[Federal Register Volume 84, Number 78 (Tuesday, April 23, 2019)]
[Notices]
[Pages 16890-16897]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-07933]


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NUCLEAR REGULATORY COMMISSION

[NRC-2019-0099]


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 March 26, 2019 to April 8, 2019. The last 
biweekly notice was published on April 9, 2019.

DATES: Comments must be filed by May 23, 2019. A request for a hearing 
must be filed by June 24, 2019.

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-2019-0099. 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(s) listed in the FOR FURTHER 
INFORMATION CONTACT section of this document.
     Mail comments to: Office of Administration, Mail Stop: 
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Lynn Ronewicz, Office of Nuclear 
Reactor Regulations, 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-2019-0099, 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-2019-0099.
     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 ``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

[[Page 16891]]

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-2019-0099, 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. Background

    Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as 
amended (the Act), the 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 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 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

[[Page 16892]]

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 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,

[[Page 16893]]

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 
application(s), 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. 50-369 and 50-370, McGuire 
Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina

    Date of amendment request: February 5, 2019. A publicly-available 
version is in ADAMS under Accession No. ML19042A117.
    Description of amendment request: The amendments would modify 
Technical Specification (TS) 3.5.2, ECCS [Emergency Core Cooling 
System]--Operating''; TS 3.6.6, ``Containment Spray System''; TS 3.7.5, 
``Auxiliary Feedwater (AFW) System''; TS 3.7.6, ``Component Cooling 
Water (CCW) System''; TS 3.7.7, ``Nuclear Service Water System 
(NSWS)''; TS 3.7.9, ``Control Room Area Ventilation System (CRAVS)''; 
TS 3.7.11, ``Auxiliary Building Filtered Ventilation Exhaust System 
(ABFVES)''; TS 3.8.1, ``AC [Alternate Current] Sources--Operating''; 
and TS 3.8.4, ``DC [Direct Current] Sources--Operating,'' to remove 
expired TS footnotes. Additionally, the amendments would fix an 
editorial error in Section 3.0, ``SR [Surveillance Requirement] 
APPLICABILITY,'' specifically, SR 3.0.5.
    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.
    This LAR [license amendment request] proposes administrative 
non-technical changes only. These proposed changes do not adversely 
affect accident initiators or precursors nor alter the design 
assumptions, conditions, or configurations of the facility. The 
proposed changes do not alter or prevent the ability of structures, 
systems, and components (SSCs) to perform their intended function to 
mitigate the consequences of an initiating event within the assumed 
limits.
    Given the above discussion, it is concluded the proposed 
amendment does not significantly increase 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.
    This LAR proposes administrative non-technical changes only. The 
proposed changes will not alter the design requirements of any 
Structure, System or Component (SSC) or its function during accident 
conditions. No new or different accidents result from the proposed 
changes. The changes do not involve a physical alteration of the 
plant or any changes in methods governing normal plant operation. 
The changes do not alter assumptions made in the safety analysis.
    Given the above discussion, it is concluded the proposed 
amendment 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.
    This LAR proposes administrative non-technical changes only. The 
proposed changes do not alter the manner in which safety limits, 
limiting safety systems settings or limiting conditions for 
operation are determined. The safety analysis acceptance criteria 
are not affected by these changes. The proposed changes will not 
result in plant operation in a configuration outside the design 
basis. The proposed changes do not adversely affect systems that 
respond to safety shutdown the plant and to maintain the plant in a 
safe shutdown condition.
    Given the above discussion, it is concluded the proposed 
amendment does not involve a significant reduction in the safety 
margin.

    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.
    Exelon FitzPatrick, LLC and Exelon Generation Company, LLC, Docket 
No. 50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County, 
New York.
    Date of amendment request: March 7, 2019. A publicly-available 
version is in ADAMS under Accession No. ML19066A251.
    Description of amendment request: The amendment would revise the 
James A. FitzPatrick Nuclear Power Plant Technical Specification 
requirements regarding ventilation system testing in accordance with 
Technical Specifications Task Force (TSTF) Traveler, TSTF-522, Revision 
0, ``Revise Ventilation System Surveillance Requirements to Operate for 
10 Hours per Month'' (ADAMS Accession No. ML100890316). The NRC 
approved TSTF-522, Revision 0, as part of the consolidated line item 
improvement process on September 20, 2012 (77 FR 58421).
    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?

[[Page 16894]]

    Response: No.
    The proposed change replaces an existing Surveillance 
Requirement to operate the SGT [Standby Gas Treatment] System 
equipped with electric heaters for a continuous 10-hour period every 
31 days with a requirement to operate the systems for 15 continuous 
minutes with heaters operating.
    The system is not an accident initiator and therefore, these 
changes do not involve a significant increase in the probability of 
an accident. The proposed system and filter testing change is 
consistent with current regulatory guidance for the system and will 
continue to assure that the system performs the design function 
which may include mitigating accidents. Thus, the change does not 
involve a significant increase in the consequences of an accident.
    Therefore, it is concluded that this 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 replaces an existing Surveillance 
Requirement to operate the SGT System for a continuous 10-hour 
period every 31 days with a requirement to operate the system for 15 
continuous minutes with heaters operating.
    The change proposed for the ventilation system does not change 
any system operations or maintenance activities. Testing 
requirements will be revised and will continue to demonstrate that 
the Limiting Conditions for Operation are met, and the system 
components are capable of performing their intended safety 
functions. The change does not create new failure modes or 
mechanisms and no new accident precursors are generated.
    Therefore, it is concluded that this 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 proposed change replaces an existing Surveillance 
Requirement to operate the SGT System equipped with electric heaters 
for a continuous 10-hour period every 31 days with a requirement to 
operate the systems for 15 continuous minutes with heaters 
operating, if needed.
    The design basis for the ventilation systems' heaters is to heat 
the incoming air which reduces the relative humidity. The heater 
testing change proposed will continue to demonstrate that the 
heaters are capable of heating the air and will perform their design 
function. The proposed change is consistent with regulatory 
guidance.

    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: Donald P. Ferraro, Assistant General 
Counsel, Exelon Generation Company, LLC, 200 Exelon Way, Suite 305, 
Kennett Square, PA 19348.
    NRC Branch Chief: James G. Danna.
    Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna 
Nuclear Power Plant, Wayne County, New York
    Date of amendment request: January 15, 2019. A publicly-available 
version is in ADAMS under Accession No. ML19017A136.
    Description of amendment request: The amendment would revise the 
emergency response organization (ERO) positions identified in the 
Emergency Plan for the R. E. Ginna Nuclear Power Plant.
    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:
    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.

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes to the Ginna Emergency Plan do not increase 
the probability or consequences of an accident. The proposed changes 
do not impact the function of plant Structures, Systems, or 
Components (SSCs). The proposed changes do not affect accident 
initiators or accident precursors, nor do the changes alter design 
assumptions. The proposed changes do not alter or prevent the 
ability of the onsite ERO to perform their intended functions to 
mitigate the consequences of an accident or event. The proposed 
changes remove ERO positions no longer credited or considered 
necessary in support of Emergency Plan implementation.
    Therefore, the proposed changes to the Ginna Emergency Plan do 
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 changes have no impact on the design, function, or 
operation of any plant SSCs. The proposed changes do not affect 
plant equipment or accident analyses. The proposed changes do not 
involve a physical alteration of the plant (i.e., no new or 
different type of equipment will be installed), a change in the 
method of plant operation, or new operator actions. The proposed 
changes do not introduce failure modes that could result in a new 
accident, and the proposed changes do not alter assumptions made in 
the safety analysis. The proposed changes remove ERO positions no 
longer credited or considered necessary in support of Emergency Plan 
implementation.
    Therefore, the proposed changes to the Ginna Emergency Plan do 
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.
    Margin of safety is associated with confidence in the ability of 
the fission product barriers (i.e., fuel cladding, reactor coolant 
system pressure boundary, and containment structure) to limit the 
level of radiation dose to the public.
    The proposed changes do not adversely affect existing plant 
safety margins or the reliability of the equipment assumed to 
operate in the safety analyses. 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 changes. Margins of safety are unaffected by the 
proposed changes to the ERO staffing.
    The proposed changes are associated with the Ginna Emergency 
Plan staffing and do not impact operation of the plant or its 
response to transients or accidents. The proposed changes do not 
affect the Technical Specifications. The proposed changes do not 
involve a change in the method of plant operation, and no accident 
analyses will be affected by the proposed changes. Safety analysis 
acceptance criteria are not affected by these proposed changes. The 
proposed changes to the Emergency Plan will continue to provide the 
necessary onsite ERO response staff.
    Therefore, the proposed changes to the Ginna Emergency Plan do 
not involve a significant reduction in a margin of safety.

    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 Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 
60555.
    NRC Branch Chief: James G. Danna.

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

[[Page 16895]]

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.

Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Unit Nos. 
1, 2, and 3, Maricopa County, Arizona

    Date of application for amendments: May 25, 2018, as supplemented 
by letters dated October 12, 2018, and January 31, 2019.
    Brief description of amendments: The amendments documented approval 
of elimination of periodic response time testing for a specific 
pressure transmitter, consistent with the Palo Verde Nuclear Generating 
Station, Unit Nos. 1, 2, and 3, Technical Specifications.
    Date of issuance: April 3, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment Nos.: 208 (Unit 1), 208 (Unit 2), and 208 (Unit 3). A 
publicly-available version is in ADAMS under Accession No. ML19070A218. 
Documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. NPF-41, NPF-51, and NPF-74: 
The amendments approved allocated response time verification usage for 
a specific set of replacement components in lieu of directly measured 
response time testing.
    Date of initial notice in Federal Register: July 31, 2018 (83 FR 
36973). The supplemental letters dated October 12, 2018, and January 
31, 2019, 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 amendments is contained 
in a Safety Evaluation dated April 3, 2019.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: October 19, 2017, as supplemented by 
letters dated January 11, 2018, and September 19, 2018.
    Brief description of amendment: The amendment revised the Renewed 
Facility Operating License to authorize revision of the Shearon Harris 
Nuclear Power Plant Updated Final Safety Analysis Report to incorporate 
the process based on the Tornado Missile Risk Evaluator Methodology 
described in its application, as supplemented. This methodology will 
only be applied to discovered conditions where tornado missile 
protection is not currently provided and cannot be used to avoid 
providing tornado missile protection in the plant modification process.
    Date of issuance: March 29, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment No.: 169. A publicly-available version is in ADAMS under 
Accession No. ML18347A385; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-63: The amendment 
revised the Renewed Facility Operating License.
    Date of initial notice in Federal Register: February 13, 2018 (83 
FR 6221). The supplemental letter dated September 19, 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 29, 2019.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. STN50-455, Byron Station, 
Unit No. 2, Ogle County, Illinois

    Date of amendment request: March 8, 2018, as supplemented by 
letters dated July 2, 2018; December 18, 2018; and January 16, 2019.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 4.2.1 to authorize use of two lead test assemblies 
containing a limited number of accident tolerant fuel lead test rods 
during Byron Station, Unit No. 2, refueling cycles 22, 23, and 24. The 
lead test assemblies are non-limiting under steady state reactor 
conditions and will comply with fuel limits specified in the core 
operating limits report and TSs under all operational conditions.
    Date of issuance: April 3, 2019.
    Effective date: As of the date of issuance and shall be implemented 
prior to startup with the lead test assemblies.
    Amendment No: 207. A publicly-available version is in ADAMS under 
Accession No. ML19038A017; documents related to this amendment are 
listed in the related Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-66: The amendment 
revised the Renewed Facility Operating License and TSs.
    Date of initial notice in Federal Register: November 6, 2018 (83 FR 
55573). The supplements dated July 2, 2018, and December 18, 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 
supplement dated January 16, 2019, changed the scope of the application 
as originally noticed by eliminating the license condition and 
requesting a change to TS 4.2.1. The change in scope and the updated 
proposed significant hazards consideration was published in the Federal 
Register on February 1, 2019 (84 FR 1240).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated April 3, 2019.

[[Page 16896]]

    No significant hazards consideration comments received: No.

Florida Power & Light Company, Docket Nos. 50-250 and 50-251, Turkey 
Point Nuclear Generating Unit Nos. 3 and 4, Miami-Dade County, Florida

    Date of amendment request: October 17, 2018; as supplemented by 
letters dated October 24, 2018; December 3, 2018; and January 31, 2019.
    Brief description of amendments: The amendments modified the 
Renewed Facility Operating Licenses by revising paragraph 3.D, 
``Transition License Conditions,'' to eliminate reliance on NRC 
approval of the Flowserve Reactor Coolant Pump (RCP) Seal Topical 
Report as a condition of Turkey Point Nuclear Generating's transition 
to National Fire Protection Association Standard 805, and instead 
documented the guidance outlined in NRC-approved Topical Report WCAP-
16175-P-A, Revision 0, ``Model for Failure of RCP Seals Given Loss of 
Seal Cooling in CE [Combustion Engineering] NSSS [Nuclear Steam Supply 
System] Plants.'' A non-proprietary version of WCAP-16175-P-A, Revision 
0, can be found in ADAMS under Accession No. ML071130383.
    Date of issuance: March 27, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 286 (Unit No. 3) and 280 (Unit No. 4). A publicly-
available version is in ADAMS under Accession No. ML19064A903; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. DPR-31 and DPR-41: The 
amendments revised the Renewed Facility Operating Licenses.
    Date of initial notice in Federal Register: December 26, 2018 (83 
FR 66318). The supplemental letters dated December 3, 2018, and January 
31, 2019, 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 amendments is contained 
in a Safety Evaluation dated March 27, 2019.
    No significant hazards consideration comments received: No.

NextEra Energy Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point 
Beach Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowoc 
County, Wisconsin

    Date of amendment request: March 31, 2017, as supplemented by 
letters dated April 12, 2018 (two); May 29, 2018; August 30, 2018; and 
March 13, 2019.
    Brief description of amendments: The amendments revised the Point 
Beach Nuclear Plant, Units 1 and 2, operating licenses by adding a 
license condition to resolve construction truss design code 
nonconformances. The amendments approved a risk-informed approach to 
resolve legacy design code nonconformances associated with construction 
trusses in the containment buildings of Point Beach Nuclear Plant, 
Units 1 and 2, following the guidance in Regulatory Guide 1.174, 
Revision 2, ``An Approach for Using Probabilistic Risk Assessment in 
Risk-Informed Decisions on Plant-Specific Changes to the Licensing 
Basis,'' issued May 2011.
    Date of issuance: March 26, 2019.
    Effective date: As of the date of issuance and shall be implemented 
in accordance with the requirements specified in paragraphs 4.I and 4.H 
of Renewed Facility Operating License Nos. DPR-24 and DPR-27, 
respectively.
    Amendment Nos.: 263 (Unit 1) and 266 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18345A110; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-24 and DPR-27: The 
amendments revised the Renewed Facility Operating Licenses.
    Date of initial notice in Federal Register: June 19, 2017 (82 FR 
27890). The supplemental letters dated April 12, 2018 (two); May 29, 
2018; August 30, 2018; and March 13, 2019, 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 amendments is contained 
in a Safety Evaluation dated March 26, 2019.
    No significant hazards consideration comments received: No.

NextEra Energy, Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point 
Beach Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowoc 
County, Wisconsin

    Date of amendment request: July 30, 2018.
    Brief description of amendments: The amendments revised the Point 
Beach Nuclear Plant, Units 1 and 2, Technical Specifications (TSs), 
consistent with NRC-approved Technical Specifications Task Force (TSTF) 
Traveler TSTF-547, Revision 1, ``Clarification of Rod Position 
Requirements.'' The amendments provide time to repair rod movement 
failures that do not affect rod operability, correct conflicts between 
the TSs, increase consistency between the subject TSs, and improve the 
format and presentation.
    Date of issuance: March 27, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment Nos.: 264 (Unit 1) and 267 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML19052A544; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-24 and DPR-27: The 
amendments revised the Renewed Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: November 6, 2018 (83 FR 
55575).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 27, 2019.
    No significant hazards consideration comments received: No.

NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit 
No. 1, Rockingham County, New Hampshire

    Date of amendment request: March 16, 2018.
    Description of amendment request: The amendment revised the 
frequencies for performing the relative pressure measurement and the 
assessment of the control room envelope boundary required by Technical 
Specification 6.7.6.l, ``Control Room Envelope Habitability Program.''
    Date of issuance: March 29, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment No.: 160. A publicly-available version is in ADAMS under 
Accession No. ML19065A215; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.

[[Page 16897]]

    Renewed Facility Operating License No. NPF-86: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: July 3, 2018 (83 FR 
31186).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 29, 2019.
    No significant hazards consideration comments received: No.
    PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station, 
Salem County, New Jersey
    Date of amendment request: April 13, 2018, as supplemented by two 
letters dated October 17, 2018.
    Brief description of amendment: The amendment revised Hope Creek 
Generating Station Technical Specification 3.8.3.1, ``Distribution--
Operating,'' to increase the alternating current inverters allowed 
outage time from 24 hours to 7 days. The change was based on 
application of the Hope Creek Generating Station probabilistic risk 
assessment in support of a risk-informed extension and on additional 
considerations and compensatory actions.
    Date of issuance: March 27, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of the date of issuance.
    Amendment No.: 215. A publicly-available version is in ADAMS under 
Accession No. ML19065A156; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-57: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: June 19, 2018 (83 FR 
28462). Two supplemental letters dated October 17, 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 27, 2019.
    No significant hazards consideration comments received: No.

Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296, 
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Limestone County, 
Alabama

    Date of amendment request: October 18, 2018, as supplemented by 
letters dated February 13, 2019, and March 8, 2019.
    Brief description of amendments: The amendments revised the Renewed 
Facility Operating Licenses by changing license conditions associated 
with the fire protection program controlled by 10 CFR 50.48(c), 
``National Fire Protection Association Standard NFPA 805.'' The amended 
license conditions incorporate changes made to Table S-2, ``Plant 
Modifications Committed,'' in Tennessee Valley Authority letter dated 
October 18, 2018, as supplemented by letters dated February 13, 2019, 
and March 8, 2019, which describes modifications necessary to 
transition into full compliance with 10 CFR 50.48(c).
    Date of issuance: April 2, 2019.
    Effective date: As of the date of issuance and shall be implemented 
immediately.
    Amendment Nos.: 307 (Unit 1), 330, (Unit 2), and 290 (Unit 3). A 
publicly-available version is in ADAMS under Accession No. ML19037A137; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68: 
The amendments revised the Renewed Facility Operating Licenses.
    Date of initial notice in Federal Register: December 18, 2018 (83 
FR 64897). The supplemental letters dated February 13, 2019, and March 
8, 2019, 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 amendments is contained 
in a Safety Evaluation dated April 2, 2019.
    No significant hazards consideration comments received: No.

Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek 
Generating Station, Unit 1, Coffey County, Kansas

    Date of amendment request: May 9, 2018, as supplemented by letter 
dated November 19, 2018.
    Brief description of amendment: The amendment revised the Wolf 
Creek Generating Station Radiological Emergency Response Plan to (1) 
reduce the number of required emergency response organization 
positions, (2) standardize activation times for the technical support 
center to 75 minutes, (3) replace the current full-time normal work 
hours licensed medical practitioner position with on-shift first aid 
responders, and (4) remove reference to performing dose assessment 
using containment pressure indication.
    Date of issuance: April 1, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days from the date of issuance.
    Amendment No.: 220. A publicly-available version is in ADAMS under 
Accession No. ML19052A546; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-42. The amendment 
revised the Wolf Creek Generating Station Radiological Emergency 
Response Plan.
    Date of initial notice in Federal Register: July 3, 2018 (83 FR 
31187). The supplemental letter dated November 19, 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 April 1, 2019.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 16th day of April, 2019
    For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2019-07933 Filed 4-22-19; 8:45 am]
 BILLING CODE 7590-01-P