108.47 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.55a Codes and standards. | NRC | [79 FR 65798, Nov. 5, 2014, as amended at 79 FR 66603, Nov. 10, 2014; 79 FR 73462, Dec. 11, 2014; 82 FR 52825, Dec. 15, 2017; 83 FR 2354, Jan. 17, 2018; 83 FR 2526, Jan. 18, 2018; 84 FR 65644, Nov. 29, 2019; 85 FR 14756, Mar. 16, 2020; 85 FR 26576, May 4, 2020; 85 FR 34088, June 3, 2020; 85 FR 65662, Oct. 16, 2020; 87 FR 11949, Mar. 3, 2022; 87 FR 65148, Oct. 27, 2022; 87 FR 73633, Dec. 1, 2022; 88 FR 57878, Aug. 24, 2023; 89 FR 58055, July 17, 2024; 89 FR 60795, July 29, 2024; 89 FR 70467, Aug. 30, 2024; 91 FR 46326, Jan. 26, 2026] | (a) Documents approved for incorporation by reference. The material listed in this paragraph (a) is incorporated by reference into this section with the approval of the Director of the Federal Register under 5 U.S.C. 552(a) and 1 CFR part 51. All approved material is available for inspection at the Nuclear Regulatory Commission (NRC) and at the National Archives and Records Administration (NARA). Contact the NRC at NRC Technical Library, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852; telephone: 301-415-7000; email: Library.Resource@nrc.gov. For information on the availability of this material at NARA, visit www.archives.gov/federal-register/cfr/ibr-locations or email fr.inspection@nara.gov. The material may be obtained from the following sources in this paragraph (a). (1) American Society of Mechanical Engineers (ASME), Three Park Avenue, New York, NY 10016; telephone: 1-800-843-2763; https://www.asme.org/Codes/. (i) ASME Boiler and Pressure Vessel Code, Section III. The editions and addenda for Section III of the ASME Boiler and Pressure Vessel Code (excluding Nonmandatory Appendices) are listed in this paragraph (a)(1)(i), but limited by those provisions identified in paragraph (b)(1) of this section. (A) “Rules for Construction of Nuclear Vessels:” ( 1 ) 1963 Edition, ( 2 ) Summer 1964 Addenda, ( 3 ) Winter 1964 Addenda, ( 4 ) 1965 Edition, ( 5 ) 1965 Summer Addenda, ( 6 ) 1965 Winter Addenda, ( 7 ) 1966 Summer Addenda, ( 8 ) 1966 Winter Addenda, ( 9 ) 1967 Summer Addenda, ( 10 ) 1967 Winter Addenda, ( 11 ) 1968 Edition, ( 12 ) 1968 Summer Addenda, ( 13 )1968 Winter Addenda, ( 14 ) 1969 Summer Addenda, ( 15 ) 1969 Winter Addenda, ( 16 ) 1970 Summer Addenda, and ( 17 ) 1970 Winter Addenda. (B) “Rules for Construction of Nuclear Power Plant Components:” ( 1 ) 1971 Edition, ( 2 ) 1971 Summer Addenda, ( 3 ) 1971 Winter Addenda, ( 4 ) 1972 Summer Addenda, ( 5 ) 1972 Winter Addenda, ( 6 ) 1973 Summer Addenda, and ( 7 ) 1973 Winter Addenda. (C) “Divi… | ||||||
| 10:10:1.0.1.1.30.0.108.48 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.56 Conversion of construction permit to license; or amendment of license. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 35 FR 11461, July 17, 1970; 75 FR 73944, Nov. 30, 2010] | Upon completion of the construction or alteration of a facility, in compliance with the terms and conditions of the construction permit and subject to any necessary testing of the facility for health or safety purposes, the Commission will, in the absence of good cause shown to the contrary, issue a license of the class for which the construction permit was issued or an appropriate amendment of the license, as the case may be. | ||||||
| 10:10:1.0.1.1.30.0.108.49 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.57 Issuance of operating license. | NRC | [35 FR 5318, Mar. 31, 1970, as amended at 35 FR 6644, Apr. 25, 1970; 37 FR 11873, June 15, 1972; 37 FR 15142, July 28, 1972; 49 FR 35753, Sept. 12, 1984; 51 FR 7765, Mar. 6, 1986; 69 FR 2275, Jan. 14, 2004] | 1 The Commission may issue a provisional operating license pursuant to the regulations in this part in effect on March 30, 1970, for any facility for which a notice of hearing on an application for a provisional operating license or a notice of proposed issuance of a provisional operating license has been published on or before that date. (a)Pursuant to § 50.56, an operating license may be issued by the Commission, up to the full term authorized by § 50.51, upon finding that: (1) Construction of the facility has been substantially completed, in conformity with the construction permit and the application as amended, the provisions of the Act, and the rules and regulations of the Commission; and (2) The facility will operate in conformity with the application as amended, the provisions of the Act, and the rules and regulations of the Commission; and (3) There is reasonable assurance (i) that the activities authorized by the operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations in this chapter; and (4) The applicant is technically and financially qualified to engage in the activities authorized by the operating license in accordance with the regulations in this chapter. However, no finding of financial qualification is necessary for an electric utility applicant for an operating license for a utilization facility of the type described in § 50.21(b) or § 50.22. (5) The applicable provisions of part 140 of this chapter have been satisfied; and (6) The issuance of the license will not be inimical to the common defense and security or to the health and safety of the public. (b) Each operating license will include appropriate provisions with respect to any uncompleted items of construction and such limitations or conditions as are required to assure that operation during the period of the completion of such items will not endanger public health and safety. (c) An applicant may, in a case wher… | ||||||
| 10:10:1.0.1.1.30.0.108.50 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.58 Hearings and report of the Advisory Committee on Reactor Safeguards. | NRC | [27 FR 12186, Dec. 8, 1962, as amended at 35 FR 11461, July 17, 1970; 39 FR 10555, Mar. 21, 1974; 51 FR 7765, Mar. 6, 1986] | (a) Each application for a construction permit or an operating license for a facility which is of a type described in § 50.21(b) or § 50.22, or for a testing facility, shall be referred to the Advisory Committee on Reactor Safeguards for a review and report. An application for an amendment to such a construction permit or operating license may be referred to the Advisory Committee on Reactor Safeguards for review and report. Any report shall be made part of the record of the application and available to the public, except to the extent that security classification prevents disclosure. (b)(1) The Commission will hold a hearing after at least 30-days' notice and publication once in the Federal Register on each application for a construction permit for a production or utilization facility which is of a type described in § 50.21(b) or § 50.22, or for a testing facility. (2) When a construction permit has been issued for such a facility following the holding of a public hearing, and an application is made for an operating license or for an amendment to a construction permit or operating license, the Commission may hold a hearing after at least 30-days' notice and publication once in the Federal Register, or, in the absence of a request therefor by any person whose interest may be affected, may issue an operating license or an amendment to a construction permit or operating license without a hearing, upon 30-days' notice and publication once in the Federal Register of its intent to do so. (3) If the Commission finds, in an emergency situation, as defined in § 50.91, that no significant hazards consideration is presented by an application for an amendment to an operating license, it may dispense with public notice and comment and may issue the amendment. If the Commission finds that exigent circumstances exist, as described in § 50.91, it may reduce the period provided for public notice and comment. (4) Both in an emergency situation and in the case of exigent circumstances, the Commission will provide 30 days… | ||||||
| 10:10:1.0.1.1.30.0.108.51 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.59 Changes, tests, and experiments. | NRC | [64 FR 53613, Oct. 4, 1999, as amended at 66 FR 64738, Dec. 14, 2001; 72 FR 49500, Aug. 28, 2007; 89 FR 57720, July 16, 2024; 89 FR 106251, Dec. 30, 2024] | (a) Definitions for the purposes of this section: (1) Change means a modification or addition to, or removal from, the facility or procedures that affects a design function, method of performing or controlling the function, or an evaluation that demonstrates that intended functions will be accomplished. (2) Departure from a method of evaluation described in the FSAR (as updated) used in establishing the design bases or in the safety analyses means: (i) Changing any of the elements of the method described in the FSAR (as updated) unless the results of the analysis are conservative or essentially the same; or (ii) Changing from a method described in the FSAR to another method unless that method has been approved by NRC for the intended application. (3) Facility as described in the final safety analysis report (as updated) means: (i) The structures, systems, and components (SSC) that are described in the final safety analysis report (FSAR) (as updated), (ii) The design and performance requirements for such SSCs described in the FSAR (as updated), and (iii) The evaluations or methods of evaluation included in the FSAR (as updated) for such SSCs which demonstrate that their intended function(s) will be accomplished. (4) Final Safety Analysis Report (as updated) means the Final Safety Analysis Report (or Final Hazards Summary Report) submitted in accordance with § 50.34, as amended and supplemented, and as updated per the requirements of § 50.71(e) or § 50.71(f), as applicable. (5) Procedures as described in the final safety analysis report (as updated) means those procedures that contain information described in the FSAR (as updated) such as how structures, systems, and components are operated and controlled (including assumed operator actions and response times). (6) Tests or experiments not described in the final safety analysis report (as updated) means any activity where any structure, system, or component is utilized or controlled in a manner which is either: (i) Outside the reference boun… | ||||||
| 10:10:1.0.1.1.30.0.108.52 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.60 Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation. | NRC | [48 FR 24009, May 27, 1983, as amended at 50 FR 50777, Dec. 12, 1985; 61 FR 39300, July 29, 1996] | (a) Except as provided in paragraph (b) of this section, all light-water nuclear power reactors, other than reactor facilities for which the certifications required under § 50.82(a)(1) have been submitted, must meet the fracture toughness and material surveillance program requirements for the reactor coolant pressure boundary set forth in appendices G and H to this part. (b) Proposed alternatives to the described requirements in Appendices G and H of this part or portions thereof may be used when an exemption is granted by the Commission under § 50.12. | ||||||
| 10:10:1.0.1.1.30.0.108.53 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.61 Fracture toughness requirements for protection against pressurized thermal shock events. | NRC | [60 FR 65468, Dec. 19, 1995, as amended at 61 FR 39300, July 29, 1996; 72 FR 49500, Aug. 28, 2007; 73 FR 5722, Jan. 31, 2008; 75 FR 23, Jan. 4, 2010; 84 FR 65644, Nov. 29, 2019] | (a) Definitions. For the purposes of this section: (1) ASME Code means the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, Division I, “Rules for the Construction of Nuclear Power Plant Components,” edition and addenda and any limitations and modifications thereof as specified in § 50.55a. (2) Pressurized Thermal Shock Event means an event or transient in pressurized water reactors (PWRs) causing severe overcooling (thermal shock) concurrent with or followed by significant pressure in the reactor vessel. (3) Reactor Vessel Beltline means the region of the reactor vessel (shell material including welds, heat affected zones and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage. (4) RT NDT means the reference temperature for a reactor vessel material, under any conditions. For the reactor vessel beltline materials, RT NDT must account for the effects of neutron radiation. (5) RT NDT(U) means the reference temperature for a reactor vessel material in the pre-service or unirradiated condition, evaluated according to the procedures in the ASME Code, Paragraph NB-2331 or other methods approved by the Director, Office of Nuclear Reactor Regulation. (6) EOL Fluence means the best-estimate neutron fluence projected for a specific vessel beltline material at the clad-base-metal interface on the inside surface of the vessel at the location where the material receives the highest fluence on the expiration date of the operating license. (7) RT PTS means the reference temperature, RT NDT , evaluated for the EOL Fluence for each of the vessel beltline materials, using the procedures of paragraph (c) of this section. (8) PTS Screening Criterion means the value of RT PTS for the vessel beltline material above which the plant ca… | ||||||
| 10:10:1.0.1.1.30.0.108.54 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.61a Alternate fracture toughness requirements for protection against pressurized thermal shock events. | NRC | [75 FR 23, Jan. 4, 2010, as amended at 75 FR 5495, Feb. 3, 2010; 75 FR 10411, Mar. 8, 2010; 75 FR 72653, Nov. 26, 2010] | (a) Definitions. Terms in this section have the same meaning as those presented in 10 CFR 50.61(a), with the exception of the term “ASME Code.” (1) ASME Code means the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, Division I, “Rules for the Construction of Nuclear Power Plant Components,” and Section XI, Division I, “Rules for Inservice Inspection of Nuclear Power Plant Components,” edition and addenda and any limitations and modifications thereof as specified in § 50.55a. (2) RT MAX-AW means the material property which characterizes the reactor vessel's resistance to fracture initiating from flaws found along axial weld fusion lines. RT MAX-AW is determined under the provisions of paragraph (f) of this section and has units of °F. (3) RT MAX-PL means the material property which characterizes the reactor vessel's resistance to fracture initiating from flaws found in plates in regions that are not associated with welds found in plates. RT MAX-PL is determined under the provisions of paragraph (f) of this section and has units of °F. (4) RT MAX-FO means the material property which characterizes the reactor vessel's resistance to fracture initiating from flaws in forgings that are not associated with welds found in forgings. RT MAX-FO is determined under the provisions of paragraph (f) of this section and has units of °F. (5) RT MAX-CW means the material property which characterizes the reactor vessel's resistance to fracture initiating from flaws found along the circumferential weld fusion lines. RT MAX-CW is determined under the provisions of paragraph (f) of this section and has units of °F. (6) RT MAX-X means any or all of the material properties RT MAX-AW , RT MAX-PL , RT MAX-FO , RT MAX-CW , or sum of RT MAX-AW and RT MAX-PL , for a particular reactor vessel. (7) φt means fast neutron fluence for neutrons with energies greater than 1.0 MeV. φt is utilized under the provisions of paragraph (g) of this section and has units of n/cm 2 . (8) φ… | ||||||
| 10:10:1.0.1.1.30.0.108.55 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.62 Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants. | NRC | [49 FR 26044, June 26, 1984; 49 FR 27736, July 6, 1984, as amended at 51 FR 40310, Nov. 6, 1986; 54 FR 13362, Apr. 3, 1989; 61 FR 39301, July 29, 1996; 72 FR 49500, Aug. 28, 2007] | (a) Applicability. The requirements of this section apply to all commercial light-water-cooled nuclear power plants, other than nuclear power reactor facilities for which the certifications required under § 50.82(a)(1) have been submitted. (b) Definition. For purposes of this section, Anticipated Transient Without Scram (ATWS) means an anticipated operational occurrence as defined in appendix A of this part followed by the failure of the reactor trip portion of the protection system specified in General Design Criterion 20 of appendix A of this part. (c) Requirements. (1) Each pressurized water reactor must have equipment from sensor output to final actuation device, that is diverse from the reactor trip system, to automatically initiate the auxiliary (or emergency) feedwater system and initiate a turbine trip under conditions indicative of an ATWS. This equipment must be designed to perform its function in a reliable manner and be independent (from sensor output to the final actuation device) from the existing reactor trip system. (2) Each pressurized water reactor manufactured by Combustion Engineering or by Babcock and Wilcox must have a diverse scram system from the sensor output to interruption of power to the control rods. This scram system must be designed to perform its function in a reliable manner and be independent from the existing reactor trip system (from sensor output to interruption of power to the control rods). (3) Each boiling water reactor must have an alternate rod injection (ARI) system that is diverse (from the reactor trip system) from sensor output to the final actuation device. The ARI system must have redundant scram air header exhaust valves. The ARI must be designed to perform its function in a reliable manner and be independent (from the existing reactor trip system) from sensor output to the final actuation device. (4) Each boiling water reactor must have a standby liquid control system (SLCS) with the capability of injecting into the reactor pressure vessel a borated w… | ||||||
| 10:10:1.0.1.1.30.0.108.56 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.63 Loss of all alternating current power. | NRC | [53 FR 23215, June 21, 1988, as amended at 63 FR 50480, Sept. 22, 1998; 72 FR 49501, Aug. 28, 2007; 86 FR 43402, Aug. 9, 2021] | (a) Requirements. (1) Each light-water-cooled nuclear power plant licensed to operate under this part, each light-water-cooled nuclear power plant licensed under subpart C of 10 CFR part 52 after the Commission makes the finding under § 52.103(g) of this chapter, and each design for a light-water-cooled nuclear power plant approved under a standard design approval, standard design certification, and manufacturing license under part 52 of this chapter must be able to withstand for a specified duration and recover from a station blackout as defined in § 50.2. The specified station blackout duration shall be based on the following factors: (i) The redundancy of the onsite emergency ac power sources; (ii) The reliability of the onsite emergency ac power sources; (iii) The expected frequency of loss of offsite power; and (iv) The probable time needed to restore offsite power. (2) The reactor core and associated coolant, control, and protection systems, including station batteries and any other necessary support systems, must provide sufficient capacity and capability to ensure that the core is cooled and appropriate containment integrity is maintained in the event of a station blackout for the specified duration. The capability for coping with a station blackout of specified duration shall be determined by an appropriate coping analysis. Licensees are expected to have the baseline assumptions, analyses, and related information used in their coping evaluations available for NRC review. (b) Limitation of scope. Paragraph (c) of this section does not apply to those plants licensed to operate prior to July 21, 1988, if the capability to withstand station blackout was specifically addressed in the operating license proceeding and was explicitly approved by the NRC. (c) Implementation —(1) Information Submittal. For each light-water-cooled nuclear power plant operating license application submitted after September 27, 2007, the applicant shall submit the information defined below in its final safety analysis… | ||||||
| 10:10:1.0.1.1.30.0.108.57 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.64 Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors. | NRC | [51 FR 6519, Feb. 25, 1986] | (a) Applicability. The requirements of this section apply to all non-power reactors. (b) Requirements. (1) The Commission will not issue a construction permit after March 27, 1986 for a non-power reactor where the applicant proposes to use highly enriched uranium (HEU) fuel, unless the applicant demonstrates that the proposed reactor will have a unique purpose as defined in § 50.2. (2) Unless the Commission has determined, based on a request submitted in accordance with paragraph (c)(1) of this section, that the non-power reactor has a unique purpose, each licensee authorized to possess and use HEU fuel in connection with the reactor's operation shall: (i) Not initiate acquisition of additional HEU fuel, if low enriched uranium (LEU) fuel acceptable to the Commission for that reactor is available when it proposes that acquisition; and (ii) Replace all HEU fuel in its possession with available LEU fuel acceptable to the Commission for that reactor, in accordance with a schedule determined pursuant to paragraph (c)(2) of this section. (3) If not required by paragraphs (b) (1) and (2) of this section to use LEU fuel, the applicant or licensee must use HEU fuel of enrichment as close to 20% as is available and acceptable to the Commisson. (c) Implementation. (1) Any request by a licensee for a determination that a non-power reactor has a unique purpose as defined in § 50.2 should be submitted with supporting documentation to the Director of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, by September 29, 1986. (2) (i) By March 27, 1987 and at 12-month intervals thereafter, each licensee of a non-power reactor authorized to possess and use HEU fuel shall develop and submit to the Director of the Office of Nuclear Reactor Regulation a written proposal for meeting the requirements of paragraph (b) (2) or (3) of this section. The licensee shall include in the proposal a certification that Federal Government funding for conversion is available through the De… | ||||||
| 10:10:1.0.1.1.30.0.108.58 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power plants. | NRC | [56 FR 31324, July 10, 1991, as amended at 58 FR 33996, June 23, 1993; 61 FR 39301, July 29, 1996; 61 FR 65173, Dec. 11, 1996; 62 FR 47271, Sept. 8, 1997; 62 FR 59276, Nov. 3, 1997; 64 FR 38557, July 19, 1999; 64 FR 72001, Dec. 23, 1999; 72 FR 49501, Aug. 28, 2007] | The requirements of this section are applicable during all conditions of plant operation, including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power plant under this part and each holder of a combined license under part 52 of this chapter after the Commission makes the finding under § 52.103(g) of this chapter, shall monitor the performance or condition of structures, systems, or components, against licensee-established goals, in a manner sufficient to provide reasonable assurance that these structures, systems, and components, as defined in paragraph (b) of this section, are capable of fulfilling their intended functions. These goals shall be established commensurate with safety and, where practical, take into account industry-wide operating experience. When the performance or condition of a structure, system, or component does not meet established goals, appropriate corrective action shall be taken. For a nuclear power plant for which the licensee has submitted the certifications specified in § 50.82(a)(1) or 52.110(a)(1) of this chapter, as applicable, this section shall only apply to the extent that the licensee shall monitor the performance or condition of all structures, systems, or components associated with the storage, control, and maintenance of spent fuel in a safe condition, in a manner sufficient to provide reasonable assurance that these structures, systems, and components are capable of fulfilling their intended functions. (2) Monitoring as specified in paragraph (a)(1) of this section is not required where it has been demonstrated that the performance or condition of a structure, system, or component is being effectively controlled through the performance of appropriate preventive maintenance, such that the structure, system, or component remains capable of performing its intended function. (3) Performance and condition monitoring activities and associated goals and preventive maintenance activities shall be evaluated at least every refueling cycle prov… | ||||||
| 10:10:1.0.1.1.30.0.108.59 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.66 Requirements for thermal annealing of the reactor pressure vessel. | NRC | [60 FR 65472, Dec. 19, 1995, as amended at 64 FR 48952, Sept. 9, 1999; 64 FR 53613, Oct. 4, 1999] | (a) For those light water nuclear power reactors where neutron radiation has reduced the fracture toughness of the reactor vessel materials, a thermal annealing may be applied to the reactor vessel to recover the fracture toughness of the material. The use of a thermal annealing treatment is subject to the requirements in this section. A report describing the licensee's plan for conducting the thermal annealing must be submitted in accordance with § 50.4 at least three years prior to the date at which the limiting fracture toughness criteria in § 50.61 or appendix G to part 50 would be exceeded. Within three years of the submittal of the Thermal Annealing Report and at least thirty days prior to the start of the thermal annealing, the NRC will review the Thermal Annealing Report and make available the results of its evaluation at the NRC Web site, http://www.nrc.gov. The licensee may begin the thermal anneal after: (1) Submitting the Thermal Annealing Report required by paragraph (b) of this section; (2) The NRC makes available the results of its evaluation of the Thermal Annealing Report at the NRC Web site, http://www.nrc.gov; and (3) The requirements of paragraph (f)(1) of this section have been satisfied. (b) Thermal Annealing Report. The Thermal Annealing Report must include: a Thermal Annealing Operating Plan; a Requalification Inspection and Test Program; a Fracture Toughness Recovery and Reembrittlement Trend Assurance Program; and an Identification of Changes Requiring a License Amendment. (1) Thermal Annealing Operating Plan. The thermal annealing operating plan must include: (i) A detailed description of the pressure vessel and all structures and components that are expected to experience significant thermal or stress effects during the thermal annealing operation; (ii) An evaluation of the effects of mechanical and thermal stresses and temperatures on the vessel, containment, biological shield, attached piping and appurtenances, and adjacent equipment and components to demonstrate that … | ||||||
| 10:10:1.0.1.1.30.0.108.60 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.67 Accident source term. | NRC | [64 FR 72001, Dec. 23, 1999] | (a) Applicability. The requirements of this section apply to all holders of operating licenses issued prior to January 10, 1997, and holders of renewed licenses under part 54 of this chapter whose initial operating license was issued prior to January 10, 1997, who seek to revise the current accident source term used in their design basis radiological analyses. (b) Requirements. (1) A licensee who seeks to revise its current accident source term in design basis radiological consequence analyses shall apply for a license amendment under § 50.90. The application shall contain an evaluation of the consequences of applicable design basis accidents 1 previously analyzed in the safety analysis report. 1 The fission product release assumed for these calculations should be based upon a major accident, hypothesized for purposes of design analyses or postulated from considerations of possible accidental events, that would result in potential hazards not exceeded by those from any accident considered credible. Such accidents have generally been assumed to result in substantial meltdown of the core with subsequent release of appreciable quantities of fission products. (2) The NRC may issue the amendment only if the applicant's analysis demonstrates with reasonable assurance that: (i) An individual located at any point on the boundary of the exclusion area for any 2-hour period following the onset of the postulated fission product release, would not receive a radiation dose in excess of 0.25 Sv (25 rem) 2 total effective dose equivalent (TEDE). 2 2 The use of 0.25 Sv (25 rem) TEDE is not intended to imply that this value constitutes an acceptable limit for emergency doses to the public under accident conditions. Rather, this 0.25 Sv (25 rem) TEDE value has been stated in this section as a reference value, which can be used in the evaluation of proposed design basis changes with respect to potential reactor accidents of exceedingly low probability of occurrence and low risk of public exposure to radiation… | ||||||
| 10:10:1.0.1.1.30.0.108.61 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.68 Criticality accident requirements. | NRC | [63 FR 63130, Nov. 12, 1998, as amended at 71 FR 66652, Nov. 16, 2006] | (a) Each holder of a construction permit or operating license for a nuclear power reactor issued under this part or a combined license for a nuclear power reactor issued under part 52 of this chapter, shall comply with either 10 CFR 70.24 of this chapter or the requirements in paragraph (b) of this section. (b) Each licensee shall comply with the following requirements in lieu of maintaining a monitoring system capable of detecting a criticality as described in 10 CFR 70.24: (1) Plant procedures shall prohibit the handling and storage at any one time of more fuel assemblies than have been determined to be safely subcritical under the most adverse moderation conditions feasible by unborated water. (2) The estimated ratio of neutron production to neutron absorption and leakage (k-effective) of the fresh fuel in the fresh fuel storage racks shall be calculated assuming the racks are loaded with fuel of the maximum fuel assembly reactivity and flooded with unborated water and must not exceed 0.95, at a 95 percent probability, 95 percent confidence level. This evaluation need not be performed if administrative controls and/or design features prevent such flooding or if fresh fuel storage racks are not used. (3) If optimum moderation of fresh fuel in the fresh fuel storage racks occurs when the racks are assumed to be loaded with fuel of the maximum fuel assembly reactivity and filled with low-density hydrogenous fluid, the k-effective corresponding to this optimum moderation must not exceed 0.98, at a 95 percent probability, 95 percent confidence level. This evaluation need not be performed if administrative controls and/or design features prevent such moderation or if fresh fuel storage racks are not used. (4) If no credit for soluble boron is taken, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. If credit is taken for soluble boron, the k-effe… | ||||||
| 10:10:1.0.1.1.30.0.108.62 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.69 Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors. | NRC | [69 FR 68047, Nov. 22, 2004] | (a) Definitions. Risk-Informed Safety Class (RISC)-1 structures, systems, and components (SSCs) means safety-related SSCs that perform safety significant functions. Risk-Informed Safety Class (RISC)-2 structures, systems and components (SSCs) means nonsafety-related SSCs that perform safety significant functions. Risk-Informed Safety Class (RISC)-3 structures, systems and components (SSCs) means safety-related SSCs that perform low safety significant functions. Risk-Informed Safety Class (RISC)-4 structures, systems and components (SSCs) means nonsafety-related SSCs that perform low safety significant functions. Safety significant function means a function whose degradation or loss could result in a significant adverse effect on defense-in-depth, safety margin, or risk. (b) Applicability and scope of risk-informed treatment of SSCs and submittal/approval process. (1) A holder of a license to operate a light water reactor (LWR) nuclear power plant under this part; a holder of a renewed LWR license under part 54 of this chapter; an applicant for a construction permit or operating license under this part; or an applicant for a design approval, a combined license, or manufacturing license under part 52 of this chapter; may voluntarily comply with the requirements in this section as an alternative to compliance with the following requirements for RISC-3 and RISC-4 SSCs: (i) 10 CFR part 21. (ii) The portion of 10 CFR 50.46a(b) that imposes requirements to conform to Appendix B to 10 CFR part 50. (iii) 10 CFR 50.49. (iv) 10 CFR 50.55(e). (v) The inservice testing requirements in 10 CFR 50.55a(f); the inservice inspection, and repair and replacement (with the exception of fracture toughness), requirements for ASME Class 2 and Class 3 SSCs in 10 CFR 50.55a(g); and the electrical component quality and qualification requirements in Section 4.3 and 4.4 of IEEE 279, and Sections 5.3 and 5.4 of IEEE 603-1991, as incorporated by reference in 10 CFR 50.55a(h). (vi) 10 CFR 50.65, except for paragraph (a)(4). … | ||||||
| 10:10:1.0.1.1.30.0.109.63 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.70 Inspections. | NRC | [21 FR 355, Jan. 19, 1956; 44 FR 47919, Aug. 16, 1979, as amended at 52 FR 31612, Aug. 21, 1987; 53 FR 42942, Oct. 25, 1988; 72 FR 49501, Aug. 28, 2007; 73 FR 5722, Jan. 31, 2008; 75 FR 73944, Nov. 30, 2010; 84 FR 65644, Nov. 29, 2019] | (a) Each applicant for or holder of a license, including a construction permit or an early site permit, shall permit inspection, by duly authorized representatives of the Commission, of his records, premises, activities, and of licensed materials in possession or use, related to the license or construction permit or early site permit as may be necessary to effectuate the purposes of the Act, as amended, including Section 105 of the Act, and the Energy Reorganization Act of 1974, as amended. (b)(1) Each licensee and each holder of a construction permit shall, upon request by the Director, Office of Nuclear Reactor Regulation, provide rent-free office space for the exclusive use of the Commission inspection personnel. Heat, air conditioning, light, electrical outlets, and janitorial services shall be furnished by each licensee and each holder of a construction permit. The office shall be convenient to and have full access to the facility and shall provide the inspector both visual and acoustic privacy. (2) For a site with a single power reactor or fuel facility licensed under part 50 or part 52 of this chapter, or a facility issued a manufacturing license under part 52, the space provided shall be adequate to accommodate a full-time inspector, a part-time secretary and transient NRC personnel and will be generally commensurate with other office facilities at the site. A space of 250 square feet either within the site's office complex or in an office trailer or other onsite space is suggested as a guide. For sites containing multiple power reactor units or fuel facilities, additional space may be requested to accommodate additional full-time inspector(s). The office space that is provided shall be subject to the approval of the Director, Office of Nuclear Reactor Regulation. All furniture, supplies and communication equipment will be furnished by the Commission. (3) The licensee or construction permit holder shall afford any NRC resident inspector assigned to that site, or other NRC inspectors identified by the R… | ||||||
| 10:10:1.0.1.1.30.0.109.64 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.71 Maintenance of records, making of reports. | NRC | [33 FR 9704, July 4, 1968, as amended at 41 FR 18303, May 3, 1976; 45 FR 30615, May 9, 1980; 51 FR 40310, Nov. 6, 1986; 53 FR 19250, May 27, 1988; 57 FR 39358, Aug. 31, 1992; 61 FR 39301, July 29, 1996; 64 FR 53614, Oct. 4, 1999; 71 FR 29246, May 22, 2006; 72 FR 49501, Aug. 28, 2007; 86 FR 43402, Aug. 9, 2021; 89 FR 106251, Dec. 30, 2024] | (a) Each licensee, including each holder of a construction permit or early site permit, shall maintain all records and make all reports, in connection with the activity, as may be required by the conditions of the license or permit or by the regulations, and orders of the Commission in effectuating the purposes of the Act, including Section 105 of the Act, and the Energy Reorganization Act of 1974, as amended. Reports must be submitted in accordance with § 50.4 or 10 CFR 52.3, as applicable. (b) With respect to any production or utilization facility of a type described in § 50.21(b) or 50.22, or a testing facility, each licensee and each holder of a construction permit shall submit its annual financial report, including the certified financial statements, to the Commission, as specified in § 50.4, upon issuance of the report. However, licensees and holders of a construction permit who submit a Form 10-Q with the Securities and Exchange Commission or a Form 1 with the Federal Energy Regulatory Commission, need not submit the annual financial report or the certified financial statement under this paragraph. (c) Records that are required by the regulations in this part or part 52 of this chapter, by license condition, or by technical specifications must be retained for the period specified by the appropriate regulation, license condition, or technical specification. If a retention period is not otherwise specified, these records must be retained until the Commission terminates the facility license or, in the case of an early site permit, until the permit expires. (d)(1) Records which must be maintained under this part or part 52 of this chapter may be the original or a reproduced copy or microform if the reproduced copy or microform is duly authenticated by authorized personnel and the microform is capable of producing a clear and legible copy after storage for the period specified by Commission regulations. The record may also be stored in electronic media with the capability of producing legible, accurate, and … | ||||||
| 10:10:1.0.1.1.30.0.109.65 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.72 Immediate notification requirements for operating nuclear power reactors. | NRC | [48 FR 39046, Aug. 29, 1983; 48 FR 40882, Sept. 12, 1983; 55 FR 29194, July 18, 1990, as amended at 56 FR 944, Jan. 10, 1991; 56 FR 23473, May 21, 1991; 56 FR 40184, Aug. 13, 1991; 57 FR 41381, Sept. 10, 1992; 58 FR 67661, Dec. 22, 1993; 59 FR 14087, Mar. 25, 1994; 65 FR 63786, Oct. 25, 2000; 72 FR 49502, Aug. 28, 2007; 85 FR 65662, Oct. 16, 2020; 87 FR 20697, Apr. 8, 2022; 88 FR 15880, Mar. 14, 2023] | (a) General requirements. 1 (1) Each nuclear power reactor licensee licensed under §§ 50.21(b) or 50.22 holding an operating license under this part or a combined license under part 52 of this chapter after the Commission makes the finding under § 52.103(g), shall notify the NRC Operations Center via the Emergency Notification System of: 1 Other requirements for immediate notification of the NRC by licensed operating nuclear power reactors are contained elsewhere in this chapter, in particular §§ 20.1906, 20.2202, 50.36, 72.74, 72.75, and 73.1200. (i) The declaration of any of the Emergency Classes specified in the licensee's approved Emergency Plan; 2 or 2 These Emergency Classes are addressed in Appendix E of this part. (ii) Those non-emergency events specified in paragraph (b) of this section that occurred within three years of the date of discovery. (2) If the Emergency Notification System is inoperative, the licensee shall make the required notifications via commercial telephone service, other dedicated telephone system, or any other method which will ensure that a report is made as soon as practical to the NRC Headquarters Operations Center at the numbers specified in appendix A to part 73 of this chapter. (3) The licensee shall notify the NRC immediately after notification of the appropriate State or local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes. (4) The licensee shall activate the Emergency Response Data System (ERDS) 3 as soon as possible but not later than one hour after declaring an Emergency Class of alert, site area emergency, or general emergency. The ERDS may also be activated by the licensee during emergency drills or exercises if the licensee's computer system has the capability to transmit the exercise data. 3 Requirements for ERDS are addressed in Appendix E, Section VI. (5) When making a report under paragraph (a)(1) of this section, the licensee shall identify: (i) The Emergency Class declared; or … | ||||||
| 10:10:1.0.1.1.30.0.109.66 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.73 Licensee event report system. | NRC | [48 FR 33858, July 26, 1983, as amended at 49 FR 47824, Dec. 7, 1984; 51 FR 40310, Nov. 6, 1986; 56 FR 23473, May 21, 1991; 56 FR 61352, Dec. 3, 1991; 57 FR 41381, Sept. 10, 1992; 58 FR 67661, Dec. 22, 1993; 59 FR 50689, Oct. 5, 1994; 63 FR 50480, Sept. 22, 1998; 65 FR 63787, Oct. 25, 2000; 69 FR 18803, Apr. 9, 2004; 72 FR 49502, Aug. 28, 2007] | (a) Reportable events. (1) The holder of an operating license under this part or a combined license under part 52 of this chapter (after the Commission has made the finding under § 52.103(g) of this chapter) for a nuclear power plant (licensee) shall submit a Licensee Event Report (LER) for any event of the type described in this paragraph within 60 days after the discovery of the event. In the case of an invalid actuation reported under § 50.73(a)(2)(iv), other than actuation of the reactor protection system (RPS) when the reactor is critical, the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER. Unless otherwise specified in this section, the licensee shall report an event if it occurred within 3 years of the date of discovery regardless of the plant mode or power level, and regardless of the significance of the structure, system, or component that initiated the event. (2) The licensee shall report: (i)(A) The completion of any nuclear plant shutdown required by the plant's Technical Specifications. (B) Any operation or condition which was prohibited by the plant's Technical Specifications except when: ( 1 ) The Technical Specification is administrative in nature; ( 2 ) The event consisted solely of a case of a late surveillance test where the oversight was corrected, the test was performed, and the equipment was found to be capable of performing its specified safety functions; or ( 3 ) The Technical Specification was revised prior to discovery of the event such that the operation or condition was no longer prohibited at the time of discovery of the event. (C) Any deviation from the plant's Technical Specifications authorized pursuant to § 50.54(x) of this part. (ii) Any event or condition that resulted in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded; or (B) The nuclear power plant being in an unanalyzed conditio… | ||||||
| 10:10:1.0.1.1.30.0.109.67 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.74 Notification of change in operator or senior operator status. | NRC | [52 FR 9469, Mar. 25, 1987, as amended at 60 FR 13616, Mar. 14, 1995; 68 FR 58809, Oct. 10, 2003; 86 FR 67842, Nov. 30, 2021] | Each licensee shall notify the appropriate NRC contact, as described in § 55.5 of this chapter, within 30 days of the following in regard to a licensed operator or senior operator: (a) Permanent reassignment from the position for which the licensee has certified the need for a licensed operator or senior operator under § 55.31(a)(3) of this chapter; (b) Termination of any operator or senior operator; (c) Permanent disability or illness as described in § 55.25 of this chapter. | ||||||
| 10:10:1.0.1.1.30.0.109.68 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.75 Reporting and recordkeeping for decommissioning planning. | NRC | [53 FR 24049, June 27, 1988, as amended at 58 FR 68731, Dec. 29, 1993; 59 FR 1618, Jan. 12, 1994; 61 FR 39301, July 29, 1996; 63 FR 50480, Sept. 22, 1998; 63 FR 57236, Oct. 27, 1998; 68 FR 19727, Apr. 22, 2003; 67 FR 78350, Dec. 24, 2002; 68 FR 12571, Mar. 17, 2003; 68 FR 65388, Nov. 20, 2003; 72 FR 49502, Aug. 28, 2007; 73 FR 5722, Jan. 31, 2008; 77 FR 35571, June 17, 2012; 83 FR 30288, June 28, 2018; 84 FR 65644, Nov. 29, 2019; 87 FR 68031, Nov. 14, 2022; 89 FR 106251, Dec. 30, 2024] | (a) This section establishes requirements for indicating to NRC how a licensee will provide reasonable assurance that funds will be available for the decommissioning process. For power reactor licensees (except a holder of a manufacturing license under part 52 of this chapter), reasonable assurance consists of a series of steps as provided in paragraphs (b), (c), (e), and (f) of this section. Funding for the decommissioning of power reactors may also be subject to the regulation of Federal or State Government agencies (e.g., Federal Energy Regulatory Commission (FERC) and State Public Utility Commissions) that have jurisdiction over rate regulation. The requirements of this section, in particular paragraph (c) of this section, are in addition to, and not substitution for, other requirements, and are not intended to be used by themselves or by other agencies to establish rates. (b) Each power reactor applicant for or holder of an operating license, and each applicant for a combined license under subpart C of 10 CFR part 52 for a production or utilization facility of the type and power level specified in paragraph (c) of this section shall submit a decommissioning report, as required by § 50.33(k). (1) For an applicant for or holder of an operating license under part 50, the report must contain a certification that financial assurance for decommissioning will be (for a license applicant), or has been (for a license holder), provided in an amount which may be more, but not less, than the amount stated in the table in paragraph (c)(1) of this section adjusted using a rate at least equal to that stated in paragraph (c)(2) of this section. For an applicant for a combined license under subpart C of 10 CFR part 52, the report must contain a certification that financial assurance for decommissioning will be provided no later than 30 days after the Commission publishes notice in the Federal Register under § 52.103(a) in an amount which may be more, but not less, than the amount stated in the table in paragraph (c)(1) o… | ||||||
| 10:10:1.0.1.1.30.0.109.69 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.76 Licensee's change of status; financial qualifications. | NRC | [69 FR 4448, Jan. 30, 2004] | An electric utility licensee holding an operating license (including a renewed license) for a nuclear power reactor, no later than seventy-five (75) days prior to ceasing to be an electric utility in any manner not involving a license transfer under § 50.80, shall provide the NRC with the financial qualifications information that would be required for obtaining an initial operating license as specified in § 50.33(f)(2). The financial qualifications information must address the first full five years of operation after the date the licensee ceases to be an electric utility. | ||||||
| 10:10:1.0.1.1.30.0.110.70 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.78 Facility information and verification. | NRC | [73 FR 78605, Dec. 23, 2008, as amended at 85 FR 65663, Oct. 16, 2020] | (a) In response to a written request by the Commission, each applicant for a construction permit or license and each recipient of a construction permit or a license shall submit facility information, as described in § 75.10 of this chapter, on IAEA Design Information Questionnaire forms and site information on DOC/NRC Form AP-A and associated forms; (b) As required by the Additional Protocol, shall submit location information described in § 75.11 of this chapter on DOC/NRC Form AP-1 and associated forms; and (c) Shall permit verification thereof by the International Atomic Energy Agency (IAEA) and take other action as necessary to implement the US/IAEA Safeguards Agreement, as described in part 75 of this chapter. | ||||||
| 10:10:1.0.1.1.30.0.111.71 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.80 Transfer of licenses. | NRC | [26 FR 9546, Oct. 10, 1961, as amended at 35 FR 19661, Dec. 29, 1970; 38 FR 3956, Feb. 9, 1973; 65 FR 44660, July 19, 2000; 70 FR 61888, Oct. 27, 2005; 72 FR 49503, Aug. 28, 2007] | (a) No license for a production or utilization facility (including, but not limited to, permits under this part and part 52 of this chapter, and licenses under parts 50 and 52 of this chapter), or any right thereunder, shall be transferred, assigned, or in any manner disposed of, either voluntarily or involuntarily, directly or indirectly, through transfer of control of the license to any person, unless the Commission gives its consent in writing. (b)(1) An application for transfer of a license shall include: (i) For a construction permit or operating license under this part, as much of the information described in §§ 50.33 and 50.34 of this part with respect to the identity and technical and financial qualifications of the proposed transferee as would be required by those sections if the application were for an initial license. The Commission may require additional information such as data respecting proposed safeguards against hazards from radioactive materials and the applicant's qualifications to protect against such hazards. (ii) For an early site permit under part 52 of this chapter, as much of the information described in §§ 52.16 and 52.17 of this chapter with respect to the identity and technical qualifications of the proposed transferee as would be required by those sections if the application were for an initial license. (iii) For a combined license under part 52 of this chapter, as much of the information described in §§ 52.77 and 52.79 of this chapter with respect to the identity and technical and financial qualifications of the proposed transferee as would be required by those sections if the application were for an initial license. The Commission may require additional information such as data respecting proposed safeguards against hazards from radioactive materials and the applicant's qualifications to protect against such hazards. (iv) For a manufacturing license under part 52 of this chapter, as much of the information described in §§ 52.156 and 52.157 of this chapter with respect to the id… | ||||||
| 10:10:1.0.1.1.30.0.111.72 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.81 Creditor regulations. | NRC | [26 FR 9546, Oct. 10, 1961, as amended at 32 FR 2562, Feb. 7, 1967; 72 FR 49504, Aug. 28, 2007] | (a) Pursuant to section 184 of the Act, the Commission consents, without individual application, to the creation of any mortgage, pledge, or other lien upon any production or utilization facility not owned by the United States which is the subject of a license or upon any leasehold or other interest in such facility: Provided: (1) That the rights of any creditor so secured may be exercised only in compliance with and subject to the same requirements and restrictions as would apply to the licensee pursuant to the provisions of the license, the Atomic Energy Act of 1954, as amended, and regulations issued by the Commission pursuant to said Act; and (2) That no creditor so secured may take possession of the facility pursuant to the provisions of this section prior to either the issuance of a license from the Commission authorizing such possession or the transfer of the license. (b) Any creditor so secured may apply for transfer of the license covering such facility by filing an application for transfer of the license pursuant to § 50.80(b). The Commission will act upon such application pursuant to § 50.80 (c). (c) Nothing contained in this regulation shall be deemed to affect the means of acquiring, or the priority of, any tax lien or other lien provided by law. (d) As used in this section: (1) License includes any license under this chapter, any construction permit under this part, and any early site permit under part 52 of this chapter, which may be issued by the Commission with regard to a facility; (2) “Creditor” includes, without implied limitation, the trustee under any mortgage, pledge or lien on a facility made to secure any creditor, any trustee or receiver of the facility appointed by a court of competent jurisdiction in any action brought for the benefit of any creditor secured by such mortgage, pledge or lien, any purchaser of such facility at the sale thereof upon foreclosure of such mortgage, pledge, or lien or upon exercise of any power of sale contained therein, or any assignee of any such … | ||||||
| 10:10:1.0.1.1.30.0.111.73 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.82 Termination of license. | NRC | [61 FR 39301, July 29, 1996, as amended at 62 FR 39091, July 21, 1997; 68 FR 19727, Apr. 22, 2003; 76 FR 35571, June 17, 2011; 79 FR 66603, Nov. 10, 2014; 89 FR 57720, July 16, 2024; 89 FR 106251, Dec. 30, 2024] | For power reactor licensees who, before the effective date of this rule, either submitted a decommissioning plan for approval or possess an approved decommissioning plan, the plan is considered to be the PSDAR submittal required under paragraph (a)(4) of this section and the provisions of this section apply accordingly. For power reactor licensees whose decommissioning plan approval activities have been relegated to notice of opportunity for a hearing under subpart G of 10 CFR part 2, the public meeting convened and 90-day delay of major decommissioning activities required in paragraphs (a)(4)(ii) and (a)(5) of this section shall not apply, and any orders arising from proceedings under subpart G of 10 CFR part 2 shall continue and remain in effect absent any orders from the Commission. (a) For power reactor licensees— (1)(i) When a licensee has determined to permanently cease operations the licensee shall, within 30 days, submit a written certification to the NRC, consistent with the requirements of § 50.4(b)(8); (ii) Once fuel has been permanently removed from the reactor vessel, the licensee shall submit a written certification to the NRC that meets the requirements of § 50.4(b)(9); and (iii) For licensees whose licenses have been permanently modified to allow possession but not operation of the facility, before August 28, 1996, the certifications required in paragraphs (a)(1)(i) through (ii) of this section shall be deemed to have been submitted. (2) Upon docketing of the certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessel, or when a final legally effective order to permanently cease operations has come into effect, the 10 CFR part 50 license no longer authorizes operation of the reactor or emplacement or retention of fuel into the reactor vessel. (3) Decommissioning will be completed within 60 years of permanent cessation of operations. Completion of decommissioning beyond 60 years will be approved by the Commission only when necessary to protect pu… | ||||||
| 10:10:1.0.1.1.30.0.111.74 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.83 Release of part of a power reactor facility or site for unrestricted use. | NRC | [68 FR 19727, Apr. 22, 2003] | (a) Prior written NRC approval is required to release part of a facility or site for unrestricted use at any time before receiving approval of a license termination plan. Section 50.75 specifies recordkeeping requirements associated with partial release. Nuclear power reactor licensees seeking NRC approval shall— (1) Evaluate the effect of releasing the property to ensure that— (i) The dose to individual members of the public does not exceed the limits and standards of 10 CFR Part 20, Subpart D; (ii) There is no reduction in the effectiveness of emergency planning or physical security; (iii) Effluent releases remain within license conditions; (iv) The environmental monitoring program and offsite dose calculation manual are revised to account for the changes; (v) The siting criteria of 10 CFR Part 100 continue to be met; and (vi) All other applicable statutory and regulatory requirements continue to be met. (2) Perform a historical site assessment of the part of the facility or site to be released; and (3) Perform surveys adequate to demonstrate compliance with the radiological criteria for unrestricted use specified in 10 CFR 20.1402 for impacted areas. (b) For release of non-impacted areas, the licensee may submit a written request for NRC approval of the release if a license amendment is not otherwise required. The request submittal must include— (1) The results of the evaluations performed in accordance with paragraphs (a)(1) and (a)(2) of this section; (2) A description of the part of the facility or site to be released; (3) The schedule for release of the property; (4) The results of the evaluations performed in accordance with § 50.59; and (5) A discussion that provides the reasons for concluding that the environmental impacts associated with the licensee's proposed release of the property will be bounded by appropriate previously issued environmental impact statements. (c) After receiving an approval request from the licensee for the release of a non-impacted area, the NRC shall— (1) Deter… | ||||||
| 10:10:1.0.1.1.30.0.112.75 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.90 Application for amendment of license, construction permit, or early site permit. | NRC | [72 FR 49504, Aug. 28, 2007] | Whenever a holder of a license, including a construction permit and operating license under this part, and an early site permit, combined license, and manufacturing license under part 52 of this chapter, desires to amend the license or permit, application for an amendment must be filed with the Commission, as specified in §§ 50.4 or 52.3 of this chapter, as applicable, fully describing the changes desired, and following as far as applicable, the form prescribed for original applications. | ||||||
| 10:10:1.0.1.1.30.0.112.76 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.91 Notice for public comment; State consultation. | NRC | [51 FR 7765, Mar. 6, 1986, as amended at 51 FR 40310, Nov. 6, 1986; 61 FR 39303, July 29, 1996; 69 FR 2276, Jan. 14, 2004; 72 FR 49504, Aug. 28, 2007] | The Commission will use the following procedures for an application requesting an amendment to an operating license under this part or a combined license under part 52 of this chapter for a facility licensed under §§ 50.21(b) or 50.22, or for a testing facility, except for amendments subject to hearings governed by 10 CFR part 2, subpart L. For amendments subject to 10 CFR part 2, subpart L, the following procedures will apply only to the extent specifically referenced in § 2.309(b) of this chapter, except that notice of opportunity for hearing must be published in the Federal Register at least 30 days before the requested amendment is issued by the Commission: (a) Notice for public comment. (1) At the time a licensee requests an amendment, it must provide to the Commission, in accordance with the distribution requirements specified in § 50.4, its analysis about the issue of no significant hazards consideration using the standards in § 50.92. (2)(i) The Commission may publish in the Federal Register under § 2.105 an individual notice of proposed action for an amendment for which it makes a proposed determination that no significant hazards consideration is involved, or, at least once every 30 days, publish a periodic Federal Register notice of proposed actions which identifies each amendment issued and each amendment proposed to be issued since the last such periodic notice, or it may publish both such notices. (ii) For each amendment proposed to be issued, the notice will (A) contain the staff's proposed determination, under the standards in § 50.92, (B) provide a brief description of the amendment and of the facility involved, (C) solicit public comments on the proposed determination, and (D) provide for a 30-day comment period. (iii) The comment period will begin on the day after the date of the publication of the first notice, and, normally, the amendment will not be granted until after this comment period expires. (3) The Commission may inform the public about the final disposition of an amendme… | ||||||
| 10:10:1.0.1.1.30.0.112.77 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.92 Issuance of amendment. | NRC | [51 FR 7767, Mar. 6, 1986, as amended at 72 FR 49504, Aug. 28, 2007] | (a) In determining whether an amendment to a license, construction permit, or early site permit will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses, construction permits, or early site permits to the extent applicable and appropriate. If the application involves the material alteration of a licensed facility, a construction permit will be issued before the issuance of the amendment to the license, provided however, that if the application involves a material alteration to a nuclear power reactor manufactured under part 52 of this chapter before its installation at a site, or a combined license before the date that the Commission makes the finding under § 52.103(g) of this chapter, no application for a construction permit is required. If the amendment involves a significant hazards consideration, the Commission will give notice of its proposed action: (1) Under § 2.105 of this chapter before acting thereon; and (2) As soon as practicable after the application has been docketed. (b) The Commission will be particularly sensitive to a license amendment request that involves irreversible consequences (such as one that permits a significant increase in the amount of effluents or radiation emitted by a nuclear power plant). (c) The Commission may make a final determination, under the procedures in § 50.91, that a proposed amendment to an operating license or a combined license for a facility or reactor licensed under §§ 50.21(b) or 50.22, or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety. | ||||||
| 10:10:1.0.1.1.30.0.113.78 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.100 Revocation, suspension, modification of licenses, permits, and approvals for cause. | NRC | [72 FR 49504, Aug. 28, 2007, as amended at 89 FR 57720, July 16, 2024] | A license, permit, or standard design approval under parts 50 or 52 of this chapter may be revoked, suspended, or modified, in whole or in part, for any material false statement in the application or in the supplemental or other statement of fact required of the applicant; or because of conditions revealed by the application or statement of fact of any report, record, inspection, or other means which would warrant the Commission to refuse to grant a license, permit, or approval on an original application (other than those relating to §§ 50.51, 50.42, and 50.43(b)); or for failure to manufacture a reactor, or construct or operate a facility in accordance with the terms of the permit or license, provided, however, that failure to make timely completion of the proposed construction or alteration of a facility under a construction permit under part 50 of this chapter or a combined license under part 52 of this chapter shall be governed by the provisions of § 50.55(b); or for violation of, or failure to observe, any of the terms and provisions of the act, regulations, license, permit, approval, or order of the Commission. | ||||||
| 10:10:1.0.1.1.30.0.113.79 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.101 Retaking possession of special nuclear material. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 40 FR 8790, Mar. 3, 1975] | Upon revocation of a license, the Commission may immediately cause the retaking of possession of all special nuclear material held by the licensee. | ||||||
| 10:10:1.0.1.1.30.0.113.80 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.102 Commission order for operation after revocation. | NRC | [40 FR 8790, Mar. 3, 1975] | Whenever the Commission finds that the public convenience and necessity, or the Department finds that the production program of the Department requires continued operation of a production or utilization facility, the license for which has been revoked, the Commission may, after consultation with the appropriate federal or state regulatory agency having jurisdiction, order that possession be taken of such facility and that it be operated for a period of time as, in the judgment of the Commission, the public convenience and necessity or the production program of the Department may require, or until a license for operation of the facility shall become effective. Just compensation shall be paid for the use of the facility. | ||||||
| 10:10:1.0.1.1.30.0.113.81 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.103 Suspension and operation in war or national emergency. | NRC | [21 FR 355, Jan. 19, 1956, as amended at 35 FR 11416, July 17, 1970; 40 FR 8790, Mar. 3, 1975] | (a) Whenever Congress declares that a state of war or national emergency exists, the Commission, if it finds it necessary to the common defense and security, may, (1) Suspend any license it has issued. (2) Cause the recapture of special nuclear material. (3) Order the operation of any licensed facility. (4) Order entry into any plant or facility in order to recapture special nuclear material or to operate the facility. (b) Just compensation shall be paid for any damages caused by recapture of special nuclear material or by operation of any facility, pursuant to this section. | ||||||
| 10:10:1.0.1.1.30.0.114.82 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.109 Backfitting. | NRC | [53 FR 20610, June 6, 1988, as amended at 54 FR 15398, Apr. 18, 1989; 72 FR 49504, Aug. 28, 2007; 89 FR 57720, July 16, 2024] | (a)(1) Backfitting is defined as the modification of or addition to systems, structures, components, or design of a facility; or the design approval or manufacturing license for a facility; or the procedures or organization required to design, construct or operate a facility; any of which may result from a new or amended provision in the Commission's regulations or the imposition of a regulatory staff position interpreting the Commission's regulations that is either new or different from a previously applicable staff position after: (i) The date of issuance of the construction permit for the facility for facilities having construction permits issued after October 21, 1985; (ii) Six (6) months before the date of docketing of the operating license application for the facility for facilities having construction permits issued before October 21, 1985; (iii) The date of issuance of the operating license for the facility for facilities having operating licenses; (iv) The date of issuance of the design approval under subpart E of part 52 of this chapter; (v) The date of issuance of a manufacturing license under subpart F of part 52 of this chapter; (vi) The date of issuance of the first construction permit issued for a duplicate design under appendix N of this part; or (vii) The date of issuance of a combined license under subpart C of part 52 of this chapter, provided that if the combined license references an early site permit, the provisions in § 52.39 of this chapter apply with respect to the site characteristics, design parameters, and terms and conditions specified in the early site permit. If the combined license references a standard design certification rule under subpart B of 10 CFR part 52, the provisions in § 52.63 of this chapter apply with respect to the design matters resolved in the standard design certification rule, provided however, that if any specific backfitting limitations are included in a referenced design certification rule, those limitations shall govern. If the combined license referen… | ||||||
| 10:10:1.0.1.1.30.0.115.83 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.110 Violations. | NRC | [57 FR 55075, Nov. 24, 1992] | (a) The Commission may obtain an injunction or other court order to prevent a violation of the provisions of— (1) The Atomic Energy Act of 1954, as amended; (2) Title II of the Energy Reorganization Act of 1974, as amended; or (3) A regulation or order issued pursuant to those Acts. (b) The Commission may obtain a court order for the payment of a civil penalty imposed under Section 234 of the Atomic Energy Act: (1) For violations of— (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of the Atomic Energy Act of 1954, as amended; (ii) Section 206 of the Energy Reorganization Act; (iii) Any rule, regulation, or order issued pursuant to the sections specified in paragraph (b)(1)(i) of this section; (iv) Any term, condition, or limitation of any license issued under the sections specified in paragraph (b)(1)(i) of this section. (2) For any violation for which a license may be revoked under section 186 of the Atomic Energy Act of 1954, as amended. | ||||||
| 10:10:1.0.1.1.30.0.115.84 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.111 Criminal penalties. | NRC | [57 FR 55075, Nov. 24, 1992, as amended at 61 FR 39303, July 29, 1996] | (a) Section 223 of the Atomic Energy Act of 1954, as amended, provides for criminal sanctions for willful violation of, attempted violation of, or conspiracy to violate, any regulation issued under sections 161b, 161i, or 161o of the Act. For purposes of section 223, all the regulations in part 50 are issued under one or more of sections 161b, 161i, or 161o, except for the sections listed in paragraph (b) of this section. (b) The regulations in 10 CFR part 50 that are not issued under sections 161b, 161i, or 161o for the purposes of section 223 are as follows: §§ 50.1, 50.2, 50.3, 50.4, 50.8, 50.11, 50.12, 50.13, 50.20, 50.21, 50.22, 50.23, 50.30, 50.31, 50.32, 50.33, 50.34a, 50.35, 50.36b, 50.37, 50.38, 50.39, 50.40, 50.41, 50.42, 50.43, 50.45, 50.50, 50.51, 50.52, 50.53, 50.56, 50.57, 50.58, 50.81, 50.90, 50.91, 50.92, 50.100, 50.101, 50.102, 50.103, 50.109, 50.110, 50.111. | ||||||
| 10:10:1.0.1.1.30.0.116.85 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.120 Training and qualification of nuclear power plant personnel. | NRC | [72 FR 49505, Aug. 28, 2007] | (a) Applicability. The requirements of this section apply to each applicant for and each holder of an operating license issued under this part and each holder of a combined license issued under part 52 of this chapter for a nuclear power plant of the type specified in § 50.21(b) or § 50.22. (b) Requirements. (1)(i) Each nuclear power plant operating license applicant, by 18 months prior to fuel load, and each holder of an operating license shall establish, implement, and maintain a training program that meets the requirements of paragraphs (b)(2) and (b)(3) of this section. (ii) Each holder of a combined license shall establish, implement, and maintain the training program that meets the requirements of paragraphs (b)(2) and (b)(3) of this section, as described in the final safety analysis report no later than 18 months before the scheduled date for initial loading of fuel. (2) The training program must be derived from a systems approach to training as defined in 10 CFR 55.4, and must provide for the training and qualification of the following categories of nuclear power plant personnel: (i) Non-licensed operator. (ii) Shift supervisor. (iii) Shift technical advisor. (iv) Instrument and control technician. (v) Electrical maintenance personnel. (vi) Mechanical maintenance personnel. (vii) Radiological protection technician. (viii) Chemistry technician. (ix) Engineering support personnel. (3) The training program must incorporate the instructional requirements necessary to provide qualified personnel to operate and maintain the facility in a safe manner in all modes of operation. The training program must be developed to be in compliance with the facility license, including all technical specifications and applicable regulations. The training program must be periodically evaluated and revised as appropriate to reflect industry experience as well as changes to the facility, procedures, regulations, and quality assurance requirements. The training program must be periodically reviewed by licensee man… | ||||||
| 10:10:1.0.1.1.30.0.116.86 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.135 Renewal of non-power production or utilization facility licenses issued under § 50.22 and testing facility licenses. | NRC | [89 FR 106252, Dec. 30, 2024] | (a) Applicability. The requirements in this section apply to applicants for renewed non-power production or utilization facility operating licenses issued under § 50.22 and to applicants for renewed testing facility operating licenses issued under § 50.21(c). (b) Written communications. All applications, correspondence, reports, and other written communications must be filed in accordance with applicable portions of § 50.4. (c) Filing of application. (1) The filing of an application for a renewed license must be in accordance with subpart A of 10 CFR part 2 and all applicable sections of this part. (2) An application for a renewed license may not be submitted to the Commission earlier than 10 years before the expiration of the operating license currently in effect. (d) Contents of application. (1) Each application must include the information specified in §§ 50.33, 50.34, and 50.36, as applicable. (2) Each application must include conforming changes to the standard indemnity agreement, under 10 CFR part 140 to account for the expiration term of the proposed renewed license. (3) Each application must include a supplement to the environmental report that complies with the requirements of 10 CFR 51.56. (e) Issuance of a renewed license. (1) A renewed license will be of the class for which the operating license currently in effect was issued. (2) A renewed license will be issued for a fixed period of time. The term of any renewed license may not exceed 40 years. (3) A renewed license will become effective immediately upon its issuance, thereby superseding the operating license previously in effect. If a renewed license is subsequently set aside upon further administrative or judicial appeal, the operating license previously in effect will be reinstated unless its term has expired and the renewal application was not filed in a timely manner in accordance with 10 CFR 2.109. (4) A renewed license may be subsequently renewed in accordance with all applicable requirements. | ||||||
| 10:10:1.0.1.1.30.0.116.87 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.150 Aircraft impact assessment. | NRC | [74 FR 28146, June 12, 2009] | (a) Assessment requirements —(1) Assessment. Each applicant listed in paragraph (a)(3) shall perform a design-specific assessment of the effects on the facility of the impact of a large, commercial aircraft. Using realistic analyses, the applicant shall identify and incorporate into the design those design features and functional capabilities to show that, with reduced use of operator actions: (i) The reactor core remains cooled, or the containment remains intact; and (ii) spent fuel cooling or spent fuel pool integrity is maintained. (2) Aircraft impact characteristics. 1 The assessment must be based on the beyond-design-basis impact of a large, commercial aircraft used for long distance flights in the United States, with aviation fuel loading typically used in such flights, and an impact speed and angle of impact considering the ability of both experienced and inexperienced pilots to control large, commercial aircraft at the low altitude representative of a nuclear power plant's low profile. 1 Changes to the detailed parameters on aircraft impact characteristics set forth in guidance shall be approved by the Commission. (3) Applicability. The requirements of paragraphs (a)(1) and (a)(2) of this section apply to applicants for: (i) Construction permits for nuclear power reactors issued under this part after July 13, 2009; (ii) Operating licenses for nuclear power reactors issued under this part for which a construction permit was issued after July 13, 2009; (iii)(A) Standard design certifications issued under part 52 of this chapter after July 13, 2009; (B) Renewal of standard design certifications in effect on July 13, 2009 which have not been amended to comply with the requirements of this section by the time of application for renewal; (iv) Standard design approvals issued under part 52 of this chapter after July 13, 2009; (v) Combined licenses issued under part 52 of this chapter that: (A) Do not reference a standard design certification, standard design approval, or manufactured re… | ||||||
| 10:10:1.0.1.1.30.0.116.88 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.155 Mitigation of beyond-design-basis events. | NRC | [84 FR 39718, Aug. 9, 2019] | (a) Applicability. (1) Each holder of an operating license for a nuclear power reactor under this part and each holder of a combined license under part 52 of this chapter for which the Commission has made the finding under § 52.103(g) of this chapter shall comply with the requirements of this section until submittal of the license holder's certifications described in § 50.82(a)(1) or § 52.110(a) of this chapter. (2)(i) Once the certifications described in § 50.82(a)(1) or § 52.110(a) of this chapter have been submitted by a licensee subject to the requirements of this section, that licensee need only comply with the requirements of paragraphs (b) through (d) and (f) of this section associated with spent fuel pool cooling capabilities. (ii) Holders of operating licenses or combined licenses for which the certifications described in § 50.82(a)(1) or § 52.110(a) of this chapter have been submitted need not meet the requirements of this section except for the requirements of paragraph (b)(2) of this section associated with spent fuel pool cooling capabilities once the decay heat of the fuel in the spent fuel pool can be removed solely by heating and boiling of water within the spent fuel pool and the boil-off period provides sufficient time for the licensee to obtain off-site resources to sustain the spent fuel pool cooling function indefinitely, as demonstrated by an analysis performed and retained by the licensee. (iii) The holder of the license for Millstone Power Station, Unit 1, is not subject to the requirements of this section. (iv) Holders of operating licenses or combined licenses for which the certifications described in § 50.82(a)(1) or § 52.110(a) of this chapter have been submitted need not meet the requirements of this section once all irradiated fuel has been permanently removed from the spent fuel pool(s). (b) Strategies and guidelines. Each applicant or licensee shall develop, implement, and maintain: (1) Mitigation strategies for beyond-design-basis external events—Strategies and guideline… | ||||||
| 10:10:1.0.1.1.30.0.117.89 | 10 | Energy | I | 50 | PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES | § 50.160 Emergency preparedness for small modular reactors, non-light-water reactors, and non-power production or utilization facilities. | NRC | [88 FR 80076, Nov. 16, 2023] | (a) Definitions. For the purpose of this section: (1) Site boundary means site boundary as defined in § 20.1003 of this chapter. (2) [Reserved] (b) Requirements. The emergency plan shall contain information needed to demonstrate compliance with the elements set forth in this paragraph. The applicable requirements of § 50.47(a)(1) apply to applications submitted under this section. (1) Performance-based framework. Demonstrate effective response in drills and exercises for emergency and accident conditions. (i) Maintenance of performance. Maintain in effect preparedness to respond to emergency and accident conditions and describe in an emergency plan the provisions to be employed to maintain preparedness. (ii) Performance objectives. (A) By the beginning of each calendar quarter, develop and maintain a complete list of performance objectives for that calendar quarter; and (B) Maintain records showing the implemented performance objectives and associated metrics during each calendar quarter for the previous eight calendar quarters. (iii) Emergency response performance. The emergency response team must have sufficient capability to demonstrate the following emergency response functions using drills or exercises: (A) Event classification and mitigation. Assess, classify, monitor, and repair facility malfunctions in accordance with the emergency plan to return the facility to safe conditions. (B) Protective actions. Implement and maintain protective actions for onsite personnel for emergency conditions, and recommend protective actions to offsite authorities as conditions warrant. (C) Communications. Establish and maintain effective communications with the emergency response organization, and make notifications to response personnel and organizations who may have responsibilities for responding during emergencies. (D) Command and control. Establish and maintain effective command and control for emergencies by using a supporting organizational structure with defined roles, responsibilit… |
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