DG-1347 Revision 1 (Proposed Regulatory Guide RG 1.184 Rev 2) Decommissioning of Nuclear Power Reactors

U.S. NUCLEAR REGULATORY COMMISSION
DRAFT REGULATORY GUIDE DG-1347
Revision 1
Proposed Revision 2 to Regulatory Guide RG 1.184
Issue Date: February 2022
Technical Lead: Marlayna Doell

DECOMMISSIONING OF NUCLEAR POWER REACTORS
A. INTRODUCTION
Purpose
This regulatory guide (RG) provides guidance on the actions required of U.S. Nuclear
Regulatory Commission (NRC) licensees to decommission nuclear power reactors.
Applicability
This RG applies to power reactor applicants and licensees subject to Title 10 of the Code of
Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities”
(Ref. 1), and 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants”
(Ref. 2).
The fact that a licensee has permanently ceased operations and removed the fuel from the reactor
vessel, or that a final legally effective order to permanently cease operations has come into effect, or that
the licensed facility has been modified to be incapable of making use of special nuclear material without
significant facility alterations necessary to restore the capability to make use of special nuclear material
does not reduce or alter the requirement that the licensee comply with the applicable regulations, its NRC
license, and its technical specifications. Some regulations no longer apply when the licensee is no longer
authorized to operate, and some regulations no longer apply when the facility is no longer a utilization
facility. If a licensee wishes to reduce its regulatory burden for those requirements that still apply, it must
do so by requesting an exemption in accordance with 10 CFR 50.12, “Specific exemptions,” or 10 CFR
52.7, “Specific exemptions,” or a license amendment in accordance with 10 CFR 50.90, “Application for
amendment of license, construction permit, or early site permit,” or by making changes in accordance
with 10 CFR 50.59, “Changes, tests, and experiments,” as appropriate.

This RG is being issued in draft form to involve the public in the development of regulatory guidance in this area. It has not received final staff
review or approval and does not represent an NRC final staff position. Public comments are being solicited on this DG and its associated
regulatory analysis. Comments should be accompanied by appropriate supporting data. Comments may be submitted through the Federal
rulemaking Web site, http://www.regulations.gov, by searching for draft regulatory guide DG-1347. Alternatively, comments may be submitted
to Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.
Comments must be submitted by the date indicated in the Federal Register notice.
Electronic copies of this DG, previous versions of DGs, and other recently issued guides are available through the NRC’s public Web site under
the Regulatory Guides document collection of the NRC Library at https://nrcweb.nrc.gov/reading-rm/doc-collections/reg-guides/. The DG is also
available through the NRC’s Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html,
under Accession No. ML21347A080. The regulatory analysis is associated with a rulemaking and may be found in ADAMS under Accession No.
ML22019A132.

Applicable Regulations
•

10 CFR Part 20, “Standards for Protection against Radiation” (Ref. 3), provides the radiological
release criteria and radiological protection requirements that apply during decommissioning.

•

10 CFR Part 50 provides the regulations for licensing production and utilization facilities:

•

•

o

10 CFR 50.2, “Definitions,” provides definitions.

o

10 CFR 50.4, “Written communications,” provides the requirements for written
communications.

o

10 CFR 50.47, “Emergency plans,” provides emergency planning requirements.

o

10 CFR 50.54, “Conditions of licenses,” provides the conditions for a license.

o

10 CFR 50.59, “Changes, tests, and experiments,” provides the requirements for making
changes to a facility without prior NRC approval under certain circumstances.

o

10 CFR 50.71, “Maintenance of records, making of reports,” provides the requirements
for the maintenance of records and for making reports.

o

10 CFR 50.75, “Reporting and recordkeeping for decommissioning planning,” provides
the requirements for reporting and recordkeeping for decommissioning planning.

o

10 CFR 50.82, “Termination of license,” provides the requirements for termination of a
license, including a requirement for nuclear power reactor licensees to submit a postshutdown decommissioning activities report (PSDAR).

o

10 CFR 50.200, “Power reactor decommissioning emergency plans,” provides the
applicable emergency planning requirements for a facility that is transitioning between
operations and decommissioning.

10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related
Regulatory Functions” (Ref. 4), provides the requirements for environmental protection
regulations for the NRC’s domestic licensing and related regulatory functions:
o

10 CFR 51.53, “Postconstruction environmental reports,” provides the requirements for
the content of postconstruction environmental reports.

o

10 CFR 51.95, “Postconstruction environmental impact statements,” provides the
requirements for the content of postconstruction environmental impact statements.

10 CFR Part 52 governs the issuance of early site permits, standard design certifications,
combined licenses, standard design approvals, and manufacturing licenses for nuclear power
facilities.
o

10 CFR 52.110, “Termination of license,” provides the requirements for termination of a
license, including a requirement for nuclear power reactors licensees to submit a PSDAR.

DG-1347 Revision 1, Page 2

•

10 CFR Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel,
High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste” (Ref. 5),
provides, in part, the regulatory requirements for licensing independent spent fuel storage
installations (ISFSIs).

•

10 CFR Part 140, “Financial Protection Requirements and Indemnity Agreements” (Ref. 6),
provides, in part, the financial protection requirements for decommissioning facilities.

Related Guidance
•

RG 1.159, “Assuring the Availability of Funds for Decommissioning Nuclear Reactors” (Ref. 7),
provides guidance on estimating the amount of funds for decommissioning and methods
acceptable for demonstrating financial assurance.

•

RG 1.179, “Standard Format and Content of License Termination Plans for Nuclear Power
Reactors” (Ref. 8), provides guidance on the license termination plan requirements.

•

RG 1.185, “Standard Format and Content for Post-Shutdown Decommissioning Activities
Report” (Ref. 9), identifies the type of information that the PSDAR must contain and establishes
a standard set of contents and level of detail for the PSDAR.

•

RG 1.191, “Fire Protection Program for Nuclear Power Plants During Decommissioning and
Permanent Shutdown” (Ref. 10), provides guidance to licensees on a fire protection program for
licensees who have certified that their nuclear power plants have permanently ceased operations
and that the fuel has been permanently removed from the reactor vessels.

•

RG 4.21, “Minimization of Contamination and Radioactive Waste Generation: Life-Cycle
Planning” (Ref. 11), provides guidance to licensees on the steps they can take to minimize
contamination and facilitate decommissioning using a risk-informed approach.

•

RG 4.22, “Decommissioning Planning during Operations” (Ref. 12), provides guidance on
implementation of the Decommissioning Planning Rule (DPR).

•

NUREG-1713, “Standard Review Plan for Decommissioning Cost Estimates for Nuclear Power
Reactors” (Ref. 13), provides information on how the NRC staff will review site-specific
decommissioning cost estimates.

•

NUREG-1757, “Consolidated Decommissioning Guidance” (Ref. 14)
o

Volume 1, “Decommissioning Process for Materials Licensees,” contains guidance for
decommissioning of materials facilities,

o

Volume 2, “Characterization, Survey, and Determination of Radiological Criteria,” provides
guidance on compliance with the radiological criteria for license termination in 10 CFR Part
20, Subpart E, “Radiological Criteria for License Termination,”

o

Volume 3, “Financial Assurance, Recordkeeping, and Timeliness,” provides guidance on the
requirements for financial assurance for decommissioning, and the recordkeeping
requirements related to eventual decommissioning of material facilities.

DG-1347 Revision 1, Page 3

Purpose of Regulatory Guides
The NRC issues regulatory guides to describe to the public methods that the staff considers
acceptable for use in implementing specific parts of the agency’s regulations, to explain techniques that
the staff uses in evaluating specific problems or postulated events, and to provide guidance to applicants.
Regulatory guides are not substitutes for regulations and compliance with them is not required. Methods
and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they
provide a basis for the findings required for the issuance or continuance of a permit or license by the
Commission.
Paperwork Reduction Act
This RG provides voluntary guidance for implementing mandatory information collections
covered by 10 CFR 20, 50, 51, 52, 72, and 140 that are subject to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et. seq.). These information collections were approved by the Office of Management and
Budget (OMB), under control numbers 3150-0014, 3150-0011, 3150-0021, 3150-0151, 3150-0132, and
3150-0039, respectively. Send comments regarding this information collection to the FOIA, Library, and
Information Collections Branch, (T6-A10M), U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the OMB reviewer at OMB Office of
Information and Regulatory Affairs, NEOB-10202 (3150-0014, 3150-0011, 3150-0021, 3150-0151,
3150-0132, and 3150-0039), Office of Management and Budget, Washington, DC 20503.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of
information unless the document requesting or requiring the collection displays a currently valid OMB
control number.

DG-1347 Revision 1, Page 4

B. DISCUSSION
This revision of RG 1.184 (Revision 2) was issued as part of a rulemaking to amend the
Commission’s regulations relating to decommissioning for production and utilization facilities, such as
nuclear power reactors. The rulemaking, titled “Regulatory Improvements for Production and Utilization
Facilities Transitioning to Decommissioning” (RIN No: 3150-AJ59; NRC Docket ID: NRC-2015-0070),
amended 10 CFR 50.82, along with numerous other regulations, to provide for a more efficient process
for transitioning to decommissioning, to reduce the need for exemptions from existing regulations and
license amendment requests, and to address other decommissioning issues identified by the NRC staff
that could streamline and improve the overall decommissioning process.
Since the issuance of Revision 1 of this RG, several licensees have submitted PSDARs for the
NRC’s review as well as license amendment requests with proposed changes to technical specifications
for NRC approval. As a result of its review of these submittals, the NRC staff has identified common
areas of decommissioning planning that frequently require clarification or that could be enhanced as part
of the overall process, including the need for early communication, insufficient information in
environmental reports, the need for early detection of spills, discussions involving the decommissioning
strategy and timeline, plans for public involvement opportunities during decommissioning, discussions
involving the plans for storage of spent fuel, and estimates of decommissioning costs.
Scope of this Regulatory Guide
This RG describes methods and procedures that are acceptable to the NRC staff for implementing
the decommissioning regulations that relate to both the initial activities and major phases of the
decommissioning process. It does not contain guidance on the license termination process. That process is
addressed in RG 1.179, “Standard Format and Content of License Termination Plans for Nuclear Power
Reactors.”
This RG also addresses the irradiated fuel management plan (IFMP) (alternatively referred to as
the spent fuel management plan) requirements described in 10 CFR 50.54(bb) because a licensee’s ability
to properly plan and safely implement decommissioning is closely related to the licensee’s ability to
manage its spent fuel until title to, and possession of, the spent fuel is transferred to the U.S. Department
of Energy. The regulations in 10 CFR Part 72 address the requirements for the licensing and
decommissioning of facilities for the independent storage of spent nuclear fuel. This RG addresses
aspects of decommissioning 10 CFR Part 72 general license ISFSIs because the licensees must
decommission these ISFSIs in accordance with the requirements in 10 CFR 50.82 or 10 CFR 52.110. This
RG does not address the shipment of these materials or disposal of low-level, high-level, or greater-thanClass-C waste. The regulations in 10 CFR Part 71, “Packaging and Transportation of Radioactive
Material” (Ref. 15), cover the shipment of the materials, and 10 CFR Part 60, “Disposal of High-Level
Radioactive Wastes in Geologic Repositories” (Ref. 16), and 10 CFR Part 61, “Licensing Requirements
for Land Disposal of Radioactive Waste” (Ref. 17), address the disposal of waste.
This RG applies only to power reactor licensees. The decommissioning regulations for non-power
production or utilization facilities and fuel reprocessing plants appear in 10 CFR 50.82(b). The NRC staff
discusses the procedures for decommissioning these facilities, in part, in NUREG-1537, “Guidelines for
Preparing and Reviewing Applications for the Licensing of Non-Power Reactors” (Ref. 18), and the
Interim Staff Guidance Augmenting NUREG-1537 for licensing radioisotope production facilities and
aqueous homogeneous reactors (Ref. 19).

DG-1347 Revision 1, Page 5

Background
As defined by 10 CFR 50.2, “decommission” means to remove a facility or site safely from
service and reduce residual radioactivity to a level that permits (1) release of the property for unrestricted
use and termination of the license, or (2) release of the property under restricted conditions and
termination of the license. The general requirements for decommissioning, codified in 10 CFR 50.75,
50.82, 51.53, 51.95, and 52.110 contain decommissioning technical and financial criteria including
requirements for planning, timing, funding mechanisms, and environmental review. After a licensee
permanently shuts down a power reactor facility and the facility enters decommissioning, there is a
transition period to reconfigure the licensing basis and operational approach to reflect the differences
between an operating power reactor facility and a power reactor facility in decommissioning. The
decommissioning regulations establish a timeframe for completion of decommissioning, determine which
types of activities require prior NRC approval before being implemented, govern the release criteria that
the site must meet to qualify for license termination, outline the appropriate use of decommissioning
funds, and set up the enveloping environmental considerations for decommissioning.
Risk Informed Application
Reactors that have permanently ceased operations and have no fuel in the reactor vessel present
significantly reduced but different risks to public health and safety as compared to operating reactors. The
NRC amended the decommissioning rule to specify applicable requirements for such facilities by
eliminating, revising, or extending operating reactor requirements commensurate with their importance to
the safety of permanently shutdown reactors.
Decommissioning Phases
To facilitate understanding of the decommissioning process, the NRC staff has divided the
decommissioning activities for power reactors into three general phases. The first phase of
decommissioning includes the initial planning and transition activities starting on either the effective date
of permanent cessation of operations or upon submittal of the PSDAR or IFMP, whichever occurs first.
The first phase encompasses the activities that take place before the licensee either places the power
reactor into a storage mode or begins major decommissioning activities (as defined in 10 CFR 50.2),
including the transition of the licensing basis to reflect a decommissioning facility. The second
decommissioning phase encompasses the conduct of activities during the storage period or the
undertaking of major decommissioning activities (i.e., decontamination and dismantlement), or some
combination of the two. The third phase consists of the rest of the activities that the licensee undertakes to
reduce the remaining radioactivity at the site to a level that permits release of the site. The amendments to
10 CFR Part 2 (Ref. 20) and 10 CFR Part 51 in the 1996 decommissioning rule pertain to this third phase
of decommissioning.
In addition, Volumes 1 and 2 of Supplement 1 to NUREG-0586, “Generic Environmental Impact
Statement on Decommissioning of Nuclear Facilities” (the Decommissioning GEIS), issued
November 2002 (Ref. 21), as well as the supplemental information to the 1988 decommissioning rule
(53 FR 24018; June 27, 1988), evaluate the environmental impact of the following three
decommissioning methods:
(1)

DECON. The equipment, structures, and portions of the facility and site that contain radioactive
contaminants are promptly removed or decontaminated to a level that permits termination of the
license shortly after cessation of operations. The Decommissioning GEIS found DECON to be an
acceptable decommissioning method.

DG-1347 Revision 1, Page 6

(2)

SAFSTOR. The facility is placed in a safe, stable condition and maintained in that state (safe
storage) until it is subsequently decontaminated and dismantled to levels that permit license
termination. During SAFSTOR, a facility is left intact; however, the fuel has been removed from
the reactor vessel, and radioactive liquids have been drained from systems and components and
then processed. Radioactive decay occurs during the SAFSTOR period, thus reducing the
quantity of contaminated and radioactive material that must be disposed of during
decontamination and dismantlement. The definition of SAFSTOR also includes the
decontamination and dismantlement of the facility at the end of the storage period. The
Decommissioning GEIS found SAFSTOR to be an acceptable decommissioning method.

(3)

ENTOMB. Radioactive systems, structures, and components are encased in a structurally
long-lived substance such as concrete. The entombed structure is appropriately maintained and
kept under continued surveillance until the radioactivity decays to a level that permits termination
of the license. Because most power reactors will have radionuclides in concentrations that exceed
the limits for unrestricted use even after 100 years, this option will generally not be feasible.
However, this option might be acceptable for reactor facilities that can demonstrate that
radionuclide levels will decay to unrestricted use levels in about 100 years.
Entombment is to only be considered as a last resort for decommissioning. The expectation is that
licensees would select this method only under unique decommissioning circumstances.
Entombment would be used only if this option provides more benefit than harm to public health
and safety and the environment and does not create a legacy situation that future generations must
manage. If the ENTOMB method is used, the provisions in 10 CFR Part 20, Subpart E related to
unrestricted or restricted use still apply. The Decommissioning GEIS found ENTOMB to be an
acceptable decommissioning method.

Supplement 1 to NUREG-0586 recognizes that some combination of the first two methods
(DECON and SAFSTOR) would also be an acceptable decommissioning approach. For example, the
licensee could conduct a partial decontamination of the plant followed by a storage period and then
complete the decontamination and dismantlement in preparation for license termination.
As shown in Figure 1, the decommissioning regulations require a licensee to submit written
certification to the NRC within 30 days of determining to permanently shutdown a power reactor. Before
or within 2 years after permanent cessation of operations, the licensee is required to submit a PSDAR. No
major decommissioning activities may be performed until 90 days after the NRC has received both the
PSDAR and the certification that fuel has been permanently removed from the reactor vessel. Major
decommissioning activities are defined as any activity that results in permanent removal of major
radioactive components that permanently modifies the structure of the containment or results in
dismantling components for shipment containing greater-than-Class-C waste. Decommissioning of the
site (including a general license ISFSI) must be completed within 60 years of permanent cessation of
operations unless the NRC approves an extended timeline for decommissioning the facility or the general
license ISFSI in accordance with 10 CFR 50.82(a)(3) or 10 CFR 52.110 (c) when necessary to protect
public health and safety.

DG-1347 Revision 1, Page 7

Figure 1. Simple decommissioning timeline
Decommissioning Funding
The 1996 decommissioning rule changed the licensee’s ability to access the trust funds set aside
for radiological decommissioning under 10 CFR 50.75. The licensee’s ability to use the trust funds set
aside for radiological decommissioning depends on reaching certain milestones in the decommissioning
process. This limitation on the accessibility of the decommissioning funds is designed to ensure that
sufficient funds are always available to place the facility in a safe, stable condition that ultimately leads to
decommissioning and license termination. The licensee may use up to 23 percent of the amount (specified
in 10 CFR 50.75(c)) of the decommissioning trust funds (DTFs) for decommissioning activities before
submitting a site-specific decommissioning cost estimate. Included in this 23 percent is an initial 3 percent
that the licensee can use, even before permanent cessation of operations, for decommissioning planning,
which does not include planning for the management of irradiated fuel. The licensee may use the
remaining 20 percent for active decommissioning activities (DECON) or to ready the facility for longterm storage (SAFSTOR). This 20 percent may be used only after the licensee has submitted the
certifications specified by 10 CFR 50.82(a)(1) or 10 CFR 52.110(a), and after the 90-day period following
submission of the PSDAR. The remaining DTFs would be available for use for decommissioning
activities, consistent with 10 CFR 50.82(a)(8)(i) and 10 CFR 52.110(h)(1), after the licensee submits a
site-specific decommissioning cost estimate to the NRC. In 10 CFR 50.82(a)(8)(iii) and 10 CFR
52.110(h)(3), the NRC requires the licensee to submit a site-specific decommissioning cost estimate
within 2 years after permanent cessation of operations, if not already submitted.

DG-1347 Revision 1, Page 8

The following is a list of documents containing information that may help licensees develop
site-specific decommissioning cost estimates:
•

NUREG/CR-0672, “Technology, Safety and Costs of Decommissioning a Reference Boiling
Water Reactor Power Station,” (including Addenda 1–4) (Ref. 22)

•

NUREG/CR-0130, “Technology, Safety and Costs of Decommissioning a Reference
Pressurized Water Reactor Power Station,” (including Addenda 1–4) (Ref. 23)

•

NUREG/CR-5884, “Revised Analyses of Decommissioning for the Reference Pressurized
Water Reactor Power Station” (Ref. 24)

•

NUREG/CR-6174, “Revised Analyses of Decommissioning for the Reference Boiling Water
Reactor Power Station” (Ref. 25)

•

NUREG-0586, “Generic Environmental Impact Statement on Decommissioning of Nuclear
Facilities”

The NRC staff recognizes that, during the planning process for decommissioning while in
operation, the licensee must consider activities related to the storage of spent fuel. Accordingly, the
licensee may choose to commingle the funding for spent fuel planning, maintenance, and storage required
by 10 CFR 50.54(bb) in the same trust fund that it uses for radiological decommissioning. However,
funds set aside for decommissioning planning must not be used for spent fuel management planning
during operation; this is not allowed without an exemption and these funds must remain separate and
accounted for as such unless approved otherwise. The licensee must be able to identify and track the
amounts in the trust fund applicable to radiological decommissioning activities and the amounts set aside
for spent fuel management and other uses.
During operation, unless otherwise approved through a regulatory exemption, funds collected and
set aside in the DTF for decommissioning are exclusively for radiological decommissioning as defined in
10 CFR 50.2. Therefore, expenses that these funds can be used for include expenses directly related to
removing a facility or site safely from service and reducing residual radioactivity to a level that permits
license termination and release of the property for restricted or unrestricted use. These expenses may
include:
•

Expenses directly related to activities that satisfy the definition of “decommission” in
10 CFR 50.2;

•

Expenses directly related to decommissioning planning and execution including consulting and
paper studies, environmental assessments, engineering, and licensing activities;

•

Expenses directly related to the decontamination and dismantling of systems, structures, and
components (SSCs) (labor, materials, and equipment), including disposal of waste generated from
decontamination and dismantling activities;

•

Expenses directly related to the disposal of contaminated SSCs (labor, materials, and equipment);

•

Expenses directly related to radiological soil remediation (labor, materials, and equipment),
including disposal of this waste;

DG-1347 Revision 1, Page 9

•

Expenses directly related to overhead costs (i.e., emergency planning and security) and energy
(e.g., electricity and fuel) used in support of decommissioning activities and to maintain the
safety and security of the site;

•

Expenses directly related to undistributed costs such as property taxes and nuclear insurance
required while in decommissioning until the license terminated;

•

Expenses directly related to improving the efficiency and effectiveness of the decommissioning
process (demonstrated through a cost-benefit analysis to reduce expenses and preserve the
decommissioning fund), and to improve the safety and security of the site.

While in operation, the licensee should not reallocate or use the amount set aside for radiological
decommissioning, as required by 10 CFR 50.75, for (1) the maintenance and storage of spent fuel in the
spent fuel pool (SFP), (2) the design, construction, or operation of spent fuel storage facilities on the
reactor site, or (3) other activities not directly related to radiological decontamination or dismantlement of
the facility or site. To emphasize, an exemption is required to spend DTF funds on anything other than
radiological decommissioning activities except as allowed in 10 CFR 50.82 or 10 CFR 52.110.
Consideration of International Standards
The International Atomic Energy Agency (IAEA) works with member states and other partners to
promote the safe, secure, and peaceful use of nuclear technologies. The IAEA develops Safety
Requirements and Safety Guides for protecting people and the environment from harmful effects of
ionizing radiation. This system of safety fundamentals, safety requirements, safety guides, and other
relevant reports, reflects an international perspective on what constitutes a high level of safety. To inform
its development of this RG, the NRC considered IAEA Safety Requirements and Safety Guides pursuant
to the Commission’s International Policy Statement (Ref. 26) and Management Directive and Handbook
6.6, “Regulatory Guides” (Ref. 27). The following IAEA Safety Requirements and Guides were
considered in the update of this RG:
•

IAEA General Safety Requirements Part 6, “Decommissioning of Facilities,” issued July 2014
(Ref. 28)

•

IAEA Safety Guide WS-G-2.1, “Decommissioning of Nuclear Power Plants and Research
Reactors,” issued December 1999 (Ref. 29)

•

IAEA Safety Guide WS-G-2.2, “Decommissioning of Medical, Industrial and Research
Facilities,” issued December 1999 (Ref. 30)

•

IAEA Safety Guide WS-G-2.4, “Decommissioning of Nuclear Fuel Cycle Facilities,” issued
June 2001 (Ref. 31)

•

IAEA Safety Guide WS-G-5.2, “Safety Assessment for the Decommissioning of Facilities
Using Radioactive Material,” issued February 2009 (Ref. 32)

DG-1347 Revision 1, Page 10

C. STAFF REGULATORY GUIDANCE
This section provides detailed descriptions of the methods, approaches, or data that the NRC staff
considers acceptable for meeting the requirements of 10 CFR Part 50 and 10 CFR Part 52 for
decommissioning of nuclear power reactors.
1. Certification of Permanent Cessation of Operations
As stated in 10 CFR 50.82(a)(1)(i) and 10 CFR 52.110(a)(1), when a licensee has determined to
permanently cease operations at a nuclear power reactor unit, it must submit a written certification to the
NRC within 30 days of that determination. Note that the rule requires the licensee to submit certification
within 30 days of the decision to cease operations rather than within 30 days of actual facility shutdown.
The NRC considers that the 30-day clock starts on the day that the licensee publicly announces the date
that the facility will permanently cease operations. If the facility has already been shut down, the date of
permanent cessation of operations would correspond to the day that the decision is made not to seek to
return to power-generation operation. If the NRC issues an order to permanently cease operations at a
facility, the certification would be required within 30 days of the effective date of the order.
According to 10 CFR 50.4(b)(8) and 10 CFR 52.3(b)(8), the certification must state the date on
which power-generation operations permanently ceased, or will permanently cease, and must be
submitted under oath or affirmation. This certification is deemed to have already been submitted for
licensees whose licenses were permanently modified before the effective date of the 1996
decommissioning rule to allow for possession, but not operation, of the facility, as stated in
10 CFR 50.82(a)(1)(iii). Following submission of the certification for permanent cessation of operations,
the facility license continues in effect beyond the expiration date until the NRC notifies the licensee in
writing that the license has been terminated (in accordance with 10 CFR 50.51(b) and 10 CFR 52.109). A
permanently shutdown facility does not require an amendment to extend the expiration date of the
operating license.
The NRC deems receipt of the certification of permanent cessation of operations as a
commitment by the licensee to cease operations on the specified date. Following submission of the
certification of permanent cessation of operations, or at any time during the decommissioning process, if
the licensee desires to operate the facility again, it must notify the NRC of its intentions in writing. The
NRC would handle review and approval activities to return the facility to operation on a case-by-case
basis, and the extent of review and approval would depend on the facility status at the time that the
licensee submits a request to reauthorize operation. This prohibition on continuing reactor operation does
not apply to licensees that have only submitted a written notification of the intent to decommission a
facility at some point in the future but have not established or certified the date by which the facility will
permanently cease operations.
2. Certification of Permanent Removal of Fuel
Once the fuel is permanently removed from the reactor vessel, 10 CFR 50.82(a)(1)(ii) and
10 CFR 52.110(a)(2) require the licensee to submit a written certification to the NRC, consistent with the
requirements in 10 CFR 50.4(b)(9) and 10 CFR 52.3(b)(9), stating the date on which the fuel was
permanently removed from the reactor vessel and the disposition of the fuel. For example, the licensee
should state whether the spent fuel was transferred to another 10 CFR Part 50 or 10 CFR Part 52 licensee,
placed in the facility’s SFP, or stored in an ISFSI. This certification must be submitted under oath or
affirmation.

DG-1347 Revision 1, Page 11

Although the regulations may require the licensee to submit the certification of permanent
cessation of operations before it permanently shuts down the facility, the regulations require the licensee
to submit the certification of permanent removal of fuel only after all the fuel has been removed from the
reactor vessel. In 10 CFR 50.2, the NRC defines permanent fuel removal for a nuclear power reactor
facility as “a certification by the licensee to the NRC that it has permanently removed all fuel assemblies
from the reactor vessel.” This certification is deemed to have already been submitted for licensees whose
licenses were permanently modified before the effective date of the 1996 decommissioning rule to allow
for possession, but not operation, of the facility, as stated in 10 CFR 50.82(a)(1)(iii).
There are no requirements on the time interval between the decision to permanently cease
operations and the submittal of the certification of permanent fuel removal. However, until the NRC has
received the certification of permanent fuel removal, the licensee does not qualify for the removal of
those regulatory requirements that are no longer necessary to protect public health and safety resulting
from the nonoperational status of the facility or for a reduction in the fees required by 10 CFR 171.15,
“Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses” (Ref. 33).
The NRC staff expects to receive the certification to permanently cease operations before the
certification of permanent fuel removal, although the staff would also find it acceptable to receive a
combined certification (e.g., if the core had been offloaded before the licensee decided to permanently
shut down the facility). According to 10 CFR 50.82(a)(2) and 10 CFR 52.110(b), when the NRC dockets
both 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 at the facility comes
into effect, the 10 CFR Part 50 or 10 CFR Part 52 license no longer authorizes the operation of the reactor
or emplacement of fuel into the reactor vessel.
3. Irradiated Fuel Management Plan
The regulation in 10 CFR 50.54(bb) requires the licensee to submit, for NRC review and
approval, its plan for the management and funding for management of all spent fuel at the reactor
following permanent cessation of operations until title to, and possession of, the spent fuel is transferred to
the U.S. Department of Energy. This plan is referred to as the IFMP or, alternatively, the spent fuel
management plan. The licensee must submit this plan prior to or within two years following permanent
cessation of operations and before starting to decommission SSCs needed for moving, unloading, and
shipping the spent fuel.
The IFMP must include information on how the licensee intends to manage spent fuel, and the
IFMP must be approved by the NRC before the licensee starts to decommission the SSCs needed for
moving, unloading, and shipping the spent fuel (e.g., the SFP; fuel handling building; or fuel or cask
handling systems, including cranes or lifting equipment). The purpose of the plan, in part, is to show what
physical infrastructure or capabilities are needed for safely managing spent fuel at the site and to describe
how the infrastructure or capabilities will be maintained for the duration of expected spent fuel storage
operations.
The IFMP should discuss where the spent fuel will be stored (i.e., whether in a wet or dry storage
mode). If the licensee has placed or will place the spent fuel in dry storage at a specific license or general
license ISFSI under 10 CFR Part 72, the IFMP should summarize the design of the ISFSI and the dry
storage system that is, or will be, used to store spent fuel. The IFMP may reference design-basis
documents for the ISFSI or dry storage system (e.g., the updated final safety analysis report for a specific
license ISFSI or certificate of compliance (CoC) for the applicable dry storage system design). The IFMP
should specifically include information on which SSCs the facility relies for spent fuel management
during decommissioning, including SSCs needed for the following activities:
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a.

ready retrieval of spent fuel, consistent with the requirements in 10 CFR 72.122(l)

a.

compliance with the applicable regulatory requirements for spent fuel storage and compliance
with the ISFSI license or CoC conditions or technical specifications that involve moving or
unloading a spent fuel storage system, including required actions related to limiting conditions for
operation that involve removal of spent fuel assemblies from the storage system

b.

compliance with the ISFSI license or CoC conditions or technical specifications associated with
implementation of aging management programs for an ISFSI that is in its period of extended
operation, such as inspections, maintenance or repair activities, or corrective actions associated
with the aging management programs

c.

restoration of the facility to a safe condition after a design-basis ISFSI accident

The IFMP should also discuss any other spent fuel management issues considered by the licensee,
including use of dry storage systems that have associated transportation certificates or any contingency
planning that addresses the potential need to handle spent fuel or repair or replace casks or other spent
fuel storage components before the end of ISFSI operations (e.g., potential corrective actions for repairing
or replacing storage system SSCs during the period of extended operation). The IFMP should discuss the
physical infrastructure, expertise, or capabilities that may be necessary and explain how they would be
obtained, if needed. The regulation in 10 CFR 50.54(bb)(3) requires a licensee to identify in the IFMP any
actions for managing spent fuel that would require NRC authorization, such as any necessary exemptions
from applicable regulations or amendments to the 10 CFR Part 50, Part 52, or Part 72 licenses or
amendments to the Part 72 CoC being used by the licensee.
The regulation in 10 CFR 50.54(bb)(4) requires the IFMP to contain the projected cost of
managing spent fuel and discuss how the licensee will provide funding for the management of the spent
fuel following permanent cessation of operations until title to, and possession of, the spent fuel is
transferred to the U.S. Department of Energy. Guidance related to funding for spent fuel management is
found in NUREG/CR-5884 and NUREG/CR-6174.
The regulation at 10 CFR 50.54(bb)(5) requires a licensee to submit to the NRC any changes to
the IFMP as an application for an amendment to its license. In addition, the regulation at 10 CFR
50.54(bb)(6) requires the licensee to retain a copy of the IFMP as a record until termination of the 10 CFR
Part 50 or Part 52 operating license.
4. Post-shutdown Decommissioning Activities Report
Before or within 2 years after permanent cessation of operations, 10 CFR 50.82(a)(4)(i) and 10
CFR 52.110(d)(1) require the licensee to submit a PSDAR to the NRC and to send a copy to the
affected States. RG 1.185 provides additional guidance on the content and level of detail to be included in
the PSDAR. The PSDAR must contain a description of the planned decommissioning activities along
with a schedule for their accomplishment, a discussion whether the environmental impacts associated
with site-specific decommissioning activities will be bounded by appropriate federally issued
environmental review documents, a description of any decommissioning activities whose environmental
impacts will not be so bounded and will be evaluated prior to the performance of the activities, and a sitespecific decommissioning cost estimate, including the projected cost of managing irradiated fuel.
If the licensee identifies decommissioning activities with impacts that are not bounded by previous
federally issued environmental review documents, it should state how it intends to comply with 10 CFR
DG-1347 Revision 1, Page 13

50.82(a)(6)(ii) or 10 CFR 52.110(f)(2). For those decommissioning activities that will occur in the future
such that licensees may not be able to make the definitive conclusion that impacts will be bounded at the
PSDAR stage, identify those activities for which there are unbounded environmental impacts that will be
addressed closer to, but still prior to, the decommissioning activities being undertaken.
5. Public Meeting
Once the NRC receives the PSDAR, it will docket the report and publish a notice of receipt inthe
Federal Register to solicit comments on the PSDAR from the public in accordance with 10 CFR
50.82(a)(4)(ii) and 10 CFR 52.110(d)(2). A copy of the PSDAR will be made available to the public in the
Public Document Room and electronically through the NRC Library on the agency’s Web site at
http://www.nrc.gov/reading-rm/adams. The NRC will schedule a public meeting near the site to discuss
the licensee’s plans for decontamination and dismantlement of the facility, and the decommissioning
timeframe, as well as to hear public comments. To the extent possible, the public meeting should be held
within 90 days of the NRC’s receipt of the licensee’s PSDAR submittal; normally, the NRC will hold the
meeting at least 30 days before the 90-day period ends.
The NRC will publish a notice of this public meeting in the Federal Register and in a place or places
readily available to individuals near the site, such as a local newspaper. The notice will include the date,
time, and location of the meeting and will briefly describe the purpose of the meeting.
Comments received by the NRC staff on the PSDAR will be addressed at the public meeting, and a
question-and-answer period will follow the presentations. The NRC will prepare a written transcript of the
meeting and make it available to the public through the Public Document Room and electronically
through the NRC Library. In addition, the NRC staff’s standard practice for reviewing the PSDAR is to
provide an acknowledgment letter to the licensee that summarizes the staff’s understanding of the
PSDAR, provides highlights from the PSDAR public meeting, and categorizes the stakeholder comments
received on the PSDAR.
The public meeting will be informational and should be chaired by a senior member of the NRC
staff involved in the decommissioning of the facility. During the public meeting, the NRC will invite the
licensee to present its plans for decommissioning the facility. The NRC will offer a representative from
each affected State the opportunity to discuss any Stateregulations or oversight roles that may apply
during decommissioning. Other representatives from the affected States, local officials, and the general
public will be invited to comment on the licensee’s PSDAR.
6. Initial Decommissioning Activities
The licensee may not perform any major decommissioning activities, as defined in 10 CFR 50.2,
until 90 days after the date that the NRC receives the licensee’s PSDAR submittal and until the
certifications of permanent cessation of operations and permanent removal of fuel from the reactor vessel
have been submitted, as stated in 10 CFR 50.82(a)(5) and 10 CFR 52.110(e). The NRC staff may use this
90-day period to conduct any pre-decommissioning inspections necessary to verify that the licensee’s
programs and controls are adequate to ensure that decommissioning activities are conducted safely, and
the health and safety of the public and the environment are protected. After 90 days, the licensee may
proceed with the major decommissioning activities allowed under 10 CFR 50.82 and 10 CFR 52.110
unless the Commission issues an order prohibiting or otherwise prescribing any major decommissioning
activities because of a deficiency in the PSDAR.
Licensees may opt to submit the PSDAR before permanent cessation of operations or permanent
removal of fuel from the reactor vessel to minimize any delay in decommissioning activities resulting

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from the 90-day waiting period. However, licensees must submit certifications for permanent cessation of
operations and permanent removal of fuel before initiating major decommissioning activities.
7. Major Decommissioning Activities
As long as fuel remains in the reactor core, facility modifications under 10 CFR 50.59 and
10 CFR 52.63(b)(2) must be consistent with continued facility operation. Once the licensee certifies that
the facility has permanently ceased operations and that the fuel has been permanently removed from the
reactor vessel, and the 90-day period has passed, major decommissioning activities, as that term is defined
in 10 CFR 50.2, may begin (e.g., permanent removal of major radioactive components). The licensee’s
decommissioning activities are prescribed by the requirements of 10 CFR 50.59, 10 CFR 50.82, and
10 CFR 52.110. In addition, as stated in 10 CFR 50.82(a)(6) and 10 CFR 52.110(f), licensees of
permanently shutdown reactors may not perform any decommissioning activities that would foreclose the
release of the site for possible unrestricted use, would result in significant environmental impacts not
bounded by appropriate federally issued environmental review documents, or would result in there no
longer being reasonable assurance that adequate funds will be available for decommissioning.
The PSDAR must contain a discussion whether the site-specific environmental impacts of the
proposed decommissioning activities will be bounded by appropriate federally issued environmental
review documents, such as (1) the final environmental statement (FES) for the plant’s construction permit
or operating license (as supplemented), (2) the environmental impact statement (EIS) for a combined
operating license, (3) the Decommissioning GEIS and NUREG-1496, “Generic Environmental Impact
Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRC-Licensed
Nuclear Facilities,” issued July 1997 (Ref. 34), (4) supplemental EISs for license renewal or subsequent
license renewal, (5) site-specific environmental assessments for extended power uprates or other license
amendments, (6) programmatic agreements developed during consultations under Section 106 of the
National Historic Preservation Act of 1996, as amended (NHPA) (54 United States Code (U.S.C.) 300101
et seq.) (Ref. 35), and (7) biological assessments or biological opinions issued as part of Section 7
consultations under the Endangered Species Act of 1973 (ESA) (16 U.S.C. 1531 et seq.) (Ref. 36). The
report must describe any decommissioning activities whose environmental impacts will not be so bounded
and the anticipated schedule for conducting any such activities.
For most resource areas, the Decommissioning GEIS provides generic conclusions about
environmental impacts during decommissioning. Licensees should ensure that the predicted site-specific
environmental impacts of the proposed decommissioning activities fall within the bounding estimates,
descriptions, and assumptions stated in the Decommissioning GEIS or are otherwise considered in and
bounded by other appropriate federally issued environmental review documents. Licensees should also
provide a discussion of the reasons for the conclusions reached with respect to bounded impacts. If relying
on the Decommissioning GEIS, licensees should pay particular attention to the environmental issues for
which the NRC staff was unable to reach a generic impact conclusion. For these environmental issues, the
licensee would need to either conduct a site-specific assessment or determine whether another federally
issued environmental review document provides an adequate site-specific bounding environmental impact
assessment.
For example, the NRC staff was unable to reach a generic environmental impact determination
for threatened and endangered species in the Decommissioning GEIS. For this resource area, the licensee
can obtain a current list of threatened, endangered, proposed, and candidate species that could occur on
the site from the U.S. Fish and Wildlife Service’s (FWS’s) online database, “Information for Planning
and Consultation: Environmental Conservation Online System,” and, if appropriate, by coordinating with
the appropriate FWS or National Marine Fisheries Service (NMFS) office. In addition, the licensee should
determine if any protected habitats, such as designated critical habitat or Essential Fish Habitat, occur at
DG-1347 Revision 1, Page 15

or near the site. In many cases, the federally listed species, designated critical habitat, and Essential Fish
Habitat would have changed since the NRC staff engaged in the last consultation under the Endangered
Species Act or the Magnuson–Stevens Fishery Conservation and Management Act (16 U.S.C. 1801 et
seq.) (Ref. 37). For any federally listed species, designated critical habitat, or Essential Fish Habitat on or
near the site, the licensee should determine what the impacts from planned decommissioning activities
would be to those species and habitats, coordinating, as appropriate, with FWS and NMFS.
If planned decommissioning activities may affect any federally listed species, designated critical
habitat, or Essential Fish Habitat, the licensee should determine whether the impacts to those species or
habitats were discussed in any appropriate federally issued environmental review document. If the
impacts from decommissioning or similar activities were not described or bounded by appropriate
federally issued environmental review documents, the licensee should contact FWS or NMFS, as needed,
to determine whether a planned decommissioning activity may result in a “take,” as defined in the ESA,
of federally listed species or adversely affect Essential Fish Habitat. If a “take” could occur, then the
licensee could rely upon any additional environmental reviews required by the FWS or NMFS under the
ESA. Additionally, if a “take” could occur or if Essential Fish Habitat could be adversely affected, then
the licensee could submit a license amendment request or an exemption request to the NRC (thus creating
an agency action for the NRC to initiate consultation under the ESA or the Magnuson–Stevens Fishery
Conservation and Management Act, as appropriate), or the licensee could take any other appropriate
measures to ensure that impacts are bounded by environmental review documents and, therefore, that the
licensee remains in compliance with 10 CFR 50.82(a)(6)(ii) or 10 CFR 52.110(f)(2). The staff notes that
the take of any federally listed species by any person subject to the jurisdiction of the United States is
prohibited by Section 9 of the ESA.
The NRC was also unable to reach a generic conclusion for the environmental justice issue in the
Decommissioning GEIS. If the licensee is unable to determine or demonstrate that the impacts for a
decommissioning activity are bounded by the environmental justice impacts described in a federally
issued environmental review document or for other impact issues evaluated in the Decommissioning
GEIS, the licensee should consider following the guidance discussed below on what to do if unable to
comply with the requirement in 10 CFR 50.82(a)(6)(ii) or 10 CFR 51.110(f)(2).
The comparison to impacts in other appropriate federally issued environmental review documents
should recognize the unique nature of the site and any changes to the site that might have occurred since
the previous environmental document was issued. For example, the listed species that may occur or that
the demographic composition of minority and low-income populations living near the site might have
changed since the publication of the previous documents.
If unable to comply with the requirements of 10 CFR 50.82(a)(6)(ii) or 10 CFR 52.110(f)(2), the
licensee could take one of several actions, including the following:
a.

submit a license amendment request for prior NRC approval of the decommissioning activity to
address those impacts that are not bounded by appropriate federally issued environmental review
documents.

b.

submit an exemption request under 10 CFR 50.12 or 10 CFR 52.7 from 10 CFR 50.82(a)(6)(ii) or
10 CFR 52.110(f)(2), respectively, to request that the regulation not apply in certain
circumstances.

c.

change its plans to avoid the decommissioning activities that would likely result in significant
environmental impacts not bounded by appropriate federally issued environmental review
documents.
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If a licensee chooses to submit a license amendment or exemption request, the NRC would
prepare an environmental assessment, or other appropriate environmental document, as part of its review
and would complete any necessary environmental consultations to resolve any issues regarding
unbounded environmental impacts before the decommissioning activity takes place.
Licensees should maintain documentation of their analyses showing compliance with
10 CFR 50.82(a)(6)(ii) or 10 CFR 52.110(f)(2) for any identified environmental impacts from
decommissioning activities.
For decommissioning activities that would result in significant environmental impacts not
previously reviewed, failing to change the decommissioning activities prior to performing them so that
they will not result in significant environmental impacts not previously reviewed or failing to submit, and
have approved, either a license amendment request or an exemption request prior to performing the
decommissioning activities, may potentially constitute a violation of 10 CFR 50.82(a)(6) or
10 CFR 52.110(f)(2).
8. Technical Regulations and Requirements
8.1 Technical Specifications
The NRC regulations explicitly extend requirements for specific portions of the technical
specifications that will cover decommissioning activities. Decommissioning technical specifications will
be developed on a case-by-case basis, as stated in 10 CFR 50.36(c)(6). The licensee will review the
operational technical specifications and determine which specifications no longer apply during
decommissioning and which ones should remain in force. The licensee will make the appropriate
submittals to the NRC to request changes to the technical specifications as required by the regulations.
8.2 Effluent Releases and Reporting
Technical specifications for effluent releases are specified in 10 CFR 50.36a, “Technical
Specifications on Effluents from Nuclear Power Reactors.” In addition to complying with the applicable
provisions of 10 CFR 20.1301, “Dose Limits for Individual Members of the Public,” the licensee would
develop technical specifications that require it to establish and follow operating procedures for the control
of effluents as outlined in 10 CFR 50.34a(c), when applicable, and to maintain and use the radioactive
waste system under 10 CFR 50.34a(a). This applies when the plant is operating as well as during
decommissioning. The regulation in 10 CFR 50.36a(a)(1) requires the licensee to retain these operating
procedures as a record until the NRC terminates the license and to keep all superseded revisions to the
procedures for 3 years from the date they were superseded.
Licensees must continue to meet the requirements of 10 CFR 50.36a(a)(2) to submit an annual
report to the NRC that specifies the quantity of each of the principal radionuclides released from the
facility to unrestricted areas in liquid and gaseous effluents during the previous 12 months. The report
must include any other information that the NRC may need to estimate the maximum potential annual
radiation doses to the public resulting from effluent releases. The time between submittal of the reports
must be no longer than 12 months. If quantities of radioactive materials released during the reporting
period are significantly greater than the design objectives for the facility when it was operating or are
outside the scope of what would be expected based on the ongoing decommissioning activities at the site,
the report must specifically address the reasons for this variation.

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The NRC will use these reports, along with any additional information provided, to require the
licensee to take actions that the agency deems appropriate to control and monitor offsite liquid and
gaseous effluent releases. Licensees may continue to use the values in Appendix I, “Numerical Guides for
Design Objectives and Limiting Conditions for Operation To Meet the Criterion ‘As Low as is
Reasonably Achievable’ for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor
Effluents,” to 10 CFR Part 50. Appendix I provides numerical guidance for meeting the requirements for
radioactive materials in effluents released to unrestricted areas.
8.3 The Maintenance Rule
The maintenance rule (10 CFR 50.65, “Requirements for Monitoring the Effectiveness of
Maintenance at Nuclear Power Plants”) requires licensees to monitor the performance or condition of
certain SSCs that could affect safety. For licensees that have submitted the certifications for cessation of
operations and permanent removal of fuel from the reactor, as specified in 10 CFR 50.82(a)(1) and 10
CFR 52.110(a), this requirement applies only to the extent that the licensee monitors the performance or
condition of the SSCs associated with the storage, control, and maintenance of spent fuel in a safe
condition within the SFP. The monitoring activities must be sufficient to provide reasonable assurance
that SSCs related to the storage of spent fuel are capable of fulfilling their intended functions, as specified
in 10 CFR 50.65(a)(1).
8.4 Final Safety Analysis Report Content
The final safety analysis report (FSAR), or other comparable document, provides a
licensing-basis document for use in the evaluation of licensee activities under 10 CFR 50.59. The licensee
must update and periodically adjust this licensing-basis document to cover decommissioning activities.
According to 10 CFR 50.71(e)(4), nuclear power facilities that have submitted certifications for
permanent cessation of operations and removal of fuel must file subsequent revisions that update the
FSAR and its associated licensing basis with the NRC at least every 24 months. Specific sections of the
FSAR that the licensee should continue to update periodically during decommissioning include those
described below.
8.4.1 Facility Description
The licensee must describe, primarily in the PSDAR, the facility’s status at the time the facility is
shut down and before any decommissioning or dismantlement activities occur and make the
accompanying changes to the FSAR. The licensee should update only the descriptions of those facility
SSCs that are included in the technical specifications or that directly affect the safe storage of irradiated
fuel. However, during decommissioning, general updates to the FSAR to reflect the current condition of
SSCs that were in the operating plant version of the FSAR are needed to maintain an overall
understanding of the configuration basis of the plant. The updates should identify changes as systems are
decontaminated, inactivated, mothballed for later use, or reconfigured to support changes to their previous
functions. Even though SSCs may no longer have a safety function, documenting the status or design
function of these SSCs while the plant is in a decommissioning phase has an overall safety benefit.
For example, a cooling water system may no longer be required to provide a safety-related heat
sink. However, if the system continues to be functional, operation of a wrong valve or a system fault or
breakage, or misalignment of interfaces to this system, could result in accidents such as flooding,
personnel injury, or flushing of potentially radioactive material into an uncontaminated location. As a
minimum, the licensee should maintain a level of detail in the FSAR that provides the status of all the
operating licensing-basis SSCs until the systems are no longer mechanically or electrically active, are no
longer radioactively contaminated, have no fluid content or other materials that require special handling
DG-1347 Revision 1, Page 18

considerations, or have been physically removed during dismantlement. System disablement for
mechanical and electrical systems should rely on physical controls difficult to reverse, such as removal of
piping spool pieces and electrical breakers, rather than valve and breaker positioning and tagging.
8.4.2 Licensee Organization
The FSAR or comparable document should describe the licensee’s corporate and site organization
during decommissioning. It should describe the structure, functions, and responsibilities of the onsite
organization established to decommission the facility, including the use of a decommissioning general
contractor if applicable.
8.4.3 Radioactive Waste Management
The scope remains the same as in the operating-phase FSAR.
8.4.4 Radiation Protection
The scope remains the same as in the operating-phase FSAR.
8.4.5 Conduct of Operations
The scope remains the same as in the operating-phase FSAR.
8.4.6 Site Characteristics
The licensee should update any sections of the FSAR that discuss the site characteristics that
support the safe storage of fuel or that could directly affect the design basis of the facility.
8.4.7 Accident Analysis
The licensee should evaluate any new or different design-basis accidents identified during
10 CFR 50.59 evaluations of the changes planned during decommissioning and include them in FSAR
updates, if appropriate (e.g., consideration of accidents involving a newly installed gas pipeline within or
near the facility). Conversely, as decommissioning progresses, the licensee may remove any design-basis
accidents that are no longer possible from the FSAR or comparable document (e.g., the design basis of a
facility that has transferred its spent fuel from the SFP to an ISFSI would be significantly changed;
therefore, the licensee should update the FSAR to reflect this change).
8.5 Record Retention Requirements
Nuclear power reactor licensees that have certified that they have ceased operations and
permanently removed the fuel from the reactor vessel can eliminate records associated with SSCs that no
longer serve any NRC-regulated function. This record disposal is allowed as long as appropriate change
mechanisms, such as the 10 CFR 50.59 evaluation process or NRC-approved technical specification
changes, are used to assess the removal of those records to determine that elimination of the records will
not adversely impact public health and safety, and there are no other site-specific requirements requiring
retention of certain records, such as a Commission Order.
The records subject to removal are associated with SSCs that had been important to safety during
power operation or operation of the SFP but can no longer cause an event, incident, or condition that
would adversely impact public health and safety, as evidenced by their appropriate removal from the
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licensing-basis documents. If the SSCs no longer have the potential to cause these scenarios, it is
reasonable to conclude that the records associated with these SSCs would not be necessary to assist the
NRC in determining compliance and noncompliance, taking action on possible noncompliance, and
examining facts following an incident. Therefore, retention of such records would not serve the
underlying purpose of the recordkeeping regulations.
The following regulations ensure that records associated with SSCs will be captured, indexed,
and stored in an environmentally suitable and retrievable condition: 10 CFR 50.59(d)(3);
10 CFR 50.71(c); 10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants,”
General Design Criterion 1, “Quality Standards and Records”; and 10 CFR Part 50, Appendix B, “Quality
Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Criterion XVII, “Quality
Assurance Records.” Although licensees will retain the records required by their license as the plant
transitions from operating conditions to a fully decommissioned state, plant dismantlement will obviate
the regulatory and business need for maintenance of most records.
As the SSCs already removed from the licensing basis are subsequently dismantled and as the
need for the associated records is, on a practical basis, eliminated, licensees can dispose of the records
associated with SSCs and historical activities that are no longer relevant and thereby eliminate the
associated regulatory and economic burdens of creating alternative storage locations, relocating records,
and retaining irrelevant records. Considering the content of these records, their elimination on an
advanced timetable has no reasonable potential of presenting any undue risk to public health and safety.
In addition, upon dismantlement of the affected SSCs, the records have no functional purpose relative to
maintaining the safe operation of the SSCs, maintaining conditions that would affect the ongoing health
and safety of workers or the public, or informing decisions related to nuclear safety.
In addition, the NRC amended the decommissioning rule to change the portion of
10 CFR 72.72(d) that requires records for spent fuel in storage to be kept in duplicate for the ISFSI. The
change allows such records to be stored in a single location as long as an NRC-approved quality
assurance program (QAP) controls the record storage location. Specifically, 10 CFR 72.140(d) states that
the NRC will accept a QAP that the agency has approved as meeting the applicable requirements of
10 CFR Part 50, Appendix B, as satisfying the requirements of 10 CFR 72.140(b) for establishing an
ISFSI QAP; however, the licensee must also meet the recordkeeping provisions of 10 CFR 72.174,
“Quality Assurance Records.” This change will not affect the record content, retrievability, or retention
requirements in 10 CFR 72.72, “Material Balance, Inventory, and Records Requirements for Stored
Materials,” or 10 CFR 72.174.
In making these recordkeeping changes, the NRC determined that the process and procedures that
will be used to store the ISFSI records (i.e., in accordance with the QAP at a facility designed for
protection against degradation mechanisms such as fire, humidity, and condensation) will help ensure that
the licensee will adequately maintain the required spent fuel information. Therefore, changes that result
from the duplicate record requirement of 10 CFR 72.72(d) will not affect public health and safety and will
not endanger life or property. In addition, allowing the ISFSI spent fuel records to be stored in the same
manner as that of other quality assurance records for the nuclear facility allows greater efficiency in the
storage of all records once the facility enters the final stages of decommissioning, whereby only the ISFSI
facility will remain after license termination. Requiring a separate method for the storage of certain ISFSI
quality assurance records diverts resources from decommissioning activities.
8.6 Fire Protection Requirements
The fire protection regulations in 10 CFR 50.48(f) require licensees that have certified the
permanent cessation of operations and removal of fuel from the reactor vessel to maintain a fire protection
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program to address the potential for fires that could result in a radiological hazard. The objectives of the
fire protection program delineated in 10 CFR 50.48(f)(1) are to (1) reasonably prevent such fires from
occurring, (2) rapidly detect, control, and extinguish fires that could result in a radiological hazard, and
(3) minimize the risk of fire-induced radiological hazards to the public, environment, and plant personnel.
Further, 10 CFR 50.48(f)(2) requires licensees to assess the fire protection program on a regular
basis and revise it, as needed, throughout the various stages of facility decommissioning. The
requirements of 10 CFR 50.48(f)(3) permit licensees to make changes to the fire protection program
without NRC approval if these changes do not reduce the effectiveness of fire protection for facilities,
systems, and equipment that could result in a radiological hazard, taking into account the conditions and
activities of decommissioning at the facility. RG 1.191, “Fire Protection Program for Nuclear Power
Plants during Decommissioning and Permanent Shutdown,” presents additional guidance.
8.7 Certified Fuel Handler Staffing and Management Role
The requirements of 10 CFR 50.51(b) state that 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, 10 CFR 50.51(b) requires the licensees to
(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.
To comply with these requirements, licensees should designate one or more individuals to
perform the following key functions during decommissioning: (1) safe conduct of decommissioning
activities, (2) safe handling and storage of spent fuel, (3) response to emergencies, and (4) command and
control over functions (1) – (3). To perform these key functions, the decommissioning staff should have
training, knowledge, and understanding of the following:
a. radiological safety principles and monitoring
b. facility/system design and function
c. facility administrative and safety procedures (i.e., normal, abnormal, and emergency
procedures,accident analysis, and the facility’s emergency plan), as appropriate for the
current plant status
d. facility license
e. content, bases, and importance of the facility’s technical specifications
f.

thermodynamics, heat transfer, fluid mechanics, electrical theory, and mechanical
components operation as related to monitoring, handling, storage, and cooling of nuclear
fuel

Furthermore, the decommissioning staff should be able to perform the following additional functions:
a. shift turnover

DG-1347 Revision 1, Page 21

b. shift recordkeeping
c. removal and return of equipment to service
d. watch standing activities
e. monitoring, handling, storage, and cooling of nuclear fuel
f.

response to emergencies

The NRC staff considers these qualifications to be met by individuals who are designated as
Certified Fuel Handlers (CFHs). Such an individual can provide reasonable assurance that a licensee will
meet the requirements of 10 CFR 50.51(b) for a permanently shut down and defueled reactor.
A CFH is currently defined in 10 CFR 50.2 as an NLO who has qualified in accordance with a
fuel handler training program approved by the Commission, for a nuclear power reactor facility. The
NRC staff has added a voluntary alternative definition that states that a CFH can also be an NLO who has
qualified in accordance with a fuel handler training program that meets the requirements for non-licensed
operators under 10 CFR 50.120, and is responsible for decisions regarding the key decommissioning
functions described above. Use of the voluntary alternative definition provides specific requirements on
the quality of the CFH training program and details the CFH’s responsibilities.
Safe Conduct of Decommissioning Activities
The training and responsibilities of the CFH support the safe conduct of decommissioning
activities at a facility that has permanently ceased operations. Specifically, the NRC staff has found that
use of the systems approach to training (SAT), as defined in 10 CFR 55.4, and the use of
10 CFR 50.120(b)(3) are appropriate and applicable for the training of NLOs for nuclear power reactors
during the decommissioning process; this includes those NLOs who are also qualified as CFHs. A
systems approach to training includes a systematic analysis of the jobs to be performed, and evaluation
and revision of the training based on the performance of the trained personnel in the job setting.
Accordingly, as plant conditions change (i.e., the job setting changes), training programs will be revised
to reflect these changes. These revisions could include the development of new programs, such as the
CFH training and retraining program, or the elimination of obsolete programs. However, the process also
ensures that the modification of the program to reflect the changed environment is performed in an
orderly fashion. If a decommissioning plant decides to make some or all existing training programs
unnecessary, the licensee would obtain relief from these requirements by applying for an exemption
eliminating or modifying the affected programs.
Safe Handling and Storage of Spent Fuel
A CFH is also responsible for decisions related to the safe handling and storage of spent fuel at a
decommissioning facility. In addition to the overall safety of any decommissioning-related activities at
the facility, the CFH is intended to be the on-shift licensee representative who is responsible for safe fuel
handling operations and to ensure the safe maintenance and storage of spent fuel.
Response to Emergencies
The role of the CFH in determining actions needed in response to an emergency that could affect
plant operations is significant. During emergency conditions, as discussed in 10 CFR 50.54(x)
and 10 CFR 73.55(p), a licensee may take reasonable action that departs from a license condition or a
DG-1347 Revision 1, Page 22

technical specification to protect the public health and safety or, for severe weather emergencies, to
protect the health and safety of security force personnel, when no action consistent with license conditions
or technical specifications that can provide adequate or equivalent protection is immediately apparent.
These regulations serve to ensure that the emergency action decisions that are necessary to protect public
health and safety, or the health and safety of security force personnel, are made by an individual who has
both the requisite knowledge and plant experience. For a permanently shutdown and defueled
reactor, the regulations require that such actions may only be approved, at a minimum, by a licensed
senior operator or a CFH, as these individuals have the requisite knowledge and plant experience to
evaluate plant conditions and make such emergency decisions.
Command and Control
At a decommissioning facility, the shift manager is often the senior technical position on site
and typically has overall command and control responsibilities for the three functional capabilities
discussed above. Because a CFH is also required to have training on, and is responsible for,
decisions on these three functional capabilities, the shift manager is typically also qualified as a CFH. Due
to the management responsibilities of the shift manager/CFH, he or she may also be one of
the responsible parties to meet the communication requirements in 10 CFR 73.55(j) related to ensuring
effective command and control during both normal and emergency situations, as well as to support
security personnel.
Staffing
In response to license amendment requests from decommissioning licensees, the NRC staff has
approved changes to the minimum levels for staff on shift in the administrative controls section of the
plant technical specifications. These amendments have each involved replacing the SRO and RO
positions with one CFH and one NLO, respectively, to perform activities involving the functions
discussed above. The NRC staff recognizes that these prior approvals have addressed only a limited
number of staffing scenarios that could be encountered at a decommissioning reactor, and have generally
been for a single unit plant with one SFP.1
As such, adequate staffing levels are expected to vary based on (1) the number of reactor units
that are permanently shut down on site; (2) if any operating reactor units are on site; (3) how many active
SFPs are on site; (4) whether and when all spent fuel has been relocated to an ISFSI; and/or (5) the
organizational structure approved in the license. As noted in 10 CFR 50.51(b)(2), the licensee shall
conduct its activities in accordance with its license. In some instances, the licensee might wish to submit a
license amendment request to set appropriate staffing levels that meet 10 CFR 50.51(b).
8.8 Changes to Emergency Planning, Physical Security, and Quality Assurance Requirements
The NRC does not require or expect details in the PSDAR on the radiation protection plan, the
emergency plan, the security plan, or the quality assurance plan related to decommissioning; however,
this information may be required in periodic updates to the FSAR, the QAP, the emergency plan, or other
documents applicable to decommissioning. In addition, several of these areas undergo significant changes
throughout the decommissioning process and may be captured under different regulatory processes such
as license amendments or exemptions.

1

On August 1, 2014, the NRC approved the Safe Storage Shift Manager/Certified Fuel Handler Training
Program for the San Onofre Nuclear Generating Station, Units 2 and 3 (ADAMS Accession No.
ML13268A165).

DG-1347 Revision 1, Page 23

9. Changes to the PSDAR
The regulation at 10 CFR 50.82(a)(7) or 10 CFR 52.110(g), as appropriate, requires the licensee
to notify the NRC, in writing with a copy to the affected States, before it performs any decommissioning
activity that could be considered inconsistent with, or a significant schedule change from, the planned
decommissioning activities or schedules described in the PSDAR, including changes that significantly
increase the decommissioning cost. Changes to the PSDAR may be in the form of a written letter to the
NRC describing the change or may be an actual revision to the PSDAR.
The NRC staff will use changes to the milestone schedule provided in the PSDAR to schedule
inspections of the licensee’s activities and ensure that the licensee is conducting decommissioning
safely and in accordance with the applicable regulatory requirements. Examples of changes in activities
and schedule include, but are not limited to, changing from long-term storage (SAFSTOR) to active
dismantlement (DECON), changing the method used to remove the reactor vessel or steam generators
from cutting and segmenting to intact removal, or changing the schedule to affect major milestones such
as shortening the overall term to complete decommissioning. Licensees do not need to report changes
related to the removal of SSCs that are not contaminated or in the immediate proximity of contaminated
systems that could result in a worker dose.
10. Use of Funds
The regulation at 10 CFR 50.75(f)(2) requires licensees at or about 5 years before the projected
end of operations to submit a preliminary site-specific decommissioning cost estimate that includes an upto-date assessment of the major factors that could affect the cost to decommission. Prior to or within 2
years following permanent cessation of operations, 10 CFR 50.82(a)(4)(i) and 10 CFR 52.110(d)(1)
require licensees to submit a PSDAR, which must contain a site-specific decommissioning cost estimate.
Additionally, 10 CFR 50.54(bb) requires licensees to submit an IFMP, including the projected cost of
managing irradiated fuel, prior to or within two years following permanent cessation of operations.
The regulation at 10 CFR 50.82(a)(8)(ii) and 10 CFR 52.110(h)(2) allows the licensee to use
3 percent of the generic amount of the decommissioning funds specified in 10 CFR 50.75(c) for
decommissioning planning, and such amount may be expended during the operating life of a plant
without any requirement for written notice to be made. Appropriate activities for the use of the initial
3 percent of the decommissioning funds include engineering design development, work package
preparation, and licensing activities to transition the licensing basis from operations to decommissioning.
Activities that would not be appropriate for the use of these planning funds include decontamination and
dismantlement activities, draining of systems, removal of filters, projects designed to demonstrate the
feasibility of a particular decommissioning activity, and spent fuel management planning. As an example,
the decontamination of a building that is no longer in use and would ultimately have to be decontaminated
before license termination is not an appropriate use of planning funds.
After the licensee has submitted the certifications required by 10 CFR 50.82(a)(1) or
10 CFR 52.110(a), and 90 days after the NRC has received the PSDAR, which includes a site-specific
decommissioning cost estimate, the licensee may use an additional 20 percent of the decommissioning
funds prescribed in 10 CFR 50.75(c). The withdrawals may not adversely affect the licensee’s ability to
fully fund the decommissioning trust. The licensee must ensure the availability of funds to ultimately
release the site and terminate the license.
The licensee is prohibited from using the remaining 77 percent of the decommissioning funds
until it submits a site-specific decommissioning cost estimate to the NRC. The licensee must submit this
estimate prior to or within 2 years following permanent cessation of operations with the PSDAR.
DG-1347 Revision 1, Page 24

Site-specific decommissioning cost estimates should include an outline of the expected costs for activities
specified in the PSDAR. See Regulatory Guide 1.185, “Standard Format and Content for Post-Shutdown
Decommissioning Activities Report,” for further information on the expected level of detail. See RG
1.159, “Assuring the Availability of Funds for Decommissioning Nuclear Reactors,” for guidance on
estimating the amount of funds for decommissioning and methods acceptable for demonstrating financial
assurance.
Licensees may provide site-specific decommissioning cost estimates sooner than 2 years after
permanent cessation of operations. For licensees that submitted a preliminary site-specific
decommissioning cost estimate about 5 years before the projected end of operations, the licensee could
expand and update the preliminary estimate and submit it as the site-specific decommissioning cost
estimate. The licensee could also submit the site-specific decommissioning cost estimate with the
PSDAR. If the licensee submits the site-specific decommissioning cost estimate with the PSDAR, it
should appropriately identify it as a site-specific decommissioning cost estimate. This approach would
eliminate the 23-percent hold point for spending the decommissioning funds so long as the licensee has
submitted the certifications required by 10 CFR 50.82(a)(1) or 10 CFR 52.110(a). Licensees that plan to
begin major decommissioning activities shortly after permanent cessation of operations should consider
an early submission of the site-specific decommissioning cost estimate with the PSDAR.
If the licensee’s PSDAR specifies a delayed completion of decommissioning, the licensee must
provide a means of adjusting cost estimates and associated funding levels over the storage or surveillance
period to ensure that the appropriate amount of funding will be available to terminate the license
(10 CFR 50.82(a)(8)(iv) and 10 CFR 52.110(h)(4)). NUREG-1713 provides additional guidance for sitespecific decommissioning cost estimates. This guidance specifies the level of detail required for the
financial plan to adjust cost estimates and associated funding levels.

DG-1347 Revision 1, Page 25

D. IMPLEMENTATION
The NRC staff may use this regulatory guide as a reference in its regulatory processes, such as
licensing, inspection, or enforcement. However, the NRC staff does not intend to use the guidance in this
regulatory guide to support NRC staff actions in a manner that would constitute backfitting as that term is
defined in 10 CFR 50.109, “Backfitting,” and 10 CFR 72.62, “Backfitting,” and as described in NRC
Management Directive 8.4, “Management of Backfitting, Forward Fitting, Issue Finality, and Information
Requests,” (Ref. 38), nor does the NRC staff intend to use the guidance to affect the issue finality of an
approval under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” The
staff also does not intend to use the guidance to support NRC staff actions in a manner that constitutes
forward fitting as that term is defined and described in Management Directive 8.4. If a licensee believes
that the NRC is using this regulatory guide in a manner inconsistent with the discussion in this
Implementation section, then the licensee may file a backfitting or forward fitting appeal with the NRC in
accordance with the process in Management Directive 8.4.

DG-1347 Revision 1, Page 26

REFERENCES2
1.

U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization
Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” Part 50, Chapter 1,
Title 10, “Energy3.”

2.

CFR, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter 1,
Title 10, “Energy.”

3.

CFR, “Standards for Protection against Radiation,” Part 20, Chapter 1, Title 10, “Energy.”

4.

CFR, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory
Functions,” Part 51, Chapter 1, Title 10, “Energy.”

5.

CFR, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level
Radioactive Waste, and Reactor-Related Greater than Class C Waste,” Part 72, Chapter 1,
Title 10, “Energy.”

6.

CFR, “Financial Protection Requirements and Indemnity Agreements,” Part 140, Chapter 1,
Title 10, “Energy.”

7.

U.S. Nuclear Regulatory Commission (NRC), Regulatory Guide (RG) 1.159, “Assuring the
Availability of Funds for Decommissioning Nuclear Reactors,” Washington, DC.

8.

NRC, RG 1.179, “Standard Format and Content of License Termination Plans for Nuclear Power
Reactors,” Washington, DC.

9.

NRC, RG 1.185, “Standard Format and Content for Post-Shutdown Decommissioning Activities
Report,” Washington, DC.

10.

NRC, RG 1.191, “Fire Protection Program for Nuclear Power Plants during Decommissioning
and Permanent Shutdown,” Washington, DC.

11.

NRC, RG 4.21, “Minimization of Contamination and Radioactive Waste Generation: Life-Cycle
Planning,” Washington, DC.

12.

NRC, RG 4.22, “Decommissioning Planning during Operations,” Washington, DC.

13.

NRC, NUREG-1713, “Standard Review Plan for Decommissioning Cost Estimates for Nuclear
Power Reactors, Final Report,” Washington, DC, December 2004.

14.

NRC, NUREG-1757, “Consolidated Decommissioning Guidance,” Washington, DC.

2

Publicly available NRC published documents are available electronically through the NRC Library under Document
Collections on the NRC’s public Web site at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC’s
Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html.
The documents can also be viewed online or printed for a fee in the NRC’s Public Document Room (PDR) at 11555
Rockville Pike, Rockville, MD. For problems with ADAMS, contact the PDR staff at 301-415-4737 or (800) 397-4209;
fax (301) 415-3548; or e-mail pdr.resource@nrc.gov.

3

The Code of Federal Regulations may be obtained electronically from the U.S. Government Printing Office at:
http://www.gpo.gov/fdsys/browse/collectionCfr.action?collectionCode=CFR

DG-1347 Revision 1, Page 27

15.

CFR, “Packaging and Transportation of Radioactive Material,” Part 71, Chapter 1, Title 10,
“Energy.”

16.

CFR, “Disposal of High-Level Radioactive Wastes in Geologic Repositories,” Part 60,
Chapter 1, Title 10, “Energy.”

17.

CFR, “Licensing Requirements for Land Disposal of Radioactive Waste,” Part 61, Chapter 1,
Title 10, “Energy.”

18.

NRC, NUREG-1537, Parts 1 and 2, “Guidelines for Preparing and Reviewing Applications for
the Licensing of Non-Power Reactors,” Washington, DC, February 1996 (ADAMS Accession
Nos. ML042430055 and ML042430048).

19.

NRC, Interim Staff Guidance Augmenting NUREG-1537, Parts 1 and 2, “Guidelines for
Preparing and Reviewing Applications for the Licensing of Non-Power Reactors,” for Licensing
Radioisotope Production Facilities and Aqueous Homogeneous Reactors, Washington, DC,
October 2012 (ADAMS Accession Nos. ML12156A069 and ML12156A075).

20.

CFR, “Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders,” Part 2,
Chapter 1, Title 10, “Energy.”

21.

NRC, NUREG-0586, “Generic Environmental Impact Statement on Decommissioning of Nuclear
Facilities,” Supplement 1, Volumes 1 and 2, Washington, DC, November 2002 (ADAMS
Accession Nos. ML023470304 and ML042430048).

22.

NRC, NUREG/CR-0672, “Technology, Safety and Costs of Decommissioning a Reference
Boiling Water Reactor Power Station,” Pacific Northwest Laboratory, Richland, WA, June 1980
(Legacy Library Accession No. 8006250171 (including Addendum 1, July 1983, Legacy Library
Accession No. 8308180441; Addendum 2, September 1984, Legacy Library Accession
No. 8410170289; Addendum 3, July 1988, Legacy Library Accession No. 8808120112; and
Addendum 4, February 1991, Legacy Library Accession No. 9102280246)).

23.

NRC, NUREG/CR-0130, “Technology, Safety, and Costs of Decommissioning a Reference
Pressurized Water Reactor Power Station,” Pacific Northwest Laboratory, Richland, WA,
June 1978 (Legacy Library Accession No. 79-9260338 (including Addendum 1, August 1979,
Legacy Library Accession No. 7909260338; Addendum 2, July 1983, Legacy Library Accession
No. 8308170163; Addendum 3, September 1984, Legacy Library Accession No. 8410170293;
and Addendum 4, July 1988, Legacy Library Accession No. 8808120069)).

24.

NRC, NUREG/CR-5884, Volumes 1 and 2, “Revised Analysis of Decommissioning for the
Reference Pressurized Water Reactor Power Station,” Pacific Northwest Laboratory,
Richland, WA, November 1995 (ADAMS Accession No. ML14008A187).

25.

NRC, NUREG/CR-6174, Volumes 1 and 2, “Revised Analyses of Decommissioning for the
Reference Boiling Water Reactor Power Station,” Pacific Northwest National Laboratory,
Richland, WA, July 1996 (ADAMS Accession No. ML14008A186).

26.

NRC, “Nuclear Regulatory Commission International Policy Statement,” Federal Register,
Vol. 79, No. 132, July 10, 2014, pp. 39415-39418.

DG-1347 Revision 1, Page 28

27.

NRC, Management Directive (MD) 6.6, “Regulatory Guides, Washington, DC, May 2, 2016
(ADAMS Accession No. ML18073A170).

28.

International Atomic Energy Agency (IAEA)4 General Safety Requirements Part 6,
“Decommissioning of Facilities,” Vienna, Austria, July 2014.

29.

IAEA Safety Guide WS G-2.1, “Decommissioning of Nuclear Power Plants and Research
Reactors,” Vienna, Austria, December 1999.

30.

IAEA Safety Guide WS G-2.2, “Decommissioning of Medical, Industrial and Research
Facilities,” Vienna, Austria, December 1999.

31.

IAEA Safety Guide WS G-2.4, “Decommissioning of Nuclear Fuel Cycle Facilities,” Vienna,
Austria, June 2001.

32.

IAEA Safety Guide WS-G-5.2, “Safety Assessment for the Decommissioning of Facilities Using
Radioactive Material,” Vienna, Austria, February 2009.

33.

CFR, “Annual Fees for Reactor Licenses and Fuel Cycle Licenses and Materials Licenses,
Including Holders of Certificates of Compliance, Registrations, and Quality Assurance Program
Approvals and Government Agencies Licensed by the NRC,” Part 171, Chapter 1, Title 10,
“Energy.”

34.

NRC, NUREG-1496, Volume 1, “Generic Environmental Impact Statement in Support of
Rulemaking on Radiological Criteria for License Termination of NRC-Licensed Nuclear
Facilities,” Washington, DC, July 1997 (ADAMS Accession No. ML042310492).

35.

National Historic Preservation Act of 1966, 54 U.S.C. 300101 et seq.

36.

Endangered Species Act of 1973, 16 U.S.C. 1531 et seq.

37.

Magnuson-Stevens Fishery Conversation and Management Act (16 U.S.C. 1801 et seq.).

38.

NRC, Management Directive 8.4, “Management of Facility-Specific Backfitting and Information
Collection,” Washington, DC, October 9, 2013.

4

Copies of International Atomic Energy Agency (IAEA) documents may be obtained through its Web site at
https://www.iaea.org/ or by writing the International Atomic Energy Agency, P.O. Box 100, Wagramer Strasse 5,
A-1400 Vienna, Austria. Telephone (+431)2600-0; fax (+431) 2600-7; or e-mail Official.Mail@IAEA.org.

DG-1347 Revision 1, Page 29