5.4 Power and Utilities — Nuclear
The U.S. Nuclear Regulatory Commission (NRC) defines decommissioning as permanently removing a nuclear facility from service and reducing
radioactive material on the licensed site to levels that permit termination of the NRC license. Legal
obligations associated with the decommissioning of a nuclear power plant generally are within the scope
of ASC 410-20.
5.4.1 Nuclear Power Plant Decommissioning
Decommissioning involves removing the spent nuclear fuel (i.e., the fuel that has been in the reactor vessel),
dismantling any systems or components containing activated material (such as the reactor vessel and
primary loop), and cleaning up or dismantling contaminated materials from the facility. All activated
materials generally have to be removed from the site and shipped to a waste processing, storage, or
disposal facility.
The legal obligation associated with the decommissioning of a nuclear power
plant arises from the regulations established by the NRC. Before a nuclear power
plant begins operations, the NRC requires the licensee to establish or obtain a
financial mechanism, such as a trust fund or a guarantee from its parent
company, to ensure that there will be sufficient money to cover the cost for the
ultimate decommissioning of the facility. The minimum decommissioning funding
required by the NRC reflects only the efforts necessary to terminate the NRC
license, which is commonly known as the “Part 50 license.”1 This license is not terminated until the licensee has completed all
activities included in the approved license termination plan (LTP). Other
activities related to facility deactivation and site closure, including
operation of the spent fuel storage pool, construction and operation of an
independent spent fuel storage installation (ISFSI), demolition of
decontaminated structures, and site restoration activities after residual
radioactivity has been removed, are not included in the NRC definition of
decommissioning. However, costs for the completion of these activities are
typically included in the decommissioning cost estimate (DCE) because there may
be a legal obligation imposed by the state or local government, or both, for
ultimate release of the property.
5.4.1.1 Decommissioning Funding Requirements (10 CFR Section 50.75)
Under 10 CFR Section 50.75, each nuclear power plant
licensee must report to the NRC every two years the status of its
decommissioning fund for each reactor or share of a reactor that it owns. At
or about five years before the projected end of operations, each power
reactor licensee must submit to the NRC a preliminary DCE that includes an
up-to-date assessment of the major factors that could affect the cost of
decommissioning the reactor.
Note that the biennial reporting requirement applies to
licensees during the operating phase. Licensees that have permanently ceased
operations and are actively engaged in decommissioning are subject to
additional annual financial assurance reporting requirements under 10 CFR
Section 50.82(a)(8)(v)–(vii), as further discussed in Section 5.4.1.3.
5.4.1.2 60-Year Completion Report (10 CFR Section 50.82)
Under 10 CFR Section 50.82(a)(3), decommissioning of the site, including any
general license ISFSI, must be completed within 60 years of permanent
cessation of operations unless the NRC approves an extended timeline when
necessary to protect public health and safety. This constraint is directly
relevant to both the accumulation schedule for decommissioning trust funds
and the discount rate and escalation assumptions used in site-specific DCEs.
As further discussed in Section
5.4.1.5, an extension of the operating license affects the
point in time from which the 60-year window begins to run.
5.4.1.3 Post-Shutdown Decommissioning Activities Report (10 CFR Section 50.82)
Under 10 CFR Section 50.82, a nuclear power plant licensee
is required to submit a post-shutdown decommissioning activities report
(PSDAR) to the NRC, as well as a copy to the affected state(s), before or
within two years after permanent cessation of operations. The PSDAR must
contain the following:
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A description of the planned decommissioning activities.
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A schedule for the accomplishment of significant milestones.
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A discussion of whether the environmental impacts of the site-specific decommissioning activities will be bounded by appropriate federally issued environmental review documents (such as previously approved environmental impact statements), along with a description of any activities whose impacts would not be so bounded and the licensee’s plan for addressing such activities before they are undertaken.
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A site-specific DCE, including the projected cost of managing irradiated fuel.
After receiving the PSDAR, the NRC publishes a notice of receipt, makes the
PSDAR available for public comment, and holds a public meeting in the
vicinity of the licensee’s facility to discuss the PSDAR. Upon waiting at
least 90 days after the NRC receives the PSDAR and the licensee submits its
certifications of permanent cessation of operations and permanent fuel
removal, the licensee may proceed with major decommissioning activities
unless the NRC issues an order limiting or prohibiting such activities.
While actively engaged in decommissioning, the licensee must submit annual
financial assurance status reports under 10 CFR Section
50.82(a)(8)(v)–(vii), providing updated information on fund balances, cost
projections, and the adequacy of remaining financial assurance
mechanisms.
5.4.1.4 License Termination Plan (10 CFR Section 50.82)
Under 10 CFR Section 50.82, a nuclear power plant licensee
is also required to submit an LTP at least two years before its license is
terminated. The LTP must include the following:
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A site characterization.
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Identification of remaining dismantlement activities.
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Plans for site remediation.
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Detailed plans for the final survey of residual contamination at the site.
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A description of the end use of the site, if restricted.
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An updated site-specific estimate of remaining decommissioning costs.
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A supplement to the environmental report.
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Identification of any parts of the facility or site that were released for use before the LTP was approved.
The Nuclear Energy Institute (NEI), a nuclear industry trade association,
provides guidance on the LTP process in its December 2024 technical report
License Termination Process (NEI 22-01,
Revision 1), which reflects lessons learned from recent decommissioning
proceedings.
5.4.1.5 Subsequent License Renewal and Its Effect on Decommissioning Obligations (10 CFR Part 54)
The decommissioning regulatory framework described above
assumes a fixed projected end-of-operations date from which funding
adequacy, reporting timelines, and cost estimates are calibrated. That
assumption is increasingly subject to change as a result of subsequent
license renewal (SLR), the regulatory pathway through which nuclear power
plant operators may extend operations from the initial 60-year licensed
period to 80 years.
SLR is governed under 10 CFR Part 54, “Requirements for Renewal of Operating
Licenses for Nuclear Power Plants.” It is now an active and mainstream part
of the nuclear industry’s planning horizon: as of early 2026, 21 additional
reactor units had formally notified the NRC of planned SLR application
submittals in the 2025–2027 time frame, and approved SLRs have demonstrated
that nuclear power plants can be licensed to operate for 80 years, pending
site-specific findings. Separately, the nuclear power resurgence driven by
data center load growth has further increased incentives for licensees to
pursue extended operations, with SLR serving as a key mechanism for
providing long-term power supply certainty to large commercial customers.
From a decommissioning cost and financial assurance perspective, SLR has
several important implications:
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An SLR extends the operating period by 20 years, which lengthens the time available for decommissioning trust fund assets to accumulate investment returns. This can improve projected fund adequacy relative to a shorter operating horizon, but only if the underlying assumptions (earnings rates, cost escalation, and the timing of decommissioning) are updated accordingly in the site-specific DCE.
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An 80-year operating horizon means that decommissioning costs will be incurred further into the future, requiring revised assumptions regarding labor cost escalation, low-level radioactive waste burial charges (as indexed in NUREG-1307), and technology changes. Under 10 CFR Section 50.75, funding projections must reflect updated assumptions regarding all such factors. The preliminary DCE that is required five years before the projected end of operations will also be triggered at a later date under an SLR, potentially deferring what might otherwise be a near-term disclosure obligation.
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The 60-year completion window under 10 CFR Section 50.82(a)(3) begins at permanent cessation of operations. An SLR therefore also extends by 20 years the latest permissible date for completing decommissioning, which affects the terminal date used in present value calculations for AROs under ASC 410-20.
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The shift from biennial to more frequent reporting under 10 CFR Section 50.75 occurs within five years of the projected end of operations. An SLR pushes that trigger out by 20 years, with implications for when estimates by management and ARO disclosures may require updating to reflect a higher-frequency reporting posture.
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SLR approval is conditioned on the licensee’s demonstrating the adequacy of aging management programs (AMPs) for the 60- to 80-year operating period, as evaluated under NUREG-2191. Updated guidance documents, including revised versions of NUREG-2191 and NUREG-2192, were issued in early 2025 and reflect the most current NRC expectations for SLR applicants. Increased capital expenditure requirements associated with these AMPs may also affect the operator’s overall cost basis and the relative economics of SLR versus early retirement, which is a consideration relevant to the going-concern assumptions underlying ARO measurement.
5.4.2 Nuclear Plant Decommissioning Alternatives
The nuclear DCE must reflect the type of decommissioning alternative selected.
In accordance with 10 CFR Parts 30, 40, 50, 51, 70, and 72, a nuclear power
plant licensee may choose from three decommissioning alternatives: DECON,
SAFSTOR, or ENTOMB. These alternatives are summarized in the diagram below.
In general, decommissioning must be completed within 60 years of the plant’s
cessation of operations. A time beyond that would be considered only when
necessary to protect public health and safety in accordance with NRC
regulations. The duration of operations depends on the time prescribed by the
operating license. Historically, nuclear facilities have typically been
permitted to operate for a period of 60 years based on an initial license of 40
years and a license renewal for an additional 20 years. More recently, some
licensees have sought a second license renewal to extend the life of their
permitted operating period from 60 years to 80 years. Life extensions affect
when a licensed plant is shut down and eventually decommissioned. If a
licensee’s application for a life extension is approved, the licensee will need
to prepare (1) assumptions about when spent fuel will be removed from the site
(i.e., before or after plant shutdown) and (2) a revised decommissioning
timeline.
Licensees often change their decommissioning alternative selection during the
life of the plant. For example, a licensee that originally anticipated
decommissioning a power plant under the DECON alternative may change this
decision and select SAFSTOR on the basis of external factors. If the
decommissioning alternative is changed, the DCE must be revised accordingly.
5.4.3 High-Level Radioactive Waste
Highly radioactive byproducts of the reactions that occur inside nuclear reactors are called high-level
radioactive waste. There are two types of high-level radioactive waste: (1) spent fuel when it is accepted
for disposal and (2) waste materials remaining after spent fuel is reprocessed. High-level radioactive
waste must be handled and stored with care because of its highly radioactive fission products.
The only way that radioactive waste can become harmless is through decay. However, it can take
hundreds of thousands of years for high-level radioactive waste to fully decay. For that reason, high-level
radioactive waste must be stored and finally disposed of in a way that provides the public with adequate
protection for a very long time.
In 1982, Congress passed the Nuclear Waste Policy Act, assigning the federal
government’s long-standing responsibility for disposal of spent nuclear fuel
created by commercial nuclear generating plants to the U.S. Department of Energy
(DOE). The DOE was to begin accepting spent fuel by January 31, 1998; however,
no progress has been made to date in the removal of spent fuel from commercial
generating sites. In January 2013, the DOE issued the document Strategy for the Management and Disposal of Used
Nuclear Fuel and High-Level Radioactive
Waste (the “January 2013 document”). In its January
2013 document, the DOE stated that “[w]ith the appropriate authorizations from
Congress, the Administration currently plans to implement a program over the
next 10 years that [a]dvances toward the siting and licensing of a larger
interim storage facility to be available by 2025 that will have sufficient
capacity to provide flexibility in the waste management system and allows for
acceptance of enough used nuclear fuel to reduce expected government
liabilities.”
Completion of the decommissioning process is dependent on the DOE’s ability to remove spent fuel
from the site in a timely manner. As a result of the DOE’s current inability to accept the spent fuel,
commercial generating sites have been storing their high-level radioactive waste in the ISFSI, which
is typically located on the same property as the nuclear reactor. Costs associated with the long-term
storage of the spent fuel are typically included in the decommissioning estimate. Costs for storage
include operation and maintenance of the ISFSI and security as required under NRC regulations.
It is important to consider the uncertainties associated with both the requirements related to the
storage of spent nuclear fuel and the timing and ultimate disposal of spent fuel, as well as how those
uncertainties may affect ARO cost estimates. Three approaches have been observed in industry with
respect to the estimation of when the DOE will be able to accept spent fuel from a nuclear power plant:
- The DOE will not be able to accept spent fuel, and the material will remain on-site indefinitely.
- The DOE will accept the spent fuel at a later time based on an adjustment to the pickup date provided in the DOE’s July 2004 Acceptance Priority Ranking & Annual Capacity Report, taking into account the 2025 spent fuel pickup start date provided in the DOE’s January 2013 document.
- An approach similar to that in (2) above, but with a spent fuel pickup start date later than 2025 based on professional judgment.
In addition, many of the commercial generators have entered into
settlement agreements with the DOE to obtain reimbursement from the DOE for
costs related to spent fuel that were incurred as a result of the DOE’s delay in
taking possession of spent fuel. In practice, nuclear power generators have
obtained (1) reimbursements from the federal government or state regulatory
agencies for operation and maintenance costs or (2) have recovered other
monetary damages associated with the federal government’s failure to begin
removing spent nuclear fuel and other radioactive waste from former nuclear
reactor sites. Reimbursement can be sought through either settlement agreements
or damage claims. If a utility has a settlement agreement with the DOE, the
utility can seek annual reimbursement for any delay-related nuclear waste
storage costs incurred during the year. In the absence of a settlement agreement
with the DOE, a utility can file a claim for damages in the U.S. Court of
Federal Claims. Unlike settlements, which cover all past and future damages
resulting from the DOE’s nuclear waste delays, awards by the U.S. Court of
Federal Claims can cover only damages that have already been incurred;
accordingly, utilities must continue filing damage claims as they accrue
additional delay-related costs.
The NRC has been engaged in a multiyear rulemaking process to
implement lessons learned from plants that have transitioned to decommissioning
since 2011. On January 31, 2024, NRC staff submitted the final rule package
Regulatory Improvements for Production and Utilization
Facilities Transitioning to Decommissioning (Docket
NRC-2015-0070; SECY-24-0011) to the Commission for review and approval. As of
July 15, 2026, the rule has not yet been published in the Federal
Register and is therefore not yet effective. If approved and published,
the rule would introduce a graded, four-step regulatory framework aligning
safety and security requirements with the reduction in radiological risk as
decommissioning progresses. Publication of the final rule would most likely
constitute a material triggering event requiring affected entities to reassess
and revise their DCEs.
Footnotes
1
The term “Part 50 license” refers to 10 CFR Part 50, the
citation to the corresponding regulations in the Code of Federal
Regulations.