[Federal Register Volume 91, Number 67 (Wednesday, April 8, 2026)]
[Notices]
[Pages 17815-17818]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2026-06781]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-261; NRC-2026-1750]


Duke Energy Progress, LLC; H.B. Robinson Steam Electric Plant, 
Unit No. 2; Exemption

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice; issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued an 
exemption from the regulation that would have required the application 
for subsequent renewal of Renewed Facility Operating License No. DPR-23 
for H.B. Robinson Steam Electric Plant, Unit No. 2 (Robinson) to be 
referred to the Advisory Committee on Reactor Safeguards for a review 
and report, with any report being made part of the record of the 
application and made available to the public, except to the extent that 
security classification prevents disclosure. Due to this exemption, 
such referral, review, and report are no longer required.

DATES: The exemption was issued on April 2, 2026.

[[Page 17816]]


ADDRESSES: Please refer to Docket ID NRC-2026-1750 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly available information related to this document 
using any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2026-1750. Address 
questions about Docket IDs in Regulations.gov to Bridget Curran; 
telephone: 301-415-1003; email: [email protected]. For technical 
questions, contact the individual listed in the For Further Information 
Contact section of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin ADAMS Public Search.'' 
For problems with ADAMS, please contact the NRC's Public Document Room 
(PDR) reference staff at 1-800-397-4209, at 301-415-4737, or by email 
to [email protected].
     NRC's PDR: The PDR, where you may examine and order copies 
of publicly available documents, is open by appointment. To make an 
appointment to visit the PDR, please send an email to 
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8 
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except 
Federal holidays.

FOR FURTHER INFORMATION CONTACT: Mark Yoo, Office of Nuclear Reactor 
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-8583; email: [email protected].

SUPPLEMENTARY INFORMATION: The text of the exemption is attached.

    Dated: April 6, 2026.

    For the Nuclear Regulatory Commission.
Angela Wu,
Senior Project Manager, License Renewal Projects Branch, Division of 
New and Renewed Licenses, Office of Nuclear Reactor Regulation.

Attachment--Exemption

NUCLEAR REGULATORY COMMISSION

Docket No. 50-261

Duke Energy Progress, LLC

H.B. Robinson Steam Electric Plant, Unit No. 2

Exemption

I. Background

    Duke Energy Progress, LLC (Duke) is the holder of Renewed 
Facility Operating License No. DPR-23 for H.B. Robinson Steam 
Electric Plant, Unit No. 2 (Robinson). The license provides, among 
other things, that the licensee is subject to all rules, 
regulations, and orders of the U.S. Nuclear Regulatory Commission 
(NRC, the Commission) now or hereafter in effect. Robinson consists 
of one Westinghouse three-loop pressurized-water reactor with a 
licensed power level of 2,339 megawatts thermal, and it is located 
in Hartsville, South Carolina.
    On April 1, 2025, Duke submitted to the NRC an application for 
subsequent renewal of Renewed Facility Operating License No. DPR-23 
for Robinson pursuant to title 10 of the Code of Federal Regulations 
(10 CFR) Part 54, ``Requirements for Renewal of Operating Licenses 
for Nuclear Power Plants,'' requesting subsequent renewal for a 
period of 20 years beyond the current renewed facility operating 
license's expiration date of July 31, 2030. A final NRC decision on 
this application is expected on or before April 27, 2026.
    The regulations governing license renewal and that are 
applicable to the Robinson subsequent license renewal application 
include 10 CFR 54.25, ``Report of the Advisory Committee on Reactor 
Safeguards.'' This regulation states that ``[e]ach renewal 
application will be referred to the Advisory Committee on Reactor 
Safeguards for a review and report. Any report will be made part of 
the record of the application and made available to the public, 
except to the extent that security classification prevents 
disclosure.'' The December 13, 1991, rulemaking that promulgated 10 
CFR 54.25 (Nuclear Power Plant License Renewal, 56 FR 64943, 64966) 
specifically noted that review by the Advisory Committee on Reactor 
Safeguards (ACRS) was desirable but not required by statute.
    On May 23, 2025, the President issued Executive Order (E.O.) 
14300 (90 FR 22587), ``Ordering the Reform of the Nuclear Regulatory 
Commission,'' and section 4(b) of E.O. 14300 directs, in part, that 
``[r]eview by ACRS of permitting and licensing issues shall focus on 
issues that are truly novel or noteworthy.''
    In April 2026, the NRC issued ``Safety Evaluation Related to the 
Subsequent License Renewal of H.B. Robinson Steam Electric Plant, 
Unit 2'' (ML26089A378) documenting the NRC's safety review of the 
Robinson subsequent license renewal application. As part of this 
safety review, the NRC did not identify any issues that are ``truly 
novel or noteworthy.''
    Pursuant to 10 CFR 54.15, ``Specific exemptions,'' exemptions 
from the requirements of 10 CFR part 54 may be granted by the 
Commission in accordance with 10 CFR 50.12, ``Specific exemptions.'' 
Pursuant to 10 CFR 50.12, the Commission may, upon application by an 
interested person or upon its own initiative, grant exemptions from 
its requirements when (1) the exemptions are authorized by law, will 
not present an undue risk to the public health and safety, and are 
consistent with the common defense and security and (2) special 
circumstances are present. Under 10 CFR 50.12 (a)(2)(vi), special 
circumstances are present when there is present any material 
circumstance not considered when the regulation was adopted for 
which it would be in the public interest to grant an exemption. That 
regulation also provides that if this condition is relied on 
exclusively for satisfying the special circumstances requirement, 
then the exemption may not be granted until the Executive Director 
for Operations (EDO) has consulted with the Commission.

II. Action

    Based on the direction in E.O. 14300, the regulatory history of 
10 CFR 54.25, and the fact that the NRC's safety review of the 
Robinson subsequent license renewal application did not identify any 
issues that are ``truly novel or noteworthy,'' the NRC has 
determined that the granting of an exemption upon its own 
initiative, pursuant to 10 CFR 54.15 and 10 CFR 50.12, from the 
requirements of 10 CFR 54.25 with respect to the Robinson subsequent 
license renewal application would be warranted. Moreover, for the 
reasons explained below, the NRC has determined that the 
requirements of 10 CFR 54.15 and 10 CFR 50.12 are met. Therefore, an 
exemption from the requirements of 10 CFR 54.25 with respect to the 
Robinson subsequent license renewal application may be granted.

III. Discussion

    As described in 10 CFR 1.13, ``Advisory Committee on Reactor 
Safeguards,'' the ACRS was established by the Atomic Energy Act of 
1954, as amended (AEA). Among other things, the ACRS reviews and 
reports on safety studies and applications for construction permits 
and facility operating licenses and advises the Commission with 
regard to hazards of proposed or existing reactor facilities and the 
adequacy of proposed reactor safety standards. The ACRS also reviews 
any generic issues or other matters referred to it by the Commission 
for advice.
    As previously stated, 10 CFR 54.25 requires that each renewal 
application be referred to the ACRS for a review and report. The 
rulemaking that promulgated this regulation (56 FR 64966) explained 
the regulation as follows:
    Section 182.b of the AEA states:

The ACRS shall review each application under section 103 or section 
104b. for a construction permit or an operating license for a 
facility, any application under section 104c. for a construction 
permit or an operating license for a testing facility, any 
application under section 104a. or c. specifically referred to it by 
the Commission, and any application for an amendment to a 
construction permit or an amendment to an operating license under 
section 103 or 104a., b., or c. specifically referred to it by the 
Commission . . . .

    Section 182.b does not explicitly refer to applications for 
renewal of an operating license as requiring ACRS review. However, 
the Commission believes that review by the ACRS is desirable. 
Accordingly, [10 CFR] 54.25 of the final rule requires ACRS review 
of a license renewal application.

The Commission has not changed 10 CFR 54.25 since its promulgation. 
Further, no

[[Page 17817]]

subsequent amendments of the AEA have set forth a requirement for 
the ACRS to review subsequent license renewal applications.

The Exemption Is Authorized by Law

    The exemption would remove the requirement for the Robinson 
subsequent license renewal application to be referred to the ACRS 
for a review and report. As previously stated, 10 CFR 54.15 and 10 
CFR 50.12 allow the NRC to grant exemptions from the requirements of 
10 CFR part 54, including 10 CFR 54.25, when the exemptions are 
authorized by law. The requirement of 10 CFR 54.25 is not required 
by the AEA or any other law. As noted by the Commission (56 FR 
64966), the AEA does not explicitly refer to applications for 
renewal of an operating license as requiring ACRS review. Therefore, 
the NRC finds that the exemption is authorized by law.

The Exemption Will Not Present an Undue Risk to the Public Health 
and Safety

    The exemption would remove the requirement for the Robinson 
subsequent license renewal application to be referred to the ACRS 
for a review and report. As previously stated, 10 CFR 54.15 and 10 
CFR 50.12 allow the NRC to grant exemptions from the requirements of 
10 CFR part 54, including 10 CFR 54.25, when the exemptions will not 
present an undue risk to the public health and safety. The standards 
and criteria that must be met before the Commission issues 
subsequent renewed licenses would not be affected by an exemption 
from 10 CFR 54.25. That is, regardless of the ACRS review required 
under 10 CFR 54.25, the regulation at 10 CFR 54.29, ``Standards for 
issuance of a renewed license,'' would continue to set forth the 
safety criteria that must be met before subsequent renewed licenses 
may be issued. Moreover, the NRC staff, which has a robust process 
for reviewing applications for renewed licenses, has completed its 
detailed review of how the Robinson subsequent license renewal 
application addresses the standards in 10 CFR 54.29 (and other 
relevant regulations). The results of the NRC staff's safety review 
are documented in its safety evaluation. The safety evaluation 
confirmed that all of the safety standards required for the issuance 
of the Robinson subsequent renewed license have been met. 
Additionally, the safety evaluation did not identify any ``truly 
novel or noteworthy'' issues. On this basis, the NRC finds that the 
exemption presents no undue risk to the public health and safety.

The Exemption Is Consistent With the Common Defense and Security

    The exemption would remove the requirement for the Robinson 
subsequent license renewal application to be referred to the ACRS 
for a review and report. As previously stated, 10 CFR 54.15 and 10 
CFR 50.12 allow the NRC to grant exemptions from the requirements of 
10 CFR part 54, including 10 CFR 54.25, when the exemptions are 
consistent with the common defense and security. The NRC has 
determined that the exemption does not impact the common defense and 
security because the common defense and security is not within the 
scope of subsequent license renewal reviews, which, instead, focus 
on the effects of aging on systems, structures, and components. When 
promulgating revisions to its license renewal rule in 1995 (60 FR 
22461, 22463-64), the Commission re-affirmed its philosophy that the 
existing regulatory process is adequate to ensure that the licensing 
bases of all currently operating plants provide and maintain an 
acceptable level of safety so that operation will not be inimical to 
the public health and safety or common defense and security. 
Similarly, any ACRS review of a subsequent license renewal 
application would not relate to the issue of the common defense or 
security. Therefore, the NRC finds that the exemption is consistent 
with the common defense and security.

Special Circumstances Are Present

    The exemption would remove the requirement for the Robinson 
subsequent license renewal application to be referred to the ACRS 
for a review and report. As previously stated, 10 CFR 54.15 and 10 
CFR 50.12 allow the NRC to grant exemptions from the requirements of 
10 CFR part 54, including 10 CFR 54.25, when special circumstances 
are present. One such special circumstance is that there is present 
any material circumstance not considered when the regulation was 
adopted for which it would be in the public interest to grant an 
exemption. The direction in E.O. 14300 to limit ACRS review to 
issues that are truly novel or noteworthy is a material circumstance 
and because it was issued in 2025, it was not considered when the 
NRC adopted 10 CFR 54.25 in 1991 and decided to broadly require all 
license renewal applications to be referred to the ACRS, even though 
such referrals are not required by the AEA. Additionally, following 
the direction of E.O. 14300 is in the public interest, which is 
served by not performing requirements, such as the referral of the 
Robinson subsequent license renewal application to the ACRS, that 
are unnecessary. The NRC staff has reviewed approximately 100 
license renewal and 25 subsequent license renewal applications to 
date and as part of those reviews discussed and took appropriate 
action upon identifying any novel or noteworthy issues (e.g., issues 
related to buried gray cast iron piping). The NRC staff applied this 
well-established process to its review of the Robinson subsequent 
license renewal application and did not identify any novel or 
noteworthy issues. Therefore, the referral of this application to 
the ACRS is not necessary and it would be in the public interest for 
the NRC to grant an exemption from the regulation requiring that 
referral. Finally, because the NRC is exclusively relying on 10 CFR 
50.12(a)(2)(vi) for satisfying 10 CFR 50.12(a)(2), the EDO consulted 
with the Commission, as required. On this basis, the NRC finds that 
special circumstances are present.

Environmental Considerations

    The exemption would remove the requirement for the Robinson 
subsequent license renewal application to be referred to the ACRS 
for a review and report. The NRC has determined that this exemption 
does not have a significant effect on the human environment and, 
therefore, that a categorical exclusion under 10 CFR 51.22, 
``Criterion for categorical exclusion; identification of licensing 
and regulatory actions eligible for categorical exclusion or 
otherwise not requiring environmental review,'' is appropriate. 
Specifically, under 10 CFR 51.22(c)(25), categories of actions that 
are categorical exclusions include the granting of an exemption from 
the requirements of any NRC regulation, provided that: (i) there is 
no significant hazards consideration; (ii) there is no significant 
change in the types or significant increase in the amounts of any 
effluents that may be released offsite; (iii) there is no 
significant increase in individual or cumulative public or 
occupational radiation exposure; (iv) there is no significant 
construction impact; (v) there is no significant increase in the 
potential for or consequences from radiological accidents; and (vi) 
the requirements from which the exemption is sought involve an item 
listed in 10 CFR 51.22(c)(25)(vi)(A)-(I), where 10 CFR 
51.22(c)(25)(vi)(A), (B), and (I) are ``recordkeeping 
requirements,'' ``reporting requirements,'' and ``other requirements 
of an administrative, managerial, or organizational nature,'' 
respectively. As explained below, these criteria are satisfied for 
this exemption.
    An exemption involves no significant hazards consideration if, 
as provided in 10 CFR 50.92(c), operation of the facility in 
accordance with the proposed exemption would not (1) involve a 
significant increase in the probability or consequences of an 
accident previously evaluated; or (2) create the possibility of a 
new or different kind of accident from any accident previously 
evaluated; or (3) involve a significant reduction in a margin of 
safety. The instant exemption would remove the requirement for the 
Robinson subsequent license renewal application to be referred to 
the ACRS for a review and report and the NRC has not identified any 
novel or noteworthy issues that could justify referring that 
application to the ACRS; therefore, the exemption has no bearing on 
the operation of Robinson. Referring (or declining to refer) the 
application to the ACRS would not change any manner in which the 
facility would operate and, accordingly, the exemption would not 
significantly change the types or significantly increase the amounts 
of any effluents that may be released offsite, would not 
significantly increase individual or cumulative public or 
occupational radiation exposure, would have no significant 
construction impact, and would not significantly increase the 
potential for or consequences from radiological accidents. Finally, 
the requirement from which the exemption is sought involves 
recordkeeping requirements, reporting requirements, or other 
requirements of an administrative, managerial, or organizational 
nature. Accordingly, the exemption from 10 CFR 54.25 meets the 
eligibility criteria for categorical exclusion set forth in 10 CFR 
51.22(c)(25). Pursuant to 10 CFR 51.22(b), no environmental impact 
statement or environmental assessment need be prepared in connection 
with the issuance of the exemption.

[[Page 17818]]

IV. Conclusions

    Accordingly, the Commission has determined that, pursuant to 10 
CFR 54.15 and 10 CFR 50.12, the exemption from the requirements of 
10 CFR 54.25 with respect to the Robinson subsequent license renewal 
application is authorized by law, will not present an undue risk to 
the public health and safety, and is consistent with the common 
defense and security. Also, special circumstances are present. 
Therefore, the Commission hereby grants an exemption from the 
requirements of 10 CFR 54.25 and, accordingly, the Robinson 
subsequent license renewal application is no longer required to be 
referred to the ACRS for a review and report.
    The exemption is effective upon issuance.

    Dated: April 2, 2026.

    For the Nuclear Regulatory Commission.

    /RA/

Michele Sampson,
Director, Division of New and Renewed Licenses, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2026-06781 Filed 4-7-26; 8:45 am]
BILLING CODE 7590-01-P