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10 C.F.R. §§ 53.1070–53.1080

3 sections in range

§53.1070. Termination of license.

10 C.F.R. § 53.1070

For each holder of an OL or COL under this part—
(a)
(1)
When the licensee has determined to permanently cease operations the licensee must, within 30 days, submit a written certification to the NRC, consistent with the requirements of § 53.040(b)(8);
(2)
When appropriate to support decommissioning activities and the eventual permanent removal of fuel from the reactor vessel, the licensee must develop defueled technical specifications by reviewing the operational technical specifications and determining which specifications no longer apply during decommissioning and which ones should remain applicable. The licensee must make the appropriate submittals to the NRC in accordance with § 53.1510 to request changes to the technical specifications; and
(3)
(i)
Once fuel has been permanently removed from the reactor vessel, the licensee must submit a written certification to the NRC that meets the requirements of § 53.040(b)(9); and
(ii)
The licensee must establish and maintain staffing consisting of certified fuel handlers, as defined under § 53.020, and other non-licensed personnel with appropriate qualifications, and in sufficient numbers, to ensure support for facility operations and radiological control activities, as required by the facility defueled technical specifications. These personnel must be subject to the training requirements of § 53.830.
(b)
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 license issued under this part no longer authorizes operation of the reactor or emplacement or retention of fuel into the reactor vessel.
(c)
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 public health and safety. Factors that will be considered by the Commission in evaluating an alternative that provides for completion of decommissioning beyond 60 years of permanent cessation of operations include unavailability of waste disposal capacity and other site-specific factors affecting the licensee's capability to carry out decommissioning, including presence of other nuclear facilities at the site.
(d)
(1)
Prior to or within 2 years following permanent cessation of operations, the licensee must submit a PSDAR and site-specific DCE in accordance with § 53.1060(e).
(2)
The NRC must notice receipt of the PSDAR and make the PSDAR publicly available and publish notice of its availability for public comment in the Federal Register. The NRC must also schedule a public meeting readily accessible to individuals in the vicinity of the licensee's facility. The NRC must publish a notice in the Federal Register and in a forum, such as local newspapers, that is readily accessible to individuals in the vicinity of the site, announcing the date, time, and location of the meeting, along with a brief description of the purpose of the meeting.
(e)
Licensees must not perform any major decommissioning activities, as defined in § 53.020, until 90 days after the NRC has received the licensee's PSDAR submittal and until certifications of permanent cessation of operations and permanent removal of fuel from the reactor vessel, as required under paragraph (a) of this section, have been submitted.
(f)
Licensees must not perform any decommissioning activities, as defined in § 53.020, that—
(1)
Foreclose release of the site for possible unrestricted use;
(2)
Result in significant environmental impacts not previously reviewed; or
(3)
Result in there no longer being reasonable assurance that adequate funds will be available for decommissioning.
(g)
In taking actions permitted under § 53.1540 following submittal of the PSDAR, the licensee must notify the NRC in writing, and send a copy to the affected State(s), before performing any decommissioning activity inconsistent with, or making any significant schedule change from, those actions and schedules described in the PSDAR, including changes that increase the decommissioning cost by more than 20 percent from the previously provided DCE.
(h)
Licensees may use decommissioning trust funds consistent with the limitations of § 53.1045(a). Licensees must report on the status of decommissioning trust funds consistent with the requirements of § 53.1060.
(i)
Licensees must submit an application for termination of license in accordance with § 53.1070. The application for termination of license must be accompanied or preceded by a license termination plan to be submitted for NRC approval.
(1)
The license termination plan must be a supplement to the Final Safety Analysis Report or equivalent and must be submitted at least 2 years before termination of the license date.
(2)
The license termination plan must include—
(i)
A site characterization;
(ii)
Identification of remaining dismantlement activities;
(iii)
Plans for site remediation;
(iv)
Detailed plans for the final radiation survey;
(v)
A description of the end use of the site, if restricted;
(vi)
An updated site-specific estimate of remaining decommissioning costs;
(vii)
A supplement to the environmental report, pursuant to § 51.53 of this chapter, describing any new information or significant environmental change associated with the licensee's proposed termination activities; and
(viii)
Identification of parts, if any, of the facility or site that were released for use before approval of the license termination plan.
(3)
Following receipt of the license termination plan, the NRC must make the license termination plan publicly available and publish notice of its availability for public comment in the Federal Register. The NRC must also schedule a public meeting readily accessible to individuals in the vicinity of the licensee's facility upon receipt of the license termination plan. The NRC must publish a notice in the Federal Register and in a forum, such as local newspapers, that is readily accessible to individuals in the vicinity of the site, announcing the date, time, and location of the meeting, along with a brief description of the purpose of the meeting.
(j)
If the license termination plan demonstrates that the remainder of decommissioning activities will be performed in accordance with the regulations in this chapter, will not be inimical to the common defense and security or to the health and safety of the public, and will not have a significant effect on the quality of the environment and after notice to interested persons, the Commission will approve the plan, by license amendment, subject to such conditions and limitations as it deems appropriate and necessary and authorize implementation of the license termination plan.
(k)
The Commission will terminate the license if it determines that—
(1)
The remaining dismantlement has been performed in accordance with the approved license termination plan; and
(2)
The final radiation survey and associated documentation, including an assessment of dose contributions associated with parts released for use before approval of the license termination plan, demonstrate that the facility and site have met the criteria for decommissioning in subpart E of 10 CFR part 20.
Notes, amendments, and revision history

Authority

Authority: Atomic Energy Act of 1954, secs. 11, 101, 103, 108, 122, 147, 161, 181, 182, 183, 184, 185, 186, 187, 189, 223, 234 (42 U.S.C. 2014, 2131, 2132, 2133, 2134, 2135, 2138, 2152, 2167, 2169, 2201, 2231, 2232, 2233, 2234, 2235, 2236, 2237, 2239, 2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste Policy Act of 1982, sec. 306 (42 U.S.C. 10226); National Environmental Policy Act of 1969 (42 U.S.C. 4332); 44 U.S.C. 3504 note; Pub. L. 115-439, 132 Stat. 5571.

Source

Source: 91 FR 15794, Mar. 30, 2026, unless otherwise noted.

§53.1075. Program requirements during decommissioning.

10 C.F.R. § 53.1075

(a)
Licensees that have submitted the certifications required under § 53.1070 must maintain a decommissioning fire protection program to address the potential for fires that could cause the release or spread of radioactive materials.
(1)
The objectives of the decommissioning fire protection program are to
(i)
Reasonably prevent these fires from occurring;
(ii)
Rapidly detect, control, and extinguish those fires that do occur and that could result in a radiological hazard; and
(iii)
Ensure that the risk of fire-induced radiological hazards to the public, environment, and plant personnel is minimized.
(2)
The licensee must assess the decommissioning fire protection program on a regular basis. The licensee must revise the decommissioning fire protection program documentation as appropriate throughout the various stages of facility decommissioning.
(3)
The licensee may make changes to the decommissioning fire protection program without NRC approval if these changes do not reduce the effectiveness of fire protection for structures, systems, and components that could result in a radiological hazard, taking into account the decommissioning plant conditions and activities.
(b)
[Reserved]
Notes, amendments, and revision history

Authority

Authority: Atomic Energy Act of 1954, secs. 11, 101, 103, 108, 122, 147, 161, 181, 182, 183, 184, 185, 186, 187, 189, 223, 234 (42 U.S.C. 2014, 2131, 2132, 2133, 2134, 2135, 2138, 2152, 2167, 2169, 2201, 2231, 2232, 2233, 2234, 2235, 2236, 2237, 2239, 2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste Policy Act of 1982, sec. 306 (42 U.S.C. 10226); National Environmental Policy Act of 1969 (42 U.S.C. 4332); 44 U.S.C. 3504 note; Pub. L. 115-439, 132 Stat. 5571.

Source

Source: 91 FR 15794, Mar. 30, 2026, unless otherwise noted.

§53.1080. Release of part of a commercial nuclear plant or site for unrestricted use.

10 C.F.R. § 53.1080

(a)
Prior written NRC approval is required to release part of a commercial nuclear plant or site for unrestricted use at any time before receiving approval of a license termination plan. Section 53.1060 specifies recordkeeping requirements associated with partial release. Holders of an OL or COL under this part seeking NRC review and approval must—
(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 subpart D of 10 CFR part 20;
(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 subpart D of this part 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 commercial nuclear plant or site to be released; and
(3)
Perform surveys adequate to demonstrate compliance with the radiological criteria for unrestricted use specified in § 20.1402 of this chapter for impacted areas.
(b)
For release of non-impacted areas, the licensee may submit a written request for NRC review and 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 commercial nuclear plant or site to be released;
(3)
The schedule for release of the property;
(4)
The results of the evaluations performed in accordance with § 53.1540; 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 a request from the licensee for NRC approval of the release of a non-impacted area, the NRC must—
(1)
Determine whether the licensee has adequately evaluated the effect of releasing the property as required by paragraph (a)(1) of this section;
(2)
Determine whether the licensee's classification of any release areas as non-impacted is adequately justified; and
(3)
If determining that the licensee's submittal is adequate, inform the licensee in writing that the release is approved.
(d)
For release of impacted areas, the licensee must submit an application for amendment of its license for the release of the property. The application must include—
(1)
The information specified in paragraphs (b)(1) through (b)(3) of this section;
(2)
The methods used for and results obtained from the radiation surveys required to demonstrate compliance with the radiological criteria for unrestricted use specified in § 20.1402; and
(3)
A supplement to the environmental report, under § 51.53 of this chapter.
(e)
After receiving a license amendment application from the licensee for the release of an impacted area, the NRC must—
(1)
Determine whether the licensee has adequately evaluated the effect of releasing the property as required by paragraph (a)(1) of this section;
(2)
Determine whether the licensee's classification of any release areas as non-impacted is adequately justified;
(3)
Determine whether the licensee's radiation survey for an impacted area is adequate; and
(4)
If determining that the licensee's submittal is adequate, approve the licensee's amendment application.
(f)
The NRC must publish notice receipt of the release approval request or license amendment application in the Federal Register and make the approval request or license amendment application available for public comment. Before acting on an approval request or license amendment application submitted in accordance with this section, the NRC must conduct a public meeting readily accessible to individuals in the vicinity of the licensee's facility for the purpose of obtaining public comments on the proposed release of part of the commercial nuclear plant or site. The NRC must publish a document in the Federal Register and in a forum, such as local newspapers, which is readily accessible to individuals in the vicinity of the site, announcing the date, time, and location of the meeting, along with a brief description of the purpose of the meeting.
Notes, amendments, and revision history

Authority

Authority: Atomic Energy Act of 1954, secs. 11, 101, 103, 108, 122, 147, 161, 181, 182, 183, 184, 185, 186, 187, 189, 223, 234 (42 U.S.C. 2014, 2131, 2132, 2133, 2134, 2135, 2138, 2152, 2167, 2169, 2201, 2231, 2232, 2233, 2234, 2235, 2236, 2237, 2239, 2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste Policy Act of 1982, sec. 306 (42 U.S.C. 10226); National Environmental Policy Act of 1969 (42 U.S.C. 4332); 44 U.S.C. 3504 note; Pub. L. 115-439, 132 Stat. 5571.

Source

Source: 91 FR 15794, Mar. 30, 2026, unless otherwise noted.