[Federal Register Volume 84, Number 214 (Tuesday, November 5, 2019)]
[Notices]
[Pages 59654-59659]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-23805]


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NUCLEAR REGULATORY COMMISSION

[NRC-2019-0219]


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

AGENCY: Nuclear Regulatory Commission.

ACTION: Biweekly notice.

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SUMMARY: Pursuant to the Atomic Energy Act of 1954, as amended (the 
Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this 
regular biweekly 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 
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, notwithstanding the 
pendency before the Commission of a request for a hearing from any 
person.
    This biweekly notice includes all notices of amendments issued, or 
proposed to be issued, from October 8, 2019, to October 21, 2019. The 
last biweekly notice was published on October 22, 2019.

DATES: Comments must be filed by December 5, 2019. A request for a 
hearing or petitions for leave to intervene must be filed by January 6, 
2020.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0219. Address 
questions about NRC dockets IDs in Regulations.gov to Jennifer Borges; 
telephone: 301-287-9127; email: [email protected]. For technical 
questions, contact the individual 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: Lynn Ronewicz, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 
20555-0001; telephone: 301-415-1927, email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2019-0219, facility name, unit 
number(s), plant docket number, 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-2019-0219.
     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 Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to [email protected]. The ADAMS accession number for each 
document referenced (if it is available in ADAMS) is provided the first 
time that it is mentioned in this document.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2019-0219, facility name, unit 
number(s), plant docket number, 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

[[Page 59655]]

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. Background

    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 biweekly 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 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, 
notwithstanding the pendency before the Commission of a request for a 
hearing from any person.

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

    The Commission has made a proposed determination that the following 
amendment requests involve no significant hazards consideration. Under 
the Commission's regulations in Sec.  50.92 of title 10 of the Code of 
Federal Regulations (10 CFR), this means that operation of the facility 
in accordance with the proposed amendment 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 basis 
for this proposed determination for each amendment request is shown 
below.
    The Commission is seeking public comments on this proposed 
determination. Any comments received within 30 days after the date of 
publication of this notice will be considered in making any final 
determination.
    Normally, the Commission will not issue the amendment until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment 
involves no significant hazards consideration. In addition, the 
Commission may issue the amendment 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 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 no significant hazards 
consideration determination, any hearing will take place after 
issuance. The Commission expects that the need to take this action 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 
persons (petitioner) whose interest may be affected by this action may 
file a request for a hearing and petition for leave to intervene 
(petition) with respect to the 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. The NRC's regulations are accessible 
electronically from the NRC Library on the NRC's website at https://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of 
the regulations is available at the NRC's Public Document Room, located 
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first 
floor), Rockville, Maryland 20852. 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.
    As required by 10 CFR 2.309(d) the petition should specifically 
explain the reasons why intervention should be permitted with 
particular reference to the following general requirements for 
standing: (1) The name, address, and telephone number of the 
petitioner; (2) the nature of the petitioner's right to be made a party 
to the proceeding; (3) the nature and extent of the petitioner's 
property, financial, or other interest in the proceeding; and (4) the 
possible effect of any decision or order which may be entered in the 
proceeding on the petitioner's interest.
    In accordance with 10 CFR 2.309(f), the petition must also set 
forth the specific contentions which the petitioner seeks to have 
litigated in the proceeding. Each contention must consist of a specific 
statement of the issue of law or fact to be raised or controverted. In 
addition, the petitioner must provide a brief explanation of the bases 
for the contention and a concise statement of the alleged facts or 
expert opinion which support the contention and on which the petitioner 
intends to rely in proving the contention at the hearing. The 
petitioner must also provide references to the specific sources and 
documents on which the petitioner intends to rely to support its 
position on the issue. The petition must include sufficient information 
to show that a genuine dispute exists with the applicant or licensee on 
a material issue of law or fact. Contentions must be limited to matters 
within the scope of the proceeding. The contention must be one which, 
if proven, would entitle the petitioner to relief. A petitioner who 
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at 
least one contention will not be permitted to participate as a party.
    Those permitted to intervene become parties to the proceeding, 
subject to any limitations in the order granting leave to intervene. 
Parties have the opportunity to participate fully in the conduct of the 
hearing with respect to resolution of that party's admitted 
contentions, including the opportunity to present evidence, consistent 
with the NRC's regulations, policies, and procedures.
    Petitions must be filed no later than 60 days from the date of 
publication of this notice. 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). The petition must be filed in 
accordance with the filing instructions in the ``Electronic Submissions 
(E-Filing)'' section of this document.
    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. The final determination 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

[[Page 59656]]

an appropriate order or rule under 10 CFR part 2.
    A State, local governmental body, Federally-recognized Indian 
Tribe, or agency thereof, may submit a petition to the Commission to 
participate as a party under 10 CFR 2.309(h)(1). The petition should 
state the nature and extent of the petitioner's interest in the 
proceeding. The petition should be submitted to the Commission no later 
than 60 days from the date of publication of this notice. The petition 
must be filed in accordance with the filing instructions in the 
``Electronic Submissions (E-Filing)'' section of this document, and 
should meet the requirements for petitions set forth in this section, 
except that under 10 CFR 2.309(h)(2) a State, local governmental body, 
or Federally-recognized Indian Tribe, or agency thereof does not need 
to address the standing requirements in 10 CFR 2.309(d) if the facility 
is located within its boundaries. 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).
    If a hearing is granted, any person who is not a party to the 
proceeding and is not affiliated with or represented by a party may, at 
the discretion of the presiding officer, be permitted to make a limited 
appearance pursuant to the provisions of 10 CFR 2.315(a). A person 
making a limited appearance may make an oral or written statement of 
his or her position on the issues but may not otherwise participate in 
the proceeding. A limited appearance may be made at any session of the 
hearing or at any prehearing conference, subject to the limits and 
conditions as may be imposed by the presiding officer. Details 
regarding the opportunity to make a limited appearance will be provided 
by the presiding officer if such sessions are scheduled.

B. Electronic Submissions (E-Filing)

    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing and petition for leave to intervene (petition), any 
motion or other document filed in the proceeding prior to the 
submission of a request for hearing or petition to intervene, and 
documents filed by interested governmental entities that request to 
participate under 10 CFR 2.315(c), must be filed in accordance with the 
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR 
46562; August 3, 2012). 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. Detailed 
guidance on making electronic submissions may be found in the Guidance 
for Electronic Submissions to the NRC and on the NRC website at https://www.nrc.gov/site-help/e-submittals.html. Participants may not submit 
paper copies of their filings unless they seek an exemption in 
accordance with the procedures described below.
    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 hearing in this 
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. Once a participant has obtained a 
digital ID certificate and a docket has been created, the participant 
can then submit adjudicatory documents. Submissions must be in Portable 
Document Format (PDF). Additional guidance on PDF 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. Eastern Time on the due date. Upon receipt of 
a transmission, the E-Filing system time-stamps the document and sends 
the submitter an email notice confirming receipt of the document. The 
E-Filing system also distributes an email notice 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 so that they can 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., Eastern Time, Monday through Friday, excluding government 
holidays.
    Participants who believe that they have a 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 by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, 11555 
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and 
Adjudications Staff. Participants filing adjudicatory documents in this 
manner are responsible for serving the document on all other 
participants. Filing is considered complete by first-class mail as of 
the time of deposit in the mail, or by courier, express mail, or 
expedited delivery service upon depositing the document with the 
provider of the service. A presiding officer, having granted an 
exemption request from using E-Filing, may require a participant or 
party to use E-Filing if the presiding officer subsequently determines 
that the reason for granting the exemption from use of E-Filing no 
longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the 
Commission or the presiding officer. If you do not have an NRC-issued 
digital ID certificate as described above, click ``cancel'' when the 
link requests certificates and you will be automatically directed to 
the NRC's electronic hearing dockets where you will be able to access 
any publicly available documents in a particular

[[Page 59657]]

hearing docket. Participants are requested not to include personal 
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. For example, in some 
instances, individuals provide home addresses in order to demonstrate 
proximity to a facility or site. 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 are 
requested not to include copyrighted materials in their submission.
    For further details with respect to these license amendment 
applications, see the application for amendment which is available for 
public inspection in ADAMS and at the NRC's PDR. For additional 
direction on accessing information related to this document, see the 
``Obtaining Information and Submitting Comments'' section of this 
document.

Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba 
Nuclear Station, Units 1 and 2, York County, South Carolina

    Date of amendment request: September 4, 2019. A publicly available 
version is in ADAMS under Accession No. ML19247B321.
    Description of amendment request: The amendments would modify 
Technical Specification (TS) 3.0, ``Surveillance Requirement (SR) 
Applicability,'' to correct a typographical error introduced by License 
Amendment Nos. 235 and 231. Specifically, SR 3.0.5 is proposed to be 
revised to refer to Limiting Condition for Operation (LCO) 3.0.9, 
instead of 3.0.8. The proposed change is administrative in nature.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change to revise SR 3.0.5 to refer to LCO 3.0.9 is 
administrative in nature and does not change the technical content 
of the TS. The proposed change does not adversely affect accident 
initiators or precursors nor alter the design assumptions, 
conditions or configurations of the facility. The proposed change 
does not alter or prevent the capability of structures, systems and 
components (SSCs) to perform their intended function to mitigate the 
consequences of an initiating events within the assumed acceptance 
limits.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed change to revise SR 3.0.5 to refer to LCO 3.0.9 is 
administrative in nature and does not change the technical content 
of the TS. The proposed change does not alter the design 
requirements of any SSC or its function during accident conditions. 
The proposed change does not involve a physical alteration to the 
plant or any changes in methods governing normal plant operation. 
The proposed change does not alter any assumptions made in the 
safety analysis.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in the margin of safety?
    Response: No.
    The proposed change to revise SR 3.0.5 to refer to LCO 3.0.9 is 
administrative in nature and does not change the technical content 
of the TS. The proposed change does not alter the way safety limits, 
limiting safety system settings or limiting conditions for operation 
are determined. The safety analysis acceptance criteria are not 
affected by the proposed change. The proposed change will not result 
in plant operation in a configuration outside the design basis and 
does not adversely affect systems that respond to safely shutdown 
the plant and maintain the plant in a safety shutdown condition.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Kate B. Nolan, Deputy General Counsel, Duke 
Energy Carolinas, LLC., 550 South Tryon Street--DEC45A, Charlotte, NC 
28202-1802.
    NRC Branch Chief: Michael T. Markley.

Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba 
Nuclear Station (Catawba), Units 1 and 2, York County, South Carolina

    Date of amendment request: July 2, 2019. A publicly available 
version is in ADAMS under Accession No. ML19183A038.
    Description of amendment request: The amendments would modify 
Technical Specification (TS) 3.4.3, ``RCS [Reactor Coolant System] 
Pressure and Temperature (P/T) Limits.'' Specifically, the P/T limit 
curves in Figures 3.4.3-1 and 3.4.3-2 for Unit 1 would be updated since 
the existing Unit 1 curves are only applicable up to 30.7 full power 
effective years (EFPY), which is expected to be reached during 
Operating Cycle 26 (early 2021). The new Unit 1 (P/T) limit curves will 
be applicable until 42.7 EFPY. Although the proposed change only 
impacts Unit 1, the request is docketed under both Catawba, Units 1 and 
2, since the TSs are common to both Units 1 and 2.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change revises TS 3.4.3 to reflect updated P/T 
limit curves in Figures 3.4.3-1 (UNIT 1 ONLY) and 3.4.3-2 (UNIT 1 
ONLY) that are applicable until 42.7 EFPY. The proposed change does 
not involve physical changes to the plant or alter the reactor 
coolant system (RCS) pressure boundary (i.e., there are no changes 
in operating pressure, materials or seismic loading). The proposed 
P/T limit curves and Adjusted Reference Temperature (ART) values for 
TS 3.4.3 with an applicability term of 42.7 EFPY provide continued 
assurance that the fracture toughness of the reactor pressure vessel 
(RPV) is consistent with analysis assumptions and NRC regulations. 
The methodology used to develop the proposed P/T limit curves 
provides assurance that the probability of a rapidly propagating 
failure will be minimized. The proposed P/T limit curves, with the 
applicability term of 42.7 EFPY, will continue to prohibit operation 
in regions where it is possible for brittle fracture of reactor 
vessel materials to occur, thereby assuring that the integrity of 
the RCS pressure boundary is maintained.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed change revises TS 3.4.3 to reflect updated P/T 
limit curves in Figures 3.4.3-1 (UNIT 1 ONLY) and 3.4.3-2 (UNIT 1 
ONLY) that are applicable until 42.7 EFPY. The proposed change does 
not affect the design or assumed accident performance of any 
structure, system or component or

[[Page 59658]]

introduce any new modes of system operation or failure modes. 
Compliance with the proposed P/T limit curves will provide 
sufficient protection against brittle fracture of reactor vessel 
materials to assure that the RCS pressure boundary performs as 
previously evaluated.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in the margin of safety?
    Response: No.
    The proposed change revises TS 3.4.3 to reflect updated P/T 
limit curves in Figures 3.4.3-1 (UNIT 1 ONLY) and 3.4.3-2 (UNIT 1 
ONLY) that are applicable until 42.7 EFPY. CNS [Catawba Nuclear 
Station] complies with applicable regulations (i.e., 10 CFR 50, 
Appendices G and H) and adheres to Nuclear Regulatory Commission 
(NRC)-approved methodologies (i.e., Regulatory Guides 1.99 and 
1.190) with respect to the proposed P/T limit curves in TS 3.4.3 in 
order to provide an adequate margin of safety to the conditions at 
which brittle fracture may occur. The proposed P/T limit curves for 
CNS Unit 1, with an applicability term of 42.7 EFPY, will continue 
to provide as assurance that the P/T limits are not exceeded.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Kate B. Nolan, Deputy General Counsel, Duke 
Energy Carolinas, LLC, 550 South Tryon Street--DEC45A, Charlotte, NC 
28202-1802.
    NRC Branch Chief: Michael T. Markley.

Energy Northwest, Docket No. 50-397, Columbia Generating Station, 
Benton County, Washington

    Date of amendment request: August 15, 2019, as supplemented by 
letter dated September 12, 2019. Publicly-available versions are in 
ADAMS under Accession Nos. ML19227A397, and ML19255H995, respectively.
    Description of amendment request: The amendment would adopt 
Technical Specifications Task Force (TSTF) Traveler TSTF-563, ``Revise 
Instrument Testing Definitions to Incorporate the Surveillance 
Frequency Control Program,'' which would revise the Technical 
Specification (TS) definitions of Channel Calibration and Channel 
Functional Test to allow the required frequency for testing these 
components or devices in each step to be determined in accordance with 
the TS Surveillance Frequency Control Program.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change revises the TS definitions of Channel 
Calibration and Channel Functional Test to allow the frequency for 
testing the components or devices in each step to be determined in 
accordance with the TS Surveillance Frequency Control Program. All 
components in the channel continue to be calibrated. The frequency 
at which a channel calibration is performed is not an initiator of 
any accident previously evaluated, so the probability of an accident 
is not affected by the proposed change. The channels surveilled in 
accordance with the affected definitions continue to be required to 
be operable and the acceptance criteria of the surveillances are 
unchanged. As a result, any mitigating functions assumed in the 
accident analysis will continue to be performed.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any previously evaluated?
    Response: No.
    The proposed change revises the TS definitions of Channel 
Calibration and Channel Functional Test to allow the frequency for 
testing the components or devices in each step to be determined in 
accordance with the TS Surveillance Frequency Control Program. [A] 
physical alteration of the plant (i.e., no new or different type of 
equipment will be installed) [does not occur for this proposed 
change]. No credible new failure mechanisms, malfunctions, or 
accident initiators not considered in the design and licensing bases 
are introduced. The changes do not alter assumptions made in the 
safety analysis. The proposed changes are consistent with the safety 
analysis assumptions.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed change revises the TS definitions of Channel 
Calibration and Channel Functional Test to allow the frequency for 
testing the components or devices in each step to be determined in 
accordance with the TS Surveillance Frequency Control Program. The 
Surveillance Frequency Control Program assures sufficient safety 
margins are maintained, and that that design, operation, 
surveillance methods, and acceptance criteria specified in 
applicable codes and standards (or alternatives approved for use by 
the NRC) will continue to be met as described in the plants' 
licensing basis. The proposed change does not adversely affect 
existing plant safety margins or the reliability of the equipment 
assumed to operate in the safety analysis. As such, there are no 
changes being made to safety analysis assumptions, safety limits, or 
limiting safety system settings that would adversely affect plant 
safety as a result of the proposed change. Margins of safety are 
unaffected by method of determining surveillance test intervals 
under an NRC-approved licensee-controlled program.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: William A. Horin, Esq., Winston & Strawn, 
1700 K Street NW, Washington, DC 20006-3817.
    NRC Branch Chief: Robert J. Pascarelli.

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

    During the period since publication of the last biweekly 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 no 
significant hazards consideration determination, and opportunity for a 
hearing in connection with these actions was published in the Federal 
Register as indicated.
    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

[[Page 59659]]

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.
    For further details with respect to the action see (1) the 
applications for amendment, (2) the amendment, and (3) the Commission's 
related letter, Safety Evaluation, and/or Environmental Assessment, as 
indicated. All of these items can be accessed as described in the 
``Obtaining Information and Submitting Comments'' section of this 
document.

Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, 
Braidwood Station, Units 1 and 2 (Braidwood), Will County, Illinois

Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455, 
Byron Station, Unit Nos. 1 and 2 (Byron), Ogle County, Illinois

Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power 
Station, Unit No. 1 (Clinton), DeWitt County, Illinois

Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden 
Nuclear Power Station, Units 2 and 3 (Dresden), Grundy County, Illinois

Exelon Generation Company, LLC and Exelon FitzPatrick, LLC, Docket No. 
50-333, James A. FitzPatrick Nuclear Power Plant (FitzPatrick), Oswego 
County, New York

Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle 
County Station, Units 1 and 2 (LaSalle), LaSalle County, Illinois

Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad 
Cities Nuclear Power Station, Units 1 and 2 (Quad Cities), Rock Island 
County, Illinois

    Date of amendment request: November 1, 2018.
    Brief description of amendments: The amendments revised the 
Technical Specifications for these facilities to eliminate secondary 
completion times. The changes are based on Technical Specifications 
Task Force (TSTF) Traveler TSTF-439, Revision 2, ``Eliminate Second 
Completion Times Limiting Time from Discovery of Failure to Meet an LCO 
[Limiting Condition for Operation]'' (ADAMS Accession No. ML051860296). 
The amendment for the FitzPatrick also deleted an obsolete footnote for 
a one-time action.
    Date of issuance: October 8, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of the date of issuance.
    Amendment Nos.: Braidwood--203/203, Byron--209/209, Clinton--227, 
Dresden--262/255, FitzPatrick--329, LaSalle--239/225, and Quad Cities--
275/270. A publicly-available version is in ADAMS under Accession No. 
ML19266A527. Documents related to these amendments are listed in the 
Safety Evaluation enclosed with the amendments.
    Facility Operating License Nos. NPF-72, NPF-77, NPF-37, NPF-66, 
NPF-62, DPR-19, DPR-25, DPR-59, NPF-11, NPF-18, DPR-29, and DPR-30: The 
amendments revised the Facility Operating Licenses and Technical 
Specifications.
    Date of initial notice in Federal Register: January 30, 2019 (84 FR 
493).
    The Commission's related evaluation of the amendments is contained 
in a safety evaluation dated October 8, 2019.
    No significant hazards consideration comments received: No.

Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald 
C. Cook Nuclear Plant (Cook Nuclear Plant), Unit Nos. 1 and 2 (CNP), 
Berrien County, Michigan

    Date of amendment request: December 11, 2018.
    Brief description of amendments: The amendments revised the Cook 
Nuclear Plant Environmental Protection Plan to reflect a Michigan state 
requirement to obtain and maintain a Renewable Operating Permit for the 
possession and operation of specified stationary sources of air 
pollutants
    Date of issuance: October 15, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: Unit 1--347; Unit 2--328. A publicly-available 
version is in ADAMS under Accession No. ML19259A054; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Facility Operating License Nos. DPR-58 and DPR-74: The amendments 
revised the Renewed Facility Operating Licenses, including the 
Environmental Technical Specifications included as Appendix B.
    Date of initial notice in Federal Register: March 26, 2019 (84 FR 
11339).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated October 15, 2019.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 28th day of October 2019.

    For the Nuclear Regulatory Commission.
Gregory F. Suber,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2019-23805 Filed 11-4-19; 8:45 am]
BILLING CODE 7590-01-P