Part 50 section 2 final supporting statement

FINAL SUPPORTING STATEMENT FOR
10 CFR PART 50
APPLICATIONS
SECTION 2
50.30, 55(b) & (d) - Filing Application;
Decommissioned Plants 50.54(bb); License Amend. 50.59(c), 50.90, 50.91(a), (b); License
Transfers 50.80(b); NRC Notification, 50.74; 50.33 Contents of applications; general information
(Early Site Permits; Standard Design Certifications, Combined Licenses, Standard Design
Approvals, Manufacturing Licenses, Construction Permits, Operating Licenses); 50.33(f) Financial
Qualifications, 50.36,50.36A, 50.36B & Appendix I, Technical Specifications; 50.34(c) & (d) &
50.54(p), Security; 50.35(b), Periodic Reports; 50.34(w)(3) & (4), Property Insurance Damage
Insurance
3150-0011
ABSTRACT
The U.S. Nuclear Regulatory Commission (NRC) is authorized by Congress to have responsibility
and authority for the licensing and regulation of nuclear power plants, research reactors and
testing facilities (also known collectively as research and test reactors), fuel reprocessing plants
and other utilization and production facilities licensed pursuant to the Act. To meet its
responsibilities, the NRC conducts a detailed review of all applications for licenses to construct and
operate such facilities. The purpose of the detailed review is to ensure that the proposed facilities
can be built and operated safely at the proposed locations, and that all structures, systems and
components important to safety will be designed to withstand the effects of postulated accident
conditions, without undue risk to the health and safety of the public.
Under 10 CFR Part 50, before a company or other entity can build a production or utilization facility
at a particular site, it must obtain a construction permit from the NRC. Subsequently, an operating
license must be obtained from the NRC before an applicant can operate the facility. The decision
by the NRC as to whether to approve an application for a construction permit or an operating
license is based largely on the NRC staff's detailed review of the information provided as part of an
application. Information provided by the applicant as part of the application is crucial to the
licensing process as it provides the NRC with the information it needs to make a decision with
regard to the proposed facility's impact on the public's health and safety and the environment.
The Commission issues an operating license or construction permit, with appropriate conditions
and limitations (including technical specifications), after determining that an application for a
license meets certain standards and requirements. Licensees must maintain records and prepare
reports to demonstrate their fulfillment of regulatory requirements. The information collection
requirements in this section include:
•
•

filing application for a license or combined license which includes both general (applicant
name; type of business; radiological emergency response plans) and technical information
(preliminary or final safety analysis report; descriptions of the equipment and systems);
submitting technical specifications with administrative controls. Administrative controls are

•
•
•

the provisions relating to organization and management, procedures, recordkeeping,
review and audit, and reporting necessary to ensure operation of the facility in a safe
manner;
physical security and safeguards contingency plans;
periodic reports of the progress and results of research and development programs
designed to resolve safety questions and reports on the amount and sources of property
damage/accident recovery insurance; and
report describing the implementation of a newly developed probabilistic risk assessment
(PRA) method.
These regulations affect 89 licensees for operating nuclear power plants, 31 non-power
production and utilization facilities, 15 combined operating license holders/applicants and
29 power plants that are currently being decommissioned. Licensees may voluntarily submit
a request for an exemption to the Commission and maintain a record of that request.
Licensees may voluntarily submit a request for an exemption (See Section 6) to the
Commission and maintain a record of that request.
A.

JUSTIFICATION

1.

Need for Collection of Information
The information is needed in order to determine licensee compliance with the
regulations set forth in 50.30, 55(b) & (d); 50.33a & Appendix L; 50.54(bb); 50.59(c),
50.90, 50.91(a), (b); 50.80(b); 50.74; 50.33; 50.36,50.36A, 50.36B & Appendix I,;
50.34(c) & (d) & 50.54(p); 50.35(b), 50.34(w)(3) & (4). Details of these regulations
can be found at the end of this supporting statement in “Description of Requirements.”

2.

Agency Use and Practical Utility of Information
Applicants or licensees requesting approval to construct or operate utilization or
production facilities are required by the Atomic Energy Act of 1954, as amended (the
Act), to provide information and data that the NRC may determine necessary to
ensure the health and safety of the public.
The NRC uses the records and reports required in this part to ascertain that licensees’
licensing the design, construction, operation, and decommissioning of commercial
nuclear power plants and other nuclear facilities programs are adequate to protect
public health and minimize danger to life and property and that licensees’ personnel
are aware of and follow up on the information and steps needed to perform licensed
activities in a safe manner. The reports and recordkeeping requirements allow NRC to
determine whether to take actions, such as to conduct inspections or to alert other
licensees to prevent similar events that may have generic implications.

3.

Reduction of Burden Through Information Technology
There are no legal obstacles to reducing the burden associated with this information
collection. The NRC encourages respondents to use information technology when it
would be beneficial to them. The NRC has issued Guidance for Electronic

Submissions to the NRC which provides direction for the electronic transmission and
submittal of documents to the NRC. Electronic transmission and submittal of
documents can be accomplished via the following avenues: the Electronic Information
Exchange (EIE) process, which is available from the NRC's “Electronic Submittals”
Web page, by Optical Storage Media (OSM) (e.g. CD-ROM, DVD), by facsimile or by
e-mail. It is estimated that approximately 45% of the responses are filed electronically.
4.

Effort to Identify Duplication and Use Similar Information
No sources of similar information are available. There is no duplication of
requirements.

5.

Effort to Reduce Small Business Burden
Not applicable.

6.

Consequences to Federal Program or Policy Activities if the Collection is Not
Conducted or is Conducted Less Frequently
If the information is not collected, NRC will not be able to assess whether licensees
are operating within the specific safety requirements applicable to the licensing,
constructing, and operating activities for nuclear power reactors; research and test
reactors; and other production and utilization facilities.
The information and required frequency from licensees that seek to construct and
operate nuclear power reactors, research and test reactors; and other production and
utilization facilities is essential to NRC’s determination of whether the applicant has
adequate equipment, training, funds and experience throughout the life of the licensee
to protect the public health and safety.

7.

Circumstances which Justify Variation from OMB Guidelines
10 CFR 50.74 requires that licensees notify the NRC within 30 days of any change in
the status of licensed reactor operators or senior operators. The variation is
necessary to be sure that temporarily or permanently replaced licensed or senior
reactor operators are immediately staffed by qualified personnel.
A few special reports, such as the Licensee Event Reports, required by
10 CFR 50.36(c), 10 CFR 50.72, and 10 CFR 50.73, the Post Accident Monitoring
Report (when required), and the Steam Generator Tube Inspection Report, are
required in fewer than 30 days to ensure that the NRC promptly responds to situations
with the potential to seriously impact public health and safety (also see the Section 4
Supporting Statement). Many of the records involved with this information collection
are retained longer than 3 years, some for the life of the plant, to establish patterns or
base-line performance to anticipate and assess future trends. These variations are
deemed necessary to ensure that the health and safety of the public will not be
adversely affected by the operation of the plant.
10 CFR 50.54(w)(4)(ii) requires licensees to provide written notification when the
reactor is and can be maintained in a safe and stable condition. This notification could

occur in less than 30 days of the event, at which time licensees are expected to
provide the required notification.
This notification is necessary to provide the NRC with information to monitor cleanup
and to begin allowing the release of insurance proceeds from the decontamination
priority and also used for non-cleanup purposes.
8.

Consultations Outside the NRC
Opportunity for public comment on the information collection requirements for this
clearance package was published in the Federal Register on February 19, 2021,
(86 FR 10360). Additionally, NRC staff contacted five stakeholders via email. The
stakeholders were new, operating and research and test reactor owner licensee
representatives and interested stakeholders from Duke Energy Progress, LLC, Kairos
Power, Southern Nuclear Operating Co., Washington State University and X-Energy.
The NRC received one out-of-scope comment as a result of the FRN. No additional
responses or comments were received as a result of the FRN or the staff’s direct
solicitation of comment.

9.

Payment or Gift to Respondents
Not applicable.

10.

Confidentiality of Information
Confidential and proprietary information is protected in accordance with NRC
regulations at 10 CFR 9.17(a) and 10 CFR 2.390(b).

11.

Justification for Sensitive Questions
This regulation does not request sensitive information.

12.

Estimated Industry Burden and Burden Hour Cost
The total estimated cost for information collection requirements in this section is
estimated to be 682,975 hours at a cost of $ 190,550,025 (682,975 hours x $279/hr).
Total Burden and Responses Section 2
Hours
Responses
Reporting
457,342
2,152
Recordkeeping
225,633
164
TOTAL
682,975
2,316
Detailed burden estimates are included in the supplemental burden spreadsheet titled,
“Table 1 - Summary of Supporting Statements.” The $279 hourly rate used in the
burden estimates is based on the Nuclear Regulatory Commission’s fee for hourly
rates as noted in 10 CFR 170.20 “Average cost per professional staff-hour.” For more

information on the basis of this rate, see the Revision of Fee Schedules; Fee
Recovery for Fiscal Year 2020 (85 FR 37250, June 19, 2020).
13.

Estimate of Other Additional Costs
The quantity of records to be maintained is roughly proportional to the recordkeeping
burden and therefore can be used to calculate approximate records storage costs.
Based on the number of pages maintained for a typical clearance, the records storage
cost has been determined to be equal to .0004 times the recordkeeping burden cost.
Therefore, the storage cost for this clearance is estimated to be $25,180 (225,633
recordkeeping hours x $279 x .0004).

14.

Estimated Annualized Cost to the Federal Government
The staff has developed estimates of annualized costs to the Federal Government
related to the conduct of this collection of information. These estimates are based on
staff experience and subject matter expertise and include the burden needed to
review, analyze, and process the collected information and any relevant operational
expenses.
The annualized estimated cost to the government is $28,444,887 (101,953 hours x
$279) as shown on the attached Summary Table.

15.

Reasons for Changes in Burden or Cost
The burden and number of responses have changed as described in the tables below:
Burden change

Reporting
Recordkeeping
Third Party
Disclosure
Total

2018
estimates
440,901.7
230,820.5
0.0
671,722.2

Current
submission
457,342
225,633
0
682,975

Change
16,440.3
-5,187.5
0
11,252.8

Change in Responses

Reporting
Recordkeeping
Third Party
Disclosure
Total

2018
estimates
2,152
153

Current
submission

Change

2,152
164

0
11.00

0

0

0

2,305.3

2,316

11.00

Overall, for this section, the changes are attributed the increase in certificate holders
and decommissioning plants, and a decrease in operating reactors and sites.

The largest increase in burden is due to an increase in the estimated number of
license amendments under 50.59(c), 50.90, 50.91(a), and (b). The number of
estimated license amendments increased from 918 to 984. At 313 hours per license
amendment, this resulted in an increase of 20,658 hours. In addition, 6,000 hours of
burden was added for license amendments related to topical reports.
The largest decrease in burden is associated with technical specifications for
operating power reactors. Due to a change in the number of operating reactors from
94 to 89, the estimated burden for this section decreased from 195,520 to 185,120, a
decrease of 10,400 hours. The burden for technical specifications for shutdown
reactors increased by 3,120 hours. The burden for technical specifications is lower for
a shutdown reactor (208 hours rather than 2080 hours); therefore, the overall burden
for technical specifications was a net decrease.
In addition, the burden for 50.34(c) & (d) & 50.54(p) that is covered under
10 CFR 73.67 (approved by OMB under Clearance No. 3150-0002) has been
removed, which reduced the responses by 76.
16.

Publication for Statistical Use

17.

The information being collected is not expected to be published for statistical use.
Reason for Not Displaying the Expiration Date
The recordkeeping and reporting requirements for this information collection are
associated with regulations and are not submitted on instruments such as forms or
surveys. For this reason, there are no data instruments on which to display an OMB
expiration date. Further, amending the regulatory text of the CFR to display
information that, in an annual publication, could become obsolete would be unduly
burdensome and too difficult to keep current.

18.

Exceptions to the Certification Statement
None.

B.

COLLECTIONS OF INFORMATION EMPLOYING STATISTICAL METHODS
Not applicable.

Appendix A – Description Requirements
Applications
10 CFR 50.30 This section provides for the filing of an application for early site
permits; standard design certifications, combined licenses, standard design approvals,
manufacturing licenses, construction permits, and operating licenses which includes
both general and technical information. General information is covered under Section
50.33, and technical information is covered under Section 50.34. Provisions pertaining
to technical information submitted in applications currently in Section 50.34 for early
site permits, standard design certifications, and combined licenses are being amended
to move these requirements to, and cover the burden in, Part 52. The general
information required by Section 50.33 will remain in Part 50. Section 50.30(f) also
requires that an Environmental Report (ER) be submitted pursuant to Part 51. The
information collection burden associated with the ER is covered by a separate OMB
clearance for Part 51 (3150-0021) and, therefore, no environmental burden is included
for Section 50.30.
10 CFR 50.33. This section requires each application to provide general information
such as: applicant name, address, type of business (partnership or corporation),
citizenship, to identify the class of license, how the license will be used, the time period
for the license, a list of other related licenses and provide details about the applicant's
financial qualifications and emergency response plans.
10 CFR 50.33(f) This subsection requires the applicant to submit information
demonstrating the financial qualification of the applicant to carry out, in accordance
with regulations in this chapter, the activities for which the permit or license is sought.
Under subsection 50.33(f)(5) the Commission may request an established entity or
newly formed entity to submit additional or more detailed information respecting its
financial arrangements and status of funds if the Commission considers this
information appropriate. This may include information regarding a licensee’s ability to
continue the conduct of the activities authorized by the license and to decommission
the facility.
10 CFR 50.33(g). This section of 10 CFR 50 requires that the applicant for an
operating license submit state and local government radiological emergency
response plans. The plans shall define the Emergency Planning Zone (EPZ) for the
plume exposure pathway and the ingestion pathway. Generally, with the nuclear
facility located at the center, the plume exposure pathway for the EPZ will cover an
area with a radius of approximately 10 miles, and the ingestion pathway will cover
an area with a radius of approximately 50 miles. The exact size and configuration
of the EPZ will be determined in relation to the local emergency response needs
and capabilities as they are affected by such conditions as demography,
topography, access routes and jurisdictional boundaries.
10 CFR 50.54(bb). This section requires that for operating nuclear power reactors,
the licensee shall, within 2 years following permanent cessation of operation of the
reactor or 5 years before expiration of the reactor operating license, whichever
occurs first, submit written notification to the Commission for its review and

preliminary approval of the program by which the licensee intends to manage and
provide funding for the management of all irradiated fuel at the reactor following
permanent cessation of operation of the reactor until title to the irradiated fuel and
possession of the fuel is transferred to the Secretary of Energy for its ultimate
disposal in a repository. Final Commission review will be undertaken as part of any
proceeding for continued licensing under 10 CFR 50 or 10 CFR 72. The licensee
must demonstrate to the NRC that the elected actions will be consistent with NRC
requirements for licensed possession of irradiated nuclear fuel and that the actions
will be implemented on a timely basis. Where implementation of such actions
requires NRC authorizations, the licensee shall verify in the notification that
submittals for such actions have been or will be made to the NRC and shall identify
them. A copy of the notification shall be retained by the licensee as a record until
expiration of the reactor operating license. The licensee shall notify the NRC of any
significant changes in the proposed waste management program as described in
the initial notification.
10 CFR 50.55(b). This section specifies that if the proposed construction or
modification of a facility is not completed by the latest completion date specified in
the construction permit, the permit shall expire and all rights there under shall be
forfeited. However, if good cause can be shown by the applicant, the Commission
may extend the completion date for a reasonable period of time. The Commission
will recognize, among other things, developmental problems attributable to the
experimental nature of the facility or fire, flood, explosion, strike, sabotage,
domestic violence, enemy action, an act of the elements, and other acts beyond
the control of the permit holder, as a basis for extending the completion date. No
completion date extensions are expected during this clearance period. Thus, the
relevant burden is zero.
Pursuant to 10 CFR 50.55(d), at or about the time of completion of the
construction or modification of the facility, the applicant must file any additional
information needed to bring the original application for license up to date, and
must file an application for an operating license or an amendment to an
application for a license to construct and operate the facility for the issuance of an
operating license, as appropriate, as specified in 10 CFR 50.30(d).
10 CFR 50.59(c), 50.90, 50.91(a) and (b). These sections are applicable for
amendment of licenses to operating nuclear power plants, research and test
reactors, and other production and utilization facilities, amendment of licenses to
permanently shut down nuclear power and research and test reactors and other
production and utilization facilities and amendments to combined licenses,
manufacturing licenses, early site permits and construction permits. 10 CFR
50.59(c) requires the holder of a license authorizing operation of a production or
utilization facility who desires to make a change to the facility or procedures as
described in the FSAR or to conduct tests or experiments not described in the
FSAR to submit an application for amendment of the license pursuant to 10 CFR
50.90 if the change, experiment, or test does meet certain criteria or a change to the
TS is required. 10 CFR 50.59 (d)(2) requires the licensee to submit a report of
these changes and the corresponding evaluations at intervals not to exceed 24
months. Amendments to permits and licenses may also be submitted by holders of

construction permits, early permits, manufacturing licenses, and combined licenses
(prior to the operation of the nuclear power plant).
10 CFR 50.90 requires the application for amendment of the license or permit to be
filed with the Commission, fully describing the changes and following as far as
applicable in the form prescribed for original applications.
The application for amendment of the license or permit enables the staff to evaluate
any changes made at the facility or any new information concerning the facility that
may potentially affect the safety of the facility and consequently the health and
safety of the public.
Under 10 CFR 50.91(a)(1) and (b)(1), a licensee requesting an amendment must
provide to the NRC and the State in which its facility is located, the amendment
application and an analysis concerning the issue of no significant hazards
consideration. NRC needs licensees' and permit holder’s analyses to quickly make
and publish for public comment its “proposed determination” about no significant
hazards consideration; the States need licensees' and permit holder’s analyses in
order to quickly consult with the NRC.
On July 19, 1995, the Commission published in the Federal Register (60 FR 36953)
its final rule on TS for nuclear power reactors. The rule codified the criteria
identified in the final policy statement for determining the content of TS. A major
benefit of the rule involves the reduction in the number of safety functions controlled
by TS (limiting conditions for operation) by applying the criteria. The rule ensures
that any changes to the most safety significant features will require prior review and
approval by NRC. The safety functions that do not satisfy the criteria can be
relocated to licensee-controlled documents and changed pursuant to 10 CFR 50.59.
The burden on licensees and the NRC can be reduced by relocating such
provisions or, for power reactor licensees, completely converting the existing TS to
the improved Standard Technical Specifications (STS). Recordkeeping and
reporting requirements for revisions that do not require an amendment are covered
in Section 5 of this clearance submittal.
10 CFR 50.80(b) This section specifies that an application for a transfer of a license
shall include as much of the information described in 10 CFR 50.33 and 50.34 with
respect to the identity and technical and financial qualifications of the proposed
transferee as would be required by those sections if the application were for an
initial license. 10 CFR 50.80(b) also specifies that the Commission may require
additional information, such as data with respect to proposed safeguards against
hazards from radioactive materials, and the transferee's qualifications to protect
against such hazards.
The requirements described above are needed to assure the transferee's financial
capability to run the facility safely and to ensure the transferee's technical capability
to properly and safely operate the facility in a way that protects the health and
safety of the public.

Procedures for aircraft impact and beyond-design basis threat
The Power Reactor Security Final Rule, approved by OMB in April 2009,
established and updated generically applicable security requirements similar to
those previously imposed by Commission orders issued after the terrorist attacks of
September 11, 2001. This rule added sections 50.54(hh) (1)&(2):
10 CFR 50.74 This section requires licensees of nuclear power facilities to notify
the NRC within 30 days of a change in status of a licensed reactor operator or
senior operator. The NRC needs to know if operators have been permanently
reassigned, terminated, or have undergone permanent disability, or illness as
required by 10 CFR 55.25, to ensure that a qualified replacement has been
assigned. (Note that notifications involving 10 CFR 55.25 are cleared under OMB
Clearance No. 3150-0024.)
10 CFR 50.36 requires licensees to maintain technical specifications with
administrative controls. Administrative controls are the provisions relating to
organization and management, procedures, recordkeeping, review and audit, and
reporting necessary to ensure operation of the facility in a safe manner. These
reporting and recordkeeping requirements are set forth in the Technical
Specifications (TS), Appendix A to the operating license for each facility license.
Pursuant to 10 CFR 50.36b, environmental reporting and recordkeeping
requirements are set forth in Appendix B to the operating license for each facility
license or in each licensee’s environmental protection plans. (A few facilities have a
single appendix that contains the combined aspects of both Appendices A and B).
10 CFR 50.36(a) requires each applicant for a license authorizing operation of a
production or utilization facility to include in its application proposed TS. A summary
statement of the bases or reasons for such specifications, other than those covering
administrative controls, shall also be included in the application.
10 CFR 50.36(b) requires each license authorizing operation of a production or
utilization facility to include TS. The TS are derived from the analyses and
evaluations included in the safety analysis report, and amendments thereto,
submitted pursuant to 10 CFR 50.34.
10 CFR 50.36(c) specifies that limiting conditions for operations (LCO) are the
lowest functional capability or performance levels of equipment required for safe
operation of a facility. When an LCO of a nuclear reactor is not met, the licensee
shall shutdown the reactor or follow any remedial action permitted by the technical
specifications until the condition can be met. A completion time (CT) is the duration
for which a licensee may continue to operate when it does not meet the
requirements for lowest functional capability. Licensees can use PRA models
acceptable to the NRC to estimate CTs. Those licensees shall submit reports to
NRC if their PRA models incorporate newly developed methods.
10 CFR 50 Appendix I consists of numerical guides for design objectives and limiting
conditions for plant operation to meet the criterion "as low as is reasonably
achievable" for radioactive material in light-water-cooled reactor effluents.

Section 50.34(c)(3) requires that each plan must describe how the applicant will
meet the requirements of 10 CFR 73 (and 10 CFR 11, if applicable, including the
identification and description of jobs as required by 10 CFR 11.11(a), at the
proposed facility). The plan must list tests, inspections, audits, and other means to
be used to demonstrate compliance with the requirements of 10 CFR 11 and 10 CFR
73, if applicable. 10 CFR 73.67 prescribes requirements for the establishment and
maintenance of a physical protection system which will have capabilities for the
protection of SNM at fixed sites and in transit and for plants in which SNM is used.
10 CFR 11 prescribes criteria and procedures for determining eligibility for access to,
or control over, certain quantities of SNM. The burden to provide this information is
included in the OMB clearance for 10 CFR Part 52, “Licenses, Certifications, and
Approvals for Nuclear Power Plants” (3150-0151).
Section 50.34(d)(1) requires that each application for a license to operate a
production or utilization facility that will be subject to 10 CFR 73.50 and 10 CFR
73.60 must include a licensee SCP in accordance with 10 CFR 73 Appendix C. The
SCP shall include plans for dealing with threats, thefts, and radiological sabotage as
defined in 10 CFR 73. Four categories of information must be included in the
applicant's SCP. These categories are specified in 10 CFR 73 Appendix C. First,
the "Background" must identify and define the perceived dangers and incidents with
which the plan will deal and the general way it will handle them. Second, the
"Generic Planning Base" must define the criteria for initiation and termination of
responses to safeguards contingencies together with the specific decisions, actions,
and supporting information needed to bring about such responses. Third, the
"Licensee Planning Base" must include the factors affecting contingency planning
that are specific to the facility. The fourth category relates to a "Responsibility
Matrix" that must include a detailed identification of the organizational entities
responsible for each decision and action associated with specific responses to
safeguards contingencies. The burden to provide this information is included in the
OMB clearance for 10 CFR Part 52, “Licenses, Certifications, and Approvals for
Nuclear Power Plants” (3150-0151).
Section 50.54(p)(1) requires that each licensee prepare and maintain SCP
procedures in accordance with 10 CFR 73 Appendix C. Procedures must be
established in order to aid execution of the detailed plan as developed in the
"Responsibility Matrix" section of the SCP. The procedures must detail the actions to
be taken and decisions to be made by each member or unit of the organization as
planned in the "Responsibility Matrix." The procedures need not be submitted to the
Commission for approval, but are inspected by the NRC staff on a periodic basis.
The burden to provide this information is included in the OMB clearance for 10 CFR
Part 73, “Physical Protection of Plants and Materials” (3150-0002).
Section 50.54(p)(1) specifies that the licensee may make no change which would
decrease the effectiveness of a PSP, or T&QP or CSP (required by 10 CFR 73.55
and 10 CFR 73.54) prepared pursuant to 10 CFR 50.34(c) or 10 CFR 73 or to the
first four categories of information contained in the SCP prepared pursuant to 10
CFR 50.34(d) or 10 CFR 73, as applicable, without prior approval of the
Commission. A licensee desiring to make such a change must submit an application
for an amendment to the licensee's license pursuant 10 CFR 50.90.

Section 50.54(p)(2) also specifies that a licensee may make changes to the plans
referenced in 10 CFR 50.54(p)(1) without prior approval if the changes do not
decrease the safeguards effectiveness of the safeguards plan. The licensee,
however, must maintain records of changes to the plans for a period of three years
from the date of the change and must submit a report containing a description of each
change within two months after the change is made.
Section 50.54(p)(3) requires the licensee to provide for the development, revision,
implementation, and maintenance of its SCP. To this end, the licensee shall provide
for a review at least every 12 months of the SCP by individuals independent of both
security program management and personnel who have direct responsibility for
implementation of the security program. All elements of the SCP must be reviewed at
least once every 24 months.
Section 50.54(p)(4) requires that the review must include a review and audit of
safeguards contingency procedures and practices, an audit of the security system
testing and maintenance program, and a test of the safeguards systems along with
commitments established for response by local law enforcement authorities. The
results of the review and audit, along with recommendations for improvements, must
be documented, reported to the licensee's corporate and plant management, and kept
available at the plant for inspection for a period of three years. The burden to provide
this information is included in the OMB clearance for 10 CFR Part 73, “Physical
Protection of Plants and Materials” (3150-0002).
10 CFR 50.35(b) specifies that "The Commission may, in its discretion, incorporate in
any construction permit provisions requiring the applicant to furnish periodic reports of
the progress and results of research and development programs designed to resolve
safety questions.”
Under 10 CFR 50.54(w)(3), licensees are required to report annually on the amount
and sources of this required insurance.
Under 10 CFR 50.54(w)(4)(i) and 10 CFR 50.54(w)(4)(ii), a licensee suffering an
accident is required to submit a cleanup plan outlining the steps and costs needed to
complete decontamination and cleanup and to allow release of the remaining
insurance proceeds for non-cleanup purposes.
10 CFR 50.54(w)(4)(I) establishes a threshold of $100 million before a cleanup plan
would be required.
10 CFR 50.54(w)(4)(ii) requires licensees to inform the Director of the Office of
Nuclear Reactor Regulation in writing when the reactor is and can be maintained in a
safe and stable condition so as to prevent any significant risk to public health and
safety. Within 30 days after the licensee informs the Director that the reactor is in this
condition, or at such earlier time as the licensee may elect or the Director may for
good cause direct, the licensee shall prepare and submit a cleanup plan for the
Director's approval. The cleanup plan must identify and contain an estimate of the
cost of each cleanup operation that will be required to decontaminate the reactor
sufficiently to permit the licensee either to resume operation of the reactor or to apply

to the U.S. Nuclear Regulatory Commission (NRC) for authority to decommission the
reactor and to surrender the license voluntarily.
The NRC topical report program is governed by several relevant regulations. Title 10
of the Code of Federal Regulations (10 CFR) Part 2, “Agency Rules of Practice and
Procedure, Part 21, “Reporting of Defects and Noncompliance,” Part 50 “Domestic
Licensing of Production and Utilization Facilities” and Part 170, “Fees for Facilities,
Materials, Import and Export Licenses, and other Regulatory Services under The
Atomic Energy Act of 1954, As Amended,” describes the formal procedures that the
NRC uses to implement its topical report program.
A topical report is a document that addresses a technical topic related to nuclear
power plant safety, which the industry submits for review and approval by the NRC
before publishing the report for use in the licensing process by other nuclear power
plant licensees.
Applicants submit a report that addresses a specific safety-related topic, i.e.,
component design regarding a U.S. nuclear power plant that requires a safety
evaluation by the agency. An applicant seeking a topical review must submit the
report to the NRC by letter, in accordance with LIC-500, “Topical Report Process”
(ADAMS Accession Number ML13158A296).
.

GUIDANCE DOCUMENTS FOR INFORMATION COLLECTION REQUIREMENTS
CONTAINED IN
APPLICATIONS
10 CFR PART 50
SECTION 2
50.30, 55(b) & (d) - Filing Application;
Decommissioned Plants 50.54(bb); License Amend. 50.59(c), 50.90, 50.91(a), (b);
License Transfers 50.80(b); NRC Notification, 50.74; 50.33 Early Site Permits 50.33(a)-(d), (j);
50.33 Non-Power Operating License; 50.33 Standard Design Certification 50.33(a)-(d);
50.33 Combined OL 50.33(a)-(d), (g)
3150-0011
Title
Regulatory Guide 1.21, Rev. 2, “Measuring,
Evaluating, and Reporting Radioactivity in
Solid Wastes and Releases of Radioactive
Materials in Liquid and Gaseous Effluents from
Light-Water-Cooled Nuclear Power Plants,”
Regulatory Guide 1.174, “An Approach for
Using Probabilistic Risk Assessment in RiskInformed Decisions on Plant-Specific Changes
to the Licensing Basis”
Regulatory Guide 1.177, “An Approach for
Plant-Specific, Risk-Informed Decisionmaking:
Technical Specifications”
Regulatory Guide 1.200, “An Approach for
Determining the Technical Adequacy of
Probabilistic Risk Assessment Results for
Risk-Informed Activities”
Regulatory Guide 4.1, Rev. 2, “Programs for
Monitoring Radioactivity in the Environs of
Nuclear Power Plants.”
LIC-500, “Topical Report Process”
DG-1362 for RG 1.200 Revision 3,
Acceptability of Probabilistic Risk Assessment
Results for Risk-Informed Activities
Regulatory Guide 1.70, Revision 3, Standard
Format and Content of Safety Analysis
Reports for Nuclear Power Plants, LWR
Edition.
Regulatory Guide 1.206, Revision 1,
Applications for Nuclear Power Plants
NUREG-1537, Part 1, "Guidelines for
Preparing & Reviewing Applications for
Licensing of Non-Power Reactors, Format and
Content."

Accession number
ML091170109

ML100910006

ML100910008
ML090410014

ML091310141
ML13158A296
ML19308B636
ML011340122

ML18131A181
ML042430055