[Federal Register Volume 83, Number 79 (Tuesday, April 24, 2018)]
[Notices]
[Pages 17858-17867]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-08070]


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NUCLEAR REGULATORY COMMISSION

[NRC-2018-0073]


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 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.
    This biweekly notice includes all notices of amendments issued, or 
proposed to be issued, from March 27 to April 9, 2018. The last 
biweekly notice was published on April 10, 2018.

DATES: Comments must be filed by May 24, 2018. A request for a hearing 
must be filed by June 25, 2018.

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):
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0073. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER

[[Page 17859]]

INFORMATION CONTACT section of this document.
     Mail comments to: May Ma, Office of Administration, Mail 
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.
    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: Beverly Clayton, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 
20555-0001; telephone: 301-415-3475, email: [email protected].

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2018-0073, 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 http://www.regulations.gov and search for Docket ID NRC-2018-0073.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then 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-2018-0073, 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 http://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

    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 http://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 under the Act 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 that 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

[[Page 17860]]

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 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 http://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 http://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 http://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

[[Page 17861]]

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 http://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 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.

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

    Date of amendment request: February 26, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18057B125.
    Description of amendment request: The proposed amendment would add, 
delete, modify and replace numerous technical specification (TS) 
requirements related to operations that have the potential for draining 
the reactor vessel (OPDRVs) with new requirements on reactor pressure 
vessel water inventory control (RPV WIC) to protect TS Safety Limit 
2.1.1.3. The proposed changes are based on Technical Specifications 
Task Force (TSTF) traveler TSTF-542, ``Reactor Pressure Vessel Water 
Inventory Control.''
    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 replaces existing TS requirements related to 
OPDRVs with new requirements on RPV WIC that will protect Safety 
Limit 2.1.1.3. Draining of RPV water inventory in Mode 4 (i.e., cold 
shutdown) and Mode 5 (i.e., refueling) is not an accident previously 
evaluated and, therefore, replacing the existing TS controls to 
prevent or mitigate such an event with a new set of controls has no 
effect on any accident previously evaluated. RPV water inventory 
control in Mode 4 or Mode 5 is not an initiator of any accident 
previously evaluated. The existing OPDRV controls or the proposed 
RPV WIC controls are not mitigating actions assumed in any accident 
previously evaluated.
    The proposed change reduces the probability of an unexpected 
draining event (which is not a previously evaluated accident) by 
imposing new requirements on the limiting time in which an 
unexpected draining event could result in the reactor vessel water 
level dropping to the top of the active fuel (TAF). These controls 
require cognizance of the plant configuration and control of 
configurations with unacceptably short drain times. These 
requirements reduce the probability of an unexpected draining event. 
The current TS requirements are only mitigating actions and impose 
no requirements that reduce the probability of an unexpected 
draining event.
    The proposed change reduces the consequences of an unexpected 
draining event (which is not a previously evaluated accident) by 
requiring an Emergency Core Cooling System (ECCS) subsystem to be 
operable at all times in Modes 4 and 5. The current TS requirements 
do not require any water injection systems, ECCS or otherwise, to be 
operable in certain conditions in Mode 5. The change in requirement 
from two ECCS subsystems to one ECCS subsystem in Modes 4 and 5 does 
not significantly affect the consequences of an unexpected draining 
event because the proposed Actions ensure equipment is available 
within the limiting drain time that is as capable of mitigating the 
event as the current requirements. The proposed controls provide 
escalating compensatory measures to be established as calculated 
drain times decrease, such as verification of a second method of 
water injection and additional confirmations that secondary 
containment and/or filtration would be available if needed.
    The proposed change reduces or eliminates some requirements that 
were determined to be unnecessary to manage the consequences of an 
unexpected draining event, such as automatic initiation of an ECCS 
subsystem and control room ventilation. These changes do not affect 
the consequences of any accident previously evaluated since a 
draining event in Modes 4 and 5 is not a previously evaluated 
accident and the requirements are not needed to adequately respond 
to a draining event.
    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 replaces existing TS requirements related to 
OPDRVs with new requirements on RPV WIC that will protect Safety 
Limit 2.1.1.3. The proposed change will not alter the design 
function of the equipment involved. Under the proposed change, some 
systems that are currently

[[Page 17862]]

required to be operable during OPDRVs would be required to be 
available within the limiting drain time or to be in service 
depending on the limiting drain time. Should those systems be unable 
to be placed into service, the consequences are no different than if 
those systems were unable to perform their function under the 
current TS requirements.
    The event of concern under the current requirements and the 
proposed change is an unexpected draining event. The proposed change 
does not create new failure mechanisms, malfunctions, or accident 
initiators that would cause a draining event or a new or different 
kind of accident not previously evaluated or included in the design 
and licensing bases.
    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 replaces existing TS requirements related to 
OPDRVs with new requirements on RPV WIC. The current requirements do 
not have a stated safety basis and no margin of safety is 
established in the licensing basis. The safety basis for the new 
requirements is to protect Safety Limit 2.1.1.3. New requirements 
are added to determine the limiting time in which the RPV water 
inventory could drain to the top of the fuel in the reactor vessel 
should an unexpected draining event occur. Plant configurations that 
could result in lowering the RPV water level to the TAF within one 
hour are now prohibited. New escalating compensatory measures based 
on the limiting drain time replace the current controls. The 
proposed TS establish a safety margin by providing defense-in-depth 
to ensure that the Safety Limit is protected and to protect the 
public health and safety. While some less restrictive requirements 
are proposed for plant configurations with long calculated drain 
times, the overall effect of the change is to improve plant safety 
and to add safety margin.
    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: Tamra Domeyer, Associate General Counsel, 
Exelon Nuclear, 4300 Winfield Road, Warrenville, IL 60555.
    NRC Branch Chief: David J. Wrona.

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

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

Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert 
Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland

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

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

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

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

Exelon Generation Company, LLC, Docket Nos. 50-352 and No. 50-353, 
Limerick Generating Station, Unit Nos. 1 and 2, Montgomery County, 
Pennsylvania

Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine 
Mile Point Nuclear Station, Unit Nos. 1 and 2, Oswego County, New York

Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
277 and 50-278, Peach Bottom Atomic Power Station, Unit Nos. 2 and 3, 
York and Lancaster Counties, Pennsylvania

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

Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear 
Power Plant, Wayne County, New York

Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island 
Nuclear Station, Unit 1, Dauphin County, Pennsylvania

    Date of amendment request: March 1, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18060A266.
    Description of amendment request: The amendments would revise the 
technical specifications for each facility to relocate the staff 
qualification requirements to the Exelon Generation Company, LLC (EGC) 
quality assurance topical report.
    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. Will operation of the facility in accordance with the 
proposed amendment involve a significant increase in the probability 
or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes do not make any physical changes to the 
plants, are administrative in nature, and do not alter accident 
analysis assumptions, add any initiators or affect the function of 
plant systems, or the manner in which systems are operated, 
maintained, tested, or inspected. The proposed changes do not 
require any plant modifications which affect the performance 
capability of the structures, systems and components relied upon to 
mitigate the consequences of postulated accidents. The unit/
facility/plant staff qualification requirements remain the same and 
are being relocated from the Technical Specifications (TS) to the 
EGC Quality Assurance Topical Report (QATR).
    Based on the above discussion, EGC concludes that the proposed 
changes do not involve a significant increase in the probability or 
consequences of an accident previously evaluated.
    2. Will the operation of the facility in accordance with the 
proposed amendment create the possibility of a new or different kind 
of accident from any accident previously evaluated?
    Response: No.
    The proposed changes do not involve changes to unit/facility/
plant staff selection, qualification and training programs, are 
administrative in nature, and do not impact physical plant systems. 
The qualification standards are being relocated from the TS to the 
EGC QATR. As a result, the ability of the plant to respond to and 
mitigate accidents is unchanged by the proposed changes. The 
proposed changes do not alter accident analysis assumptions, add any 
initiators, or affect the function of plant systems or the manner in 
which systems are operated, maintained, modified, tested, or 
inspected.
    Based on the above discussion, EGC concludes that the proposed 
changes do not create the possibility of a new or different kind of 
accident from any accident previously evaluated.
    3. Will operation of the facility in accordance with the 
proposed amendment involve a significant reduction in a margin of 
safety?
    Response: No.
    The proposed changes are administrative in nature. The proposed 
changes do not affect plant design, hardware, system operation, or 
procedures for accident mitigation systems. The proposed changes do 
not impact any plant safety margins that are established in existing 
limiting conditions for operation, limiting safety systems settings 
and specified

[[Page 17863]]

safety limits. There are no changes in the established safety 
margins of these systems. The proposed changes do not impact the 
performance or proficiency requirements for licensed operators or 
unit/facility/plant staff, since the qualification standards are not 
changing and are only being relocated from the TS to the EGC QATR. 
As a result, the ability of the plant to respond to and mitigate 
accidents is unchanged by the proposed changes. Therefore, these 
proposed changes do not involve a significant reduction in a margin 
of safety.
    Based on the above discussion, EGC concludes that the proposed 
changes do 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 
requested amendments involve no significant hazards consideration.
    Attorney for licensee: Tamra Domeyer, Associate General Counsel, 
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 
60555.
    NRC Branch Chief: David J. Wrona.

FirstEnergy Nuclear Operating Company, Docket No. 50-440, Perry Nuclear 
Power Plant, Unit No. 1, Lake County, Ohio

    Date of amendment request: February 14, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18045A195.
    Description of amendment request: The proposed amendment would 
revise Technical Specification Surveillance Requirement 3.3.1.1.2 to 
verify that the calculated power is no more than 2 percent greater than 
the average power range monitor (APRM) channel output when operating at 
greater than or equal to 23.8 percent of rated thermal power. The 
proposed change is based on Technical Specifications Task Force (TSTF) 
traveler TSTF-546, ``Revise APRM Channel Adjustment Surveillance 
Requirement.''
    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 APRM system and the RPS [reactor protection system] are not 
initiators of any accidents previously evaluated. As a result, the 
proposed change does not affect the probability of any accident 
previously evaluated. The APRM system and the RPS functions act to 
mitigate the consequences of accidents previously evaluated. The 
reliability of APRM system and the RPS is not significantly affected 
by removing the gain adjustment requirement on the APRM channels 
when the APRMs are calibrated conservatively with respect to the 
calculated heat balance. This is because the actual core thermal 
power at which the reactor will automatically trip is lower, thereby 
increasing the margin to the core thermal limits and the limiting 
safety system settings assumed in the safety analyses. The 
consequences of an accident during the adjustment of the APRM 
instrumentation are no different from those during the existing 
surveillance testing period or the existing time allowed to restore 
the instruments to operable status. As a result, the ability of the 
APRM system and the RPS to mitigate any accident previously 
evaluated is not significantly affected.
    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 does not alter the protection system design, 
create new failure modes, or change any modes of operation. The 
proposed change does not involve a physical alteration of the plant; 
no new or different kind of equipment will be installed. 
Consequently, there are no new initiators that could result in a new 
or different kind of accident.
    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 a margin of safety?
    Response: No.
    The margin of safety provided by the APRM system and the RPS is 
to ensure that the reactor is shut down automatically when plant 
parameters exceed the setpoints for the system. Any reduction in the 
margin of safety resulting from the adjustment of the APRM channels 
while continuing operation is considered to be offset by delaying a 
plant shutdown (i.e., a transient) for a short time with the APRM 
system, the primary indication of core power and an input to the 
RPS, not calibrated. Additionally, the short time period required 
for adjustment is consistent with the time allowed by Technical 
Specifications to restore the core power distribution parameters to 
within limits and is acceptable based on the low probability of a 
transient or design basis accident occurring simultaneously with 
inaccurate APRM channels.
    The proposed change does not alter setpoints or limits 
established or assumed by the accident analyses. The Technical 
Specifications continue to require operability of the RPS functions, 
which provide core protection for postulated reactivity insertion 
events occurring during power operating conditions consistent with 
the plant safety analyses.
    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: David W. Jenkins, Attorney, FirstEnergy 
Corporation, Mail Stop A-GO-15, 76 South Main Street, Akron, OH 44308.
    NRC Branch Chief: David J. Wrona.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant, Unit Nos. 3 and 4, Burke County, 
Georgia

    Date of amendment request: January 31, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18031B181.
    Description of amendment request: The amendment request proposes to 
depart from the approved combined license (COL) Appendix A, Technical 
Specifications. The proposed changes revise COL Appendix A, 
Surveillance Requirements (SR) 3.8.1.2 to identify that the required 
minimum amperage output for the battery chargers is 150 amps. 
Additionally, the proposed changes revise COL Appendix A, SR 3.8.7.6 to 
align the test frequency with the expected life of the AP1000 Class 1E 
batteries. This submittal requests approval of the license amendment 
necessary to implement these changes.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR50.91(a), the licensee has provided 
its analysis of the issue of no significant hazards consideration, 
which is presented below with NRC staff's edits in square brackets:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The changes do not involve an interface with any [structure, 
system, and component (SSC)] accident initiator or initiating 
sequence of events, and thus, the probabilities of the accidents 
evaluated in the plant-specific [Updated Final Safety Analysis 
Report (UFSAR)] are not affected. The proposed changes do not 
involve a change to any mitigation sequence or the predicted 
radiological releases due to postulated accident conditions, thus, 
the consequences of the accidents evaluated in the UFSAR are not 
affected. Therefore, the proposed amendment does not involve a 
significant increase in the probability or consequences of an 
accident previously evaluated.

[[Page 17864]]

    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 changes do not adversely affect any system or 
design function or equipment qualification as the change does not 
modify any SSCs that prevent safety functions from being performed. 
The changes do not introduce a new failure mode, malfunction or 
sequence of events that could adversely affect safety or safety-
related equipment. Therefore, the proposed amendment does not create 
the possibility of a new or different kind of accident from accident 
previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed changes would not affect any safety-related design 
code, function, design analysis, safety analysis input or result, or 
existing design/safety margin. No safety analysis or design basis 
acceptance limit/criterion is challenged or exceed the requested 
changes. Therefore, the proposed amendment 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: M. Stanford Blanton, Balch & Bingham LLP, 
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
    NRC Branch Chief: Jennifer Dixon-Herrity.

III. 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 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.

Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear 
Power Plant, Unit 1, Wake and Chatham Counties, North Carolina

    Date of amendment request: May 22, 2017, as supplemented by letters 
dated October 30 and November 29, 2017.
    Brief description of amendment: The amendment revised the licensing 
basis as described in Updated Final Safety Analysis Report to provide 
gap release fractions for high-burnup fuel rods that exceed the 6.3 
kilowatt per foot linear heat generation rate limit detailed in Table 3 
of Regulatory Guide 1.183 (ADAMS Accession No. ML003716792).
    Date of issuance: March 26, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days of issuance.
    Amendment No.: 163. A publicly-available version is in ADAMS under 
Accession No. ML18045A060; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-63: Amendment revised 
the Renewed Facility Operating License.
    Date of initial notice in Federal Register: August 29, 2017 (82 FR 
41067). The supplemental letters dated October 30 and November 29, 
2017, provided additional information that clarified the application, 
did not expand the scope of the application as originally noticed, and 
did not change the staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 26, 2018.
    No significant hazards consideration comments received: No.

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

    Date of application for amendment: March 27, 2017, as supplemented 
by letter dated January 2, 2018.
    Brief description of amendment: The amendment revised CGS Technical 
Specification (TS) 5.5.12, ``Primary Containment Leakage Rate Testing 
Program,'' in accordance with Nuclear Energy Institute (NEI) 94-01, 
Revision 3-A, ``Industry Guideline for Implementing Performance-Based 
Option of 10 CFR part 50, Appendix J,'' July 2012, and the conditions 
and limitations specified in NEI 94-01, Revision 2-A, ``Industry 
Guideline for Implementing Performance-Based Option of 10 CFR part 50, 
Appendix J,'' dated October 2008, which serves as the guidance document 
for implementation of performance-based Option B of 10 CFR part 50, 
Appendix J.
    Date of issuance: March 30, 2018.
    Effective date: As of its date of issuance and shall be implemented 
within 120 days from the date of issuance.
    Amendment No.: 247. A publicly-available version is in ADAMS under 
Accession No. ML18052B185; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-21: The amendment 
revised the Renewed Facility Operating License and TSs.
    Date of initial notice in Federal Register: June 6, 2017 (82 FR 
26131). The supplemental letter dated January 2, 2018, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the NRC staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 30, 2018.
    No significant hazards consideration comments received: No.

Entergy Nuclear Operations, Inc., Docket No. 50-271, Vermont Yankee 
Nuclear Power Station, Vernon, Vermont

    Date of amendment request: May 15, 2017, as supplemented by letter 
dated November 16, 2017.
    Brief description of amendment: The amendment is for a revision to 
the site emergency plan and emergency action

[[Page 17865]]

level scheme to reflect an Independent Spent Fuel Storage Instillation 
(ISFSI)-only configuration for the storage of spent nuclear fuel onsite 
once all of the spent nuclear fuel is placed in the ISFSI in 2018.
    Date of issuance: March 30, 2018.
    Effective date: This license amendment is effective as of the date 
the licensee notifies the NRC in writing that all spent nuclear fuel 
assemblies have been transferred out of the spent fuel pool and have 
been placed in dry storage within the ISFSI. The license amendment 
shall be implemented within 60 days of the effective date.
    Amendment No.: 267. A publicly-available version is in ADAMS under 
Accession No. ML18053A111; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. DPR-28: The amendment revised the 
Facility Operating License.
    Date of initial notice in Federal Register: July 18, 2017 (82 FR 
32879). The supplemental letter dated November 16, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 30, 2018.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point 
Nuclear Station, Unit 2, Oswego County, New York

    Date of amendment request: February 28, 2017, as supplemented by 
letters dated November 3, December 27, 2017, January 12, and February 
6, 2018.
    Brief description of amendment: The amendment revises the Nine Mile 
Point Nuclear Station, Unit 2, Technical Specifications by replacing 
the existing specifications related to ``operations with a potential 
for draining the reactor vessel,'' with revised requirements for 
reactor pressure vessel water inventory control to protect Safety Limit 
2.1.1.3, which requires reactor vessel water level to be greater than 
the top of active irradiated fuel. The revisions, with variations as 
noted in the license amendment request, are based on the NRC-approved 
Technical Specifications Task Force Traveler TSTF-542, Revision 2, 
``Reactor Pressure Vessel Water Inventory Control'' (ADAMS Accession 
No. ML16074A448).
    Date of issuance: March 28, 2018.
    Effective date: As of the date of issuance and shall be implemented 
no later than the start of the Nine Mile Point Nuclear Station, Unit 2, 
spring 2018, refueling outage.
    Amendment No.: 168. A publicly-available version is in ADAMS under 
Accession No. ML18073A364; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-69: Amendment revised 
the Renewed Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: April 25, 2017 (82 FR 
19102). The supplements dated November 3, December 27, 2017, January 
12, and February 6, 2018, provided additional information that 
clarified the application, did not expand the scope of the application 
as originally noticed, and did not change the NRC staff's original 
proposed no significant hazards consideration determination.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 28, 2018.
    No significant hazards consideration comments received: No.

Florida Power & Light Company, Docket No. 50-250, Turkey Point Nuclear 
Generating Unit No. 3, Miami-Dade County, Florida

    Date of amendment request: December 18, 2017, as supplemented by 
letter dated February 16, 2018.
    Brief description of amendment: The amendment revised the Technical 
Specifications to allow a one-time extension of the allowable outage 
time for the Unit 3 Containment Spray System from 72 hours to 14 days.
    Date of issuance: April 3, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment No.: 280. A publicly-available version is in ADAMS under 
Accession No. ML18075A348; documents related to the amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-31: Amendment revised 
the Renewed Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: January 30, 2018 (83 FR 
4285). The supplemental letter dated February 16, 2018, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated April 3, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: May 23, 2017, as supplemented by letter 
dated December 8, 2017.
    Brief description of amendments: The amendments change the 
emergency plan for the Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2, 
by revising the emergency action level scheme to one based on the 
Nuclear Energy Institute (NEI) document NEI 99-01, Revision 6, 
``Development of Emergency Action Levels for Non-Passive Reactors.''
    Date of issuance: April 5, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days of issuance.
    Amendment Nos.: 339 (Unit No. 1) and 321 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18057B067; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. DPR-58 and DPR-74: 
Amendments revised the Renewed Facility Operating Licenses.
    Date of initial notice in Federal Register: July 5, 2017 (82 FR 
31098). The supplemental letter dated December 8, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated April 5, 2018.
    No significant hazards consideration comments received: No.

Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station, 
Unit 1 (FCS), Washington County, Nebraska

    Date of amendment request: June 16, 2017.
    Brief description of amendment: The amendment would remove the FCS 
Cyber Security Plan (CSP) from FCS License Condition 3.C.
    Date of issuance: March 28, 2018.
    Effective date: As of April 7, 2018, and shall be implemented by 
July 6, 2018.

[[Page 17866]]

    Amendment No.: 298. A publicly-available version is in ADAMS under 
Accession No. ML18047A661; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility License No. DPR-40: The amendment revised the 
Renewed Facility License.
    Date of initial notice in Federal Register: August 15, 2017 (82 FR 
38718).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 28, 2018.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant (VEGP), Unit Nos. 3 and 4, Burke 
County, Georgia

    Date of amendment request: September 29, 2017, and supplemented 
January 31, 2018.
    Description of amendment: The amendment authorizes changes to the 
VEGP Unit Nos. 3 and 4 Combined License page 7, and Updated Final 
Safety Analysis Report, including Tier 2* and associated Tier 2 to 
depart from certain information related to human engineering 
deficiencies contained in Westinghouse Electric Company's report APP-
OCS-GEH-320, titled, ``AP1000 Human Factors Engineering Integrated 
Systems Validation Plan.''
    Date of issuance: March 22, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 116 (Unit 3) and 115 (Unit 4). The publicly-
available versions are in an ADAMS package under Accession No. 
ML18044A071, which includes the Safety Evaluation that references 
documents related to this amendment.
    Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment 
revised the Facility Combined Licenses.
    Date of initial notice in Federal Register: November 21, 2017 (82 
FR 55413). The supplement dated January 31, 2018, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the NRC 
staff's original proposed no significant hazards consideration 
determination.
    The Commission's related evaluation of the amendment is contained 
in the Safety Evaluation dated March 22, 2018.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant (VEGP), Unit Nos. 3 and 4, Burke 
County, Georgia

    Date of amendment request: September 22, 2017.
    Description of amendment: The amendments consist of changes to 
Combined License Appendix A, Technical Specifications (TS). 
Specifically, the changes add new TS 3.1.10, Rod Withdrawal Test 
Exception--MODE 5, and modify TS Limiting Condition for Operation (LCO) 
3.0.7, to allow rod movement and rod drop time testing under cold 
conditions (MODE 5). Additionally, the LCO Applicability of TS 3.4.8, 
Minimum Reactor Coolant System Flow, is revised to reflect its safety 
analysis basis.
    Date of issuance: March 28, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 117 (Unit 3) and 116 (Unit 4). A publicly-available 
version is in ADAMS under Accession No. ML18060A411; documents related 
to this amendment are listed in the Safety Evaluation enclosed with the 
amendment.
    Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment 
revised the Facility Combined License.
    Date of initial notice in Federal Register: October 24, 2017 (82 FR 
49240).
    The Commission's related evaluation of the amendment is contained 
in the Safety Evaluation dated March 28, 2018.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant (VEGP), Unit Nos. 3 and 4, Burke 
County, Georgia

    Date of amendment request: July 28, 2017.
    Description of amendment: The amendment authorizes changes to the 
VEGP Units 3 and 4 Updated Final Safety Analysis Report to change 
Technical Specification (TS) Section 1.1, ``Definition of Actuation 
Logic Test,'' by adding a new TS Section 1.1, ``Definition of Actuation 
Logic Output Test (ALOT),'' revising existing Surveillance Requirements 
(SR) 3.3.15.1 and 3.3.16.1, and adding new SR 3.3.15.2 and SR 3.3.16.2 
to implement the new ALOT.
    Date of issuance: March 29, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 119 (Unit 3) and 118 (Unit 4). A publicly-available 
version is in ADAMS under Accession No. ML18064A340, which contains 
documents that are related to this amendment and are listed in the 
Safety Evaluation enclosed with this amendment.
    Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment 
revised the Facility Combined License.
    Date of initial notice in Federal Register: November 21, 2017 (82 
FR 55410).
    The Commission's related evaluation of the amendment is contained 
in the Safety Evaluation dated March 29, 2018.
    No significant hazards consideration comments received: No.

Tennessee Valley Authority, Docket No. 50-390, Watts Bar Nuclear Plant, 
Unit 1, Rhea County, Tennessee

    Date of amendment request: March 16, 2017, as supplemented by 
letter dated August 31, 2017.
    Brief description of amendment: The amendment revised Technical 
Specification Table 3.3.1-1, ``Reactor Trip System Instrumentation,'' 
to reflect plant modifications to the reactor protection system 
instrumentation associated with the turbine trip on low fluid oil 
pressure.
    Date of issuance: March 28, 2018.
    Effective date: As of the date of issuance and shall be implemented 
no later than startup from the Unit 1 refueling outage scheduled for 
fall 2018.
    Amendment No.: 119. A publicly-available version is in ADAMS under 
Accession No. ML18052B347; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. NPF-90: Amendment revised the 
Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: June 6, 2017 (82 FR 
26140). The supplemental letter dated August 31, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 28, 2018.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 12th day of April 2018.


[[Page 17867]]


    For the Nuclear Regulatory Commission.
Tara Inverso,
Acting Deputy Director, Division of Operating Reactor Licensing, Office 
of Nuclear Reactor Regulation.
[FR Doc. 2018-08070 Filed 4-23-18; 8:45 am]
BILLING CODE 7590-01-P