[Federal Register Volume 90, Number 225 (Tuesday, November 25, 2025)]
[Notices]
[Pages 53396-53402]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2025-20930]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[NRC-2025-1765]


Monthly Notice; Applications and Amendments to Facility Operating 
Licenses and Combined Licenses Involving No Significant Hazards 
Considerations

AGENCY: Nuclear Regulatory Commission.

ACTION: Monthly notice.

-----------------------------------------------------------------------

SUMMARY: Pursuant to section 189a.(2) of the Atomic Energy Act of 1954, 
as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is 
publishing this regular monthly notice. The Act requires the Commission 
to publish notice of any amendments issued, or proposed to be issued, 
and grants the Commission the authority to issue and make immediately 
effective

[[Page 53397]]

any amendment to an operating license or combined license, as 
applicable, upon a determination by the Commission that such amendment 
involves no significant hazards consideration (NSHC), notwithstanding 
the pendency before the Commission of a request for a hearing from any 
person.

DATES: Comments must be filed by December 26, 2025. A request for a 
hearing or petitions for leave to intervene must be filed by January 
26, 2026. This monthly notice includes all amendments issued, or 
proposed to be issued, from September 12, 2025, to October 9, 2025. The 
last monthly notice was published on September 30, 2025.

ADDRESSES: You may submit comments by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject); however, the NRC encourages electronic 
comment submission through the Federal rulemaking website.
     Federal rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC-2025-1765. Address 
questions about Docket IDs in Regulations.gov to Bridget Curran; 
telephone: 301-415-1003; email: [email protected]. For technical 
questions, contact the individual(s) listed in the For Further 
Information Contact section of this document.
     Mail comments to: Office of Administration, Mail Stop: 
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Angela Baxter, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-8209; email: [email protected].

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2025-1765, facility name, unit 
number(s), docket number(s), application date, and subject when 
contacting the NRC about the availability of information for this 
action. You may obtain publicly available information related to this 
action by any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2025-1765.
     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]. For the convenience of the reader, 
instructions about obtaining materials referenced in this document are 
provided in the ``Availability of Documents'' section.
     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.

B. Submitting Comments

    The NRC encourages electronic comment submission through the 
Federal rulemaking website (https://www.regulations.gov). Please 
include Docket ID NRC-2025-1765, facility name, unit number(s), docket 
number(s), application date, and subject, in your comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at 
https://www.regulations.gov as well as enter the comment submissions 
into ADAMS. The NRC does not routinely edit comment submissions to 
remove identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. Notice of Consideration of Issuance of Amendments to Facility 
Operating Licenses and Combined Licenses and Proposed No Significant 
Hazards Consideration Determination

    For the facility-specific amendment requests shown in this notice, 
the Commission finds that the licensees' analyses provided, consistent 
with section 50.91 of title 10 of the Code of Federal Regulations (10 
CFR) ``Notice for public comment; State consultation,'' are sufficient 
to support the proposed determinations that these amendment requests 
involve NSHC. Under the Commission's regulations in 10 CFR 50.92, 
operation of the facilities in accordance with the proposed amendments 
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 Commission is seeking public comments on these proposed 
determinations. Any comments received within 30 days after the date of 
publication of this notice will be considered in making any final 
determinations.
    Normally, the Commission will not issue the amendments until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue any of these license amendments before expiration 
of the 60-day period provided that its final determination is that the 
amendment involves NSHC. In addition, the Commission may issue any of 
these amendments prior to the expiration of the 30-day comment period 
if circumstances change during the 30-day comment period such that 
failure to act in a timely way would result, for example in derating or 
shutdown of the facility. If the Commission takes action on any of 
these amendments prior to the expiration of either the comment period 
or the notice period, it will publish in the Federal Register a notice 
of issuance. If the Commission makes a final NSHC determination for any 
of these amendments, any hearing will take place after issuance. The 
Commission expects that the need to take action on any amendment before 
60 days have elapsed will occur very infrequently.

A. Opportunity To Request a Hearing and Petition for Leave To Intervene

    Within 60 days after the date of publication of this notice, any 
person (petitioner) whose interest may be

[[Page 53398]]

affected by any of these actions may file a request for a hearing and 
petition for leave to intervene (petition) with respect to that action. 
Petitions shall be filed in accordance with the Commission's ``Agency 
Rules of Practice and Procedure'' in 10 CFR part 2. Interested persons 
should consult a current copy of 10 CFR 2.309. If a petition is filed, 
the Commission or a presiding officer will rule on the petition and, if 
appropriate, a notice of a hearing will be issued.
    Petitions must be filed no later than 60 days from the date of 
publication of this notice in accordance with the filing instructions 
in the ``Electronic Submissions (E-Filing)'' section of this document. 
Petitions and motions for leave to file new or amended contentions that 
are filed after the deadline will not be entertained absent a 
determination by the presiding officer that the filing demonstrates 
good cause by satisfying the three factors in 10 CFR 2.309(c)(1)(i) 
through (iii).
    If a hearing is requested, and the Commission has not made a final 
determination on the issue of no significant hazards consideration, the 
Commission will make a final determination on the issue of no 
significant hazards consideration, which will serve to establish when 
the hearing is held. If the final determination is that the amendment 
request involves no significant hazards consideration, the Commission 
may issue the amendment and make it immediately effective, 
notwithstanding the request for a hearing. Any hearing would take place 
after issuance of the amendment. If the final determination is that the 
amendment request involves a significant hazards consideration, then 
any hearing held would take place before the issuance of the amendment 
unless the Commission finds an imminent danger to the health or safety 
of the public, in which case it will issue an appropriate order or rule 
under 10 CFR part 2.
    A State, local governmental body, Federally recognized Indian 
Tribe, or designated agency thereof, may submit a petition to the 
Commission to participate as a party under 10 CFR 2.309(h) no later 
than 60 days from the date of publication of this notice. 
Alternatively, a State, local governmental body, Federally recognized 
Indian Tribe, or agency thereof may participate as a non-party under 10 
CFR 2.315(c).
    For information about filing a petition and about participation by 
a person not a party under 10 CFR 2.315, see ADAMS Accession No. 
ML20340A053 (https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML20340A053) and on the NRC's public website 
at https://www.nrc.gov/about-nrc/regulatory/adjudicatory/hearing.html#participate.

B. Electronic Submissions (E-Filing)

    All documents filed in NRC adjudicatory proceedings, including 
documents filed by an interested State, local governmental body, 
Federally recognized Indian Tribe, or designated agency thereof that 
requests to participate under 10 CFR 2.315(c), must be filed in 
accordance with 10 CFR 2.302. The E-Filing process requires 
participants to submit and serve all adjudicatory documents over the 
internet, or in some cases, to mail copies on electronic storage media, 
unless an exemption permitting an alternative filing method, as further 
discussed, is granted. Detailed guidance on electronic submissions is 
located in the ``Guidance for Electronic Submissions to the NRC'' 
(ADAMS Accession No. ML13031A056), and on the NRC's public website 
(https://www.nrc.gov/site-help/e-submittals.html).
    To comply with the procedural requirements of E-Filing, at least 10 
days prior to the filing deadline, the participant should contact the 
Office of the Secretary by email at [email protected], or by 
telephone at 301-415-1677, to: (1) request a digital identification 
(ID) certificate which allows the participant (or its counsel or 
representative) to digitally sign submissions and access the E-Filing 
system for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a petition or 
other adjudicatory document (even in instances in which the 
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the 
Secretary will establish an electronic docket for the proceeding if the 
Secretary has not already established an electronic docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public website at https://www.nrc.gov/site-help/e-submittals/getting-started.html. After a digital ID certificate is 
obtained and a docket is created, the participant must submit 
adjudicatory documents in the Portable Document Format. Guidance on 
submissions is available on the NRC's public website at https://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is 
considered complete at the time the document is submitted through the 
NRC's E-Filing system. To be timely, an electronic filing must be 
submitted to the E-Filing system no later than 11:59 p.m. ET on the due 
date. Upon receipt of a transmission, the E-Filing system time-stamps 
the document and sends the submitter an email confirming receipt of the 
document. The E-Filing system also distributes an email that provides 
access to the document to the NRC's Office of the General Counsel and 
any others who have advised the Office of the Secretary that they wish 
to participate in the proceeding, so that the filer need not serve the 
document on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before adjudicatory documents are 
filed in order to obtain access to the documents via the E-Filing 
system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic 
Filing Help Desk through the ``Contact Us'' link located on the NRC's 
public website at https://www.nrc.gov/site-help/e-submittals.html, by 
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m. 
and 6 p.m., ET, Monday through Friday, except Federal holidays.
    Participants who believe that they have good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
stating why there is good cause for not filing electronically and 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted in accordance with 10 CFR 
2.302(b)-(d). Participants filing adjudicatory documents in this manner 
are responsible for serving their documents on all other participants. 
Participants granted an exemption under 10 CFR 2.302(g)(2) must still 
meet the electronic formatting requirement in 10 CFR 2.302(g)(1), 
unless the participant also seeks and is granted an exemption from 10 
CFR 2.302(g)(1).
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket, which is publicly available at https://adams.nrc.gov/ehd, unless otherwise excluded pursuant to an order of 
the presiding officer. If you do not have an NRC-issued digital ID 
certificate as previously described, click ``cancel'' when the link 
requests certificates and you will be automatically directed to the 
NRC's electronic hearing docket where you will be able to access any 
publicly available documents in a particular hearing docket. 
Participants are requested not to include personal

[[Page 53399]]

privacy information such as social security numbers, home addresses, or 
personal phone numbers in their filings unless an NRC regulation or 
other law requires submission of such information. With respect to 
copyrighted works, except for limited excerpts that serve the purpose 
of the adjudicatory filings and would constitute a Fair Use 
application, participants should not include copyrighted materials in 
their submission.
    The following table provides the nuclear power plant names, docket 
numbers, dates of application, ADAMS accession numbers, and locations 
in the application of the licensees' proposed NSHC determination. For 
further details with respect to these license amendment applications, 
see the applications for amendment, publicly available portions of 
which are available for public inspection in ADAMS. For additional 
direction on accessing information related to this document, see the 
``Obtaining Information and Submitting Comments'' section of this 
document.
    The following table provides the plant name, docket number, date of 
application, ADAMS accession number, and location in the application of 
the licensees' proposed NSHC determinations. For further details with 
respect to these license amendment applications, see the applications 
for amendment, which are available for public inspection in ADAMS. For 
additional direction on accessing information related to this document, 
see the ``Obtaining Information and Submitting Comments'' section of 
this document.

                       License Amendment Requests
------------------------------------------------------------------------
 
------------------------------------------------------------------------
  Constellation Energy Generation, LLC; Dresden Nuclear Power Station,
                    Units 2 and 3; Grundy County, IL
------------------------------------------------------------------------
Docket Nos...................  50-237, 50-249.
Application date.............  August 6, 2025.
ADAMS Accession No...........  ML25218A256.
Location in Application of     Pages 3-5 of Attachment 1.
 NSHC.
Brief Description of           The proposed amendments would relocate
 Amendments.                    Dresden Nuclear Power Station, Units 2
                                and 3, Technical Specification 3.3.7.2,
                                ``Mechanical Vacuum Pump Trip
                                Instrumentation,'' to an appropriate
                                licensee-controlled document.
Proposed Determination.......  NSHC.
Name of Attorney for           Jason Zorn, Associate General Counsel,
 Licensee, Mailing Address.     Constellation Energy Generation, LLC,
                                4300 Winfield Road, Warrenville, IL
                                60555.
NRC Project Manager,           Surinder Arora, 301-415-1421.
 Telephone Number.
------------------------------------------------------------------------
Constellation Energy Generation, LLC; Quad Cities Nuclear Power Station,
                  Units 1 and 2; Rock Island County, IL
------------------------------------------------------------------------
Docket Nos...................  50-254, 50-265.
Application date.............  August 6, 2025.
ADAMS Accession No...........  ML25218A263.
Location in Application of     Pages 3-5 of Attachment 1.
 NSHC.
Brief Description of           The proposed amendments would relocate
 Amendments.                    Quad Cities Nuclear Power Station, Units
                                1 and 2, Technical Specification
                                3.3.7.2, ``Mechanical Vacuum Pump Trip
                                Instrumentation,'' to an appropriate
                                licensee-controlled document.
Proposed Determination.......  NSHC.
Name of Attorney for           Jason Zorn, Associate General Counsel,
 Licensee, Mailing Address.     Constellation Energy Generation, LLC,
                                4300 Winfield Road, Warrenville, IL
                                60555.
NRC Project Manager,           Surinder Arora, 301-415-1421.
 Telephone Number.
------------------------------------------------------------------------
 Duke Energy Carolinas, LLC; Oconee Nuclear Station, Units 1, 2, and 3;
                            Oconee County, SC
------------------------------------------------------------------------
Docket Nos...................  50-269, 50-270, 50-287.
Application date.............  August 19, 2025.
ADAMS Accession No...........  ML25232A073.
Location in Application of     Pages 118-121 of the Enclosure.
 NSHC.
Brief Description of           The proposed amendments would increase
 Amendments.                    the existing Type A integrated leakage
                                rate test program test interval from 10
                                years to 15 years, adopt an extension of
                                the containment isolation valve leakage
                                rate testing frequency for Type C
                                leakage rate testing of selected
                                components, adopt the use of American
                                National Standards Institute/American
                                Nuclear Society (ANSI/ANS) 56.8-2020,
                                ``Containment System Leakage Testing
                                Requirements,'' and adopt a more
                                conservative allowable test interval
                                extension of 9 months for Type A, Type B
                                and Type C leakage rate tests in
                                accordance with NEI 94-01, Revision 3-A,
                                ``Industry Guideline for Implementing
                                Performance-Based Option of 10 CFR Part
                                50, Appendix J.''
Proposed Determination.......  NSHC.
Name of Attorney for           Tracey Mitchell LeRoy, Deputy General
 Licensee, Mailing Address.     Counsel, Duke Energy Corporation, 525 S
                                Tryon Street, Charlotte, NC 28202.
NRC Project Manager,           Shawn Williams, 301-415-1009.
 Telephone Number.
------------------------------------------------------------------------
 Nebraska Public Power District; Cooper Nuclear Station; Nemaha County,
                                   NE
------------------------------------------------------------------------
Docket No....................  50-298.
Application date.............  July 17, 2025.
ADAMS Accession No...........  ML25202A106.
Location in Application of     Pages 19-21 of Attachment 1.
 NSHC.

[[Page 53400]]

 
Brief Description of           The proposed amendment would revise
 Amendment.                     Cooper Nuclear Station Technical
                                Specification (TS) 3.8.2, ``AC
                                [Alternating Current] Sources--
                                Shutdown,'' and TS 3.8.3, ``Diesel Fuel
                                Oil, Lube Oil, and Starting Air,'' to
                                allow the fuel oil storage tanks to be
                                out of service for up to 14 days for the
                                purpose of performing the required
                                cleaning and inspection of the tanks. An
                                alternate fuel oil storage system will
                                be utilized during the tank inspection
                                evolution, as necessary, to supply the
                                required diesel generator day tank.
                                These TS changes would be applicable
                                during the 2026 Refuel Outage 34 while
                                in Mode 5.
Proposed Determination.......  NSHC.
Name of Attorney for           John C. McClure, Executive Vice President
 Licensee, Mailing Address.     External Affairs and General Counsel
                                Nebraska Public Power District, P.O. Box
                                499, Columbus, NE 68601.
NRC Project Manager,           Thomas Byrd, 301-415-3719.
 Telephone Number.
------------------------------------------------------------------------
  Pacific Gas and Electric Company; Diablo Canyon Nuclear Power Plant,
                Units 1 and 2; San Luis Obispo County, CA
------------------------------------------------------------------------
Docket Nos...................  50-275, 50-323.
Application date.............  August 27, 2025.
ADAMS Accession No...........  ML25239B075.
Location in Application of     Pages 4-6 of the Enclosure.
 NSHC.
Brief Description of           The proposed amendments would adopt
 Amendments.                    emergency action level scheme pursuant
                                to Nuclear Energy Institute (NEI) 99-01,
                                Revision 7, ``Development of Emergency
                                Action Levels for Non-Passive
                                Reactors.''
Proposed Determination.......  NSHC.
Name of Attorney for           Jennifer Post, Esq., Pacific Gas and
 Licensee, Mailing Address.     Electric Co., 77 Beale Street, Room
                                3065, Mail Code B30A, San Francisco, CA
                                94105.
NRC Project Manager,           Samson Lee, 301-415-3168.
 Telephone Number.
------------------------------------------------------------------------
   Tennessee Valley Authority; Sequoyah Nuclear Plant, Units 1 and 2;
   Hamilton County, TN; Tennessee Valley Authority; Watts Bar Nuclear
                  Plant, Units 1 and 2; Rhea County, TN
------------------------------------------------------------------------
Docket Nos...................  50-327, 50-328, 50-390, 50-391.
Application date.............  August 19, 2025.
ADAMS Accession No...........  ML25231A300.
Location in Application of     Pages E1-E3 of the Enclosure.
 NSHC.
Brief Description of           The proposed amendments would revise
 Amendments.                    Sequoyah Nuclear Plant, Units 1 and 2,
                                and Watts Bar Nuclear Plant, Units 1 and
                                2, technical specifications to eliminate
                                the periodic surveillance requirement to
                                verify that all required diesel
                                generators achieve rated frequency and
                                voltage within the specified time period
                                when started simultaneously, consistent
                                with Technical Specifications Task Force
                                (TSTF) Traveler TSTF-599-A, Revision 1,
                                ``Eliminate Periodic Surveillance Test
                                of Simultaneous Start of Redundant
                                Diesel Generators.''
Proposed Determination.......  NSHC.
Name of Attorney for           Rebecca Tolene (Acting), Executive VP and
 Licensee, Mailing Address.     General Counsel Tennessee Valley
                                Authority, 400 West Summit Hill Drive,
                                WT 6A, Knoxville, TN 37902.
NRC Project Manager,           Kimberly Green, 301-415-1627.
 Telephone Number.
------------------------------------------------------------------------
Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2; Rhea
                               County, TN
------------------------------------------------------------------------
Docket Nos...................  50-390, 50-391.
Application date.............  August 25, 2025.
ADAMS Accession No...........  ML25237A197.
Location in Application of     TSTF-26: pages E6-E7; TSTF-27: pages E10-
 NSHC.                          E11; TSTF-87: pages E14-E15; TSTF-96:
                                pages E1-E18; TSTF-116: pages E21-E22;
                                TSTF-197: pages E26-E27; TSTF-233: pages
                                E31-E32; TSTF-263: pages E35-E36; TSTF-
                                265: page E39; TSTF-272: pages E42-E43;
                                TSTF-280: pages E46-E47; TSTF-284: pages
                                E50-E51; TSTF-286: pages E56-E57; TSTF-
                                349, TSTF-361, and TSTF-438: pages E61-
                                E63; TSTF-352: pages E66-E68; TSTF-20:
                                pages E70-E71; TSTF-247: pages E73-E75;
                                TSTF-309: pages E77-E78.
Brief Description of           The proposed amendments would revise
 Amendments.                    various technical specifications (TS)
                                within the Watts Bar Nuclear Plant,
                                Units 1 and 2, TS Sections 3.4 and 3.9
                                by adopting the following Technical
                                Specifications Task Force (TSTF)
                                Travelers:
                                TSTF-26-A, Revision 0--``Revise
                                the Action for Minimum Temperature for
                                Criticality to match the
                                Applicability.''
                                TSTF-27-A, Revision 3--``Revise
                                SR [surveillance requirement] frequency
                                for Minimum Temperature for
                                Criticality.''
                                TSTF-87-A, Revision 2--``Revise
                                `RTBs [reactor trip breakers] open' &
                                `CRDM [control rod drive mechanism] de-
                                energized' Actions to `incapable of rod
                                withdrawal.' ''
                                TSTF-96-A, Revision 1--``Delete
                                the initial performance of the boron
                                concentration measurement with no source
                                range detectors.''
                                TSTF-116-A, Revision 2--``RCS
                                [reactor coolant system] Inventory
                                Balance SR: Steady State
                                Clarification.''
                                TSTF-197-A, Revision 2--
                                ``Require containment closure when
                                shutdown cooling requirements are not
                                met.''
                                TSTF-233-A, Revision 0--
                                ``Relocate LTOP [low-temperature
                                overpressure protection] Arming
                                Temperature to PTLR [pressure-
                                temperature limits report] (except for
                                Technical Specification [TS] 1.1).''

[[Page 53401]]

 
                                TSTF-263-A, Revision 3--
                                ``Correct usage of `required' components
                                and base ACTIONS on inoperable required
                                equipment.''
                                TSTF-265-A, Revision 2--
                                ``Clarify 3.4 `non-operating loop'
                                SRs.''
                                TSTF-272-A, Revision 1--
                                ``Refueling Boron Concentration
                                Clarification.''
                                TSTF-280-A, Revision 1--``Exempt
                                SRs on LTOP equipment not used to
                                satisfy the LCO [limiting condition for
                                operation].''
                                TSTF-284-A, Revision 3--``Add
                                `Met vs. Perform' to Specification 1.4,
                                Frequency.''
                                TSTF-286-A, Revision 2--``Define
                                `Operations Involving Positive
                                Reactivity Additions' '' (only TS
                                Sections 3.4 and 3.9).
                                TSTF-349-A, Revision 1--``Add
                                Note to LCO 3.9.5 Allowing Shutdown
                                Cooling Loops Removal from Operation.''
                                TSTF-352-A, Revision 1--
                                ``Provide Consistent Completion Time to
                                Reach MODE 4.''
                                TSTF-361-A, Revision 2--``Allow
                                standby SDC/RHR/DHR [shutdown cooling/
                                residual heat removal/decay heat
                                removal] loop to inoperable to support
                                testing.''
                                TSTF-438-A, Revision 0--
                                ``Clarify Exception Notes to be
                                Consistent with the Requirement Being
                                Excepted.''
                                TSTF-20-A, Revision 0--``Delete
                                extraneous Action from Refueling Cavity
                                Water Level.''
                                TSTF-247-A, Revision 0--
                                ``Provide separate condition entry for
                                each PORV [power-operated relief valve]
                                and block valve.''
                                TSTF-309, Revision 2--``Revise
                                Pressurizer PORV Actions to not require
                                cycling of block valve when closed for
                                isolation''
Proposed Determination.......  NSHC.
Name of Attorney for           Rebecca Tolene (Acting), Executive VP and
 Licensee, Mailing Address.     General Counsel Tennessee Valley
                                Authority, 400 West Summit Hill Drive,
                                WT 6A, Knoxville, TN 37902.
NRC Project Manager,           Kimberly Green, 301-415-1627.
 Telephone Number.
------------------------------------------------------------------------
 Vistra Operations Company LLC; Davis-Besse Nuclear Power Station, Unit
   1; Ottawa County, OH; Vistra Operations Company LLC ; Beaver Valley
   Power Station, Units 1 and 2; Beaver County, PA; Vistra Operations
   Company LLC; Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2;
Somervell County, TX; Vistra Operations Company LLC; Perry Nuclear Power
                     Plant, Unit 1; Lake County, OH
------------------------------------------------------------------------
Docket Nos...................  50-334, 50-346, 50-412, 50-440, 50-445,
                                50-446.
Application date.............  July 10, 2025.
ADAMS Accession No...........  ML25191A246.
Location in Application of     Pages 25-27 of the Enclosure.
 NSHC.
Brief Description of           The proposed amendments would modify
 Amendments.                    technical specification Definitions and
                                add a new ``Online Monitoring Program.''
                                The amendments propose to use online
                                monitoring (OLM) methodology as the
                                technical basis to switch from time-
                                based surveillance frequency for channel
                                calibrations to a condition-based
                                calibration frequency based on OLM
                                results.
Proposed Determination.......  NSHC.
Name of Attorney for           Roland Backhaus, Senior Lead Counsel-
 Licensee, Mailing Address.     Nuclear, Vistra Corp., 325 7th Street
                                NW, Suite 520, Washington, DC 20004.
NRC Project Manager,           Robert Kuntz, 301-415-3733.
 Telephone Number.
------------------------------------------------------------------------

III. Notice of Issuance of Amendments to Facility Operating Licenses 
and Combined Licenses

    During the period since publication of the last monthly notice, the 
Commission has issued the following amendments. The Commission has 
determined for each of these amendments that the application complies 
with the standards and requirements of the Atomic Energy Act of 1954, 
as amended (the Act), and the Commission's rules and regulations. The 
Commission has made appropriate findings as required by the Act and the 
Commission's rules and regulations in 10 CFR chapter I, which are set 
forth in the license amendment.
    A notice of consideration of issuance of amendment to facility 
operating license or combined license, as applicable, proposed NSHC 
determination, and opportunity for a hearing in connection with these 
actions, was published in the Federal Register as indicated in the 
safety evaluation for each amendment.
    Unless otherwise indicated, the Commission has determined that 
these amendments satisfy the criteria for categorical exclusion in 
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), 
no environmental impact statement or environmental assessment need be 
prepared for these amendments. If the Commission has prepared an 
environmental assessment under the special circumstances provision in 
10 CFR 51.22(b) and has made a determination based on that assessment, 
it is so indicated in the safety evaluation for the amendment.
    For further details with respect to each action, see the amendment 
and associated documents such as the Commission's letter and safety 
evaluation, which may be obtained using the ADAMS accession numbers 
indicated in the following table. The safety evaluation will provide 
the ADAMS accession numbers for the application for amendment and the 
Federal Register citation for any environmental assessment. All of 
these items can be accessed as described in the ``Obtaining Information 
and Submitting Comments'' section of this document.

                       License Amendment Issuances
------------------------------------------------------------------------
 
------------------------------------------------------------------------
  Arizona Public Service Company, et al.; Palo Verde Nuclear Generating
             Station, Units 1, 2, and 3; Maricopa County, AZ
------------------------------------------------------------------------
Docket Nos...................  50-528, 50-529, 50-530.

[[Page 53402]]

 
Amendment Date...............  September 22, 2025.
ADAMS Accession No...........  ML25254A064.
Amendment Nos................  226 (Unit 1), 226 (Unit 2), and 226 (Unit
                                3).
Brief Description of           The amendments revised Technical
 Amendments.                    Specification 5.6.5.b, ``Core Operating
                                Limits Report (COLR),'' to add Topical
                                Report WCAP-18240-P-A, ``Westinghouse
                                Thermal Design Procedure (WTDP),'' to
                                the list of referenced analytical
                                methods for the determination of reactor
                                core operating limits.
Public Comments Received as    No.
 to Proposed NSHC (Yes/No).
------------------------------------------------------------------------
 Florida Power & Light Company, et al.; St. Lucie Plant, Unit No. 2; St.
                            Lucie County, FL
------------------------------------------------------------------------
Docket No....................  50-389.
Amendment Date...............  September 26, 2025.
ADAMS Accession No...........  ML25241A191.
Amendment No.................  212.
Brief Description of           The amendment revised the St. Lucie
 Amendment.                     Plant, Unit No. 2, Technical
                                Specification (TS) 3.7.15, ``Spent Fuel
                                Pool Storage,'' and TS 4.3, ``Fuel
                                Storage,'' to support updated spent fuel
                                pool and new fuel vault criticality
                                analyses, which account for the impact
                                of planned transition to 24-month fuel
                                cycles on fresh and spent fuel storage.
Public Comments Received as    No.
 to Proposed NSHC (Yes/No).
------------------------------------------------------------------------
Florida Power & Light Company; Turkey Point Nuclear Generating Unit Nos.
                     3 and 4; Miami-Dade County, FL
------------------------------------------------------------------------
Docket Nos...................  50-250, 50-251.
Amendment Date...............  September 25, 2025.
ADAMS Accession No...........  ML25266A206.
Amendment Nos................  303 (Unit 3) and 297 (Unit 4).
Brief Description of           The amendments revised the technical
 Amendments.                    specifications for Turkey Point Nuclear
                                Generating Unit Nos. 3 and 4 by removing
                                the pressurizer heater group emergency
                                power supply requirements.
Public Comments Received as    No.
 to Proposed NSHC (Yes/No).
------------------------------------------------------------------------
  Tennessee Valley Authority; Sequoyah Nuclear Plant, Unit 2; Hamilton
                               County, TN
------------------------------------------------------------------------
Docket No....................  50-328.
Amendment Date...............  September 22, 2025.
ADAMS Accession No...........  ML25252A202.
Amendment No.................  367.
Brief Description of           The amendment revised the Sequoyah
 Amendment.                     Nuclear Plant (SQN), Unit 2, Technical
                                Specification Surveillance Requirement
                                (SR) 3.0.2, on a one-time basis, the
                                surveillance interval for SR 3.6.12.2
                                (Ice Condenser--Ice Mass Weighing) and
                                SR 3.6.12.3 (Ice Condenser Flow Passage
                                Inspection) that are normally performed
                                on an 18-month frequency in conjunction
                                with a refueling outage. The amendment
                                extended the due date for SRs 3.6.12.2
                                and 3.6.12.3 from August 14, 2026, and
                                August 12, 2026, respectively, to prior
                                to entering Mode 4 from the SQN, Unit 2,
                                Cycle 27, Refueling Outage but no later
                                than December 1, 2026.
Public Comments Received as    No.
 to Proposed NSHC (Yes/No).
------------------------------------------------------------------------


    Dated: November 19, 2025.
    For the Nuclear Regulatory Commission.
Hipolito Gonzalez,
Acting Deputy Director, Division of Operating Reactor Licensing, Office 
of Nuclear Reactor Regulation.
[FR Doc. 2025-20930 Filed 11-24-25; 8:45 am]
BILLING CODE 7590-01-P