[Federal Register Volume 83, Number 137 (Tuesday, July 17, 2018)]
[Notices]
[Pages 33263-33276]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-14779]


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NUCLEAR REGULATORY COMMISSION

[NRC-2018-0140]


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 June 18, 2018, to June 29, 2018. The last 
biweekly notice was published on July 3, 2018.

DATES: Comments must be filed by August 16, 2018. A request for a 
hearing must be filed by September 17, 2018.

ADDRESSES: You may submit comments by any of the following methods:
    <bullet> Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0140. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: <a href="/cdn-cgi/l/email-protection#f1bb949f9f98979483dfb39e83969482b19f8392df969e87"><span class="__cf_email__" data-cfemail="9fd5faf1f1f6f9faedb1ddf0edf8faecdff1edfcb1f8f0e9">[email protected]</span></a>. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
    <bullet> 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: Janet C. Burkhardt, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-1384, email: <a href="/cdn-cgi/l/email-protection#4e042f202b3a600c3b3c25262f3c2a3a0e203c2d60292138"><span class="__cf_email__" data-cfemail="da90bbb4bfaef498afa8b1b2bba8beae9ab4a8b9f4bdb5ac">[email protected]</span></a>.

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2018-0140, 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:
    <bullet> Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0140.
    <bullet> 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 <a href="/cdn-cgi/l/email-protection#5d2d392f732f382e32282f3e381d332f3e733a322b"><span class="__cf_email__" data-cfemail="d8a8bcaaf6aabdabb7adaabbbd98b6aabbf6bfb7ae">[email protected]</span></a>. 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.
    <bullet> 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.

[[Page 33264]]

B. Submitting Comments

    Please include Docket ID NRC-2018-0140, 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 section 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 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

[[Page 33265]]

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 <a href="/cdn-cgi/l/email-protection#6008050112090e074e040f030b0514200e12034e070f16"><span class="__cf_email__" data-cfemail="dcb4b9bdaeb5b2bbf2b8b3bfb7b9a89cb2aebff2bbb3aa">[email protected]</span></a>, 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 <a href="/cdn-cgi/l/email-protection#327f617a761c6057415d47405157725c40511c555d44"><span class="__cf_email__" data-cfemail="2c617f6468027e495f43595e4f496c425e4f024b435a">[email protected]</span></a>, 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

[[Page 33266]]

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.

Dominion Energy Nuclear Connecticut, Inc. (DENC), Docket No. 50-423, 
Millstone Power Station, Unit No. 3 (MPS3), New London County, 
Connecticut

    Date of amendment request: April 4, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18100A055.
    Description of amendment request: The amendment would revise the 
MPS3 Technical Specifications (TSs). Specifically, with one Control 
Building Inlet Ventilation Radiation monitor channel inoperable for 
greater than 7 days, or if both radiation monitor channels are 
inoperable, DENC proposes to revise and reformat Action 18 in TS Table 
3.3-3, Functional Unit 7.e, ``Control Building Inlet Ventilation 
Radiation,'' to allow control room operators to manually place one 
train of the Control Room Emergency Ventilation System (CREVS) in the 
emergency mode of operation to provide additional time to restore one 
channel of Control Building Inlet Ventilation Radiation monitoring to 
OPERABLE status.
    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 change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    Operation of MPS3 in accordance with the proposed change does 
not involve a significant increase in the probability or 
consequences of an accident previously evaluated. The proposed 
change removes an overly restrictive requirement and adds a 
conservative requirement for actions to be taken when there is a 
loss of operability of the CREVS actuation instrumentation. This 
does not increase the probability of an accident previously 
evaluated since the CREVS actuation itself is not an accident 
initiator. The proposed change is consistent with standard TSs for 
Westinghouse plants (NUREG-1431) and provides assurance that the 
CREVS is in the conservative mode of operation for a response to an 
accident. Analysis demonstrates that with one train of the CREVS in 
the emergency mode of operation, control room operators are 
adequately protected from the radiological consequences of design 
basis accident events. Therefore, the probability or consequences of 
an accident previously evaluated is not significantly increased.
    Based on the above, the proposed change does not involve a 
significant increase in the probability or consequences of an 
accident previously evaluated.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    Operation of MPS3 in accordance with the proposed change does 
not create the possibility of a new or different kind of accident 
from any accident previously evaluated. The proposed change does not 
involve a physical alteration of the plant or change in the methods 
governing normal plant operation. The proposed change replaces the 
overly restrictive shutdown requirement with a conservative action 
to be taken upon loss of CREVS actuation instrumentation 
operability, thereby avoiding the risk associated with an immediate 
controlled shutdown. Therefore, the possibility of a new or 
different kind of accident from any accident previously evaluated is 
not created.
    With one train of CREVS in the emergency mode of operation, DENC 
has confirmed that MPS3 is in compliance with the current 
radiological analyses of record for design basis accidents with dose 
consequences to the control room. Therefore, the proposed change 
does not affect the design basis analyses and does not alter the 
assumptions made in the MPS3 accident analysis.
    Based on the above, the proposed amendment does not create the 
possibility of a new or different kind of accident previously 
evaluated.
    3. Does the proposed change involve a significant reduction in 
the margin of safety?
    Response: No.
    Operation of MPS3 in accordance with the proposed change does 
not involve a significant reduction in the margin of safety. The 
proposed change revises and reformats the Control Building lnlet 
Ventilation Radiation TS to place the CREVS in the conservative mode 
of operation for a response to an accident. The proposed change 
provides additional time to restore an inoperable radiation monitor 
channel instead of requiring an immediate controlled plant shutdown 
and suspension of movement of recently irradiated fuel assemblies, 
if applicable. A plant shutdown is a transient that may be avoided 
by providing a limited time to make repairs. In addition, the 
control room operators are adequately protected from the 
radiological consequences of design basis accident events with one 
train of the CREVS in the emergency mode of operation. The potential 
to avoid a plant transient in conjunction with protecting control 
room operators offsets any risk associated with the proposed change.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.
    Based on the above, the proposed amendment does not involve a 
significant reduction in the 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: Lillian M. Cuoco, Senior Counsel, Dominion 
Energy, Inc., 120 Tredegar Street, RS-2, Richmond, VA 23219.
    NRC Branch Chief: James G. Danna.

Duke Energy Progress, LLC, Docket Nos. 50-325 and 50-324, Brunswick 
Steam Electric Plant, Units 1 and 2 (Brunswick or BSEP), Brunswick 
County, North Carolina

    Date of amendment request: April 4, 2018, as supplemented by letter 
dated May 29, 2018. Publicly-available versions are in ADAMS under 
Accession Nos. ML18094B058 and ML18149A487, respectively.
    Description of amendment request: The amendments would modify the 
BSEP Technical Specifications (TSs) to relocate the pressure-
temperature limit curves to a licensee-controlled Pressure and 
Temperature Limits Report (PTLR). The amendment request was submitted 
in accordance with guidance provided in NRC Generic Letter 96-03, 
``Relocation of the Pressure Temperature Limit Curves and Low 
Temperature Overpressure Protections System Limits,'' dated January 31, 
1996.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the

[[Page 33267]]

licensee has provided its analysis of the issue of no significant 
hazards consideration, which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed license amendment adopts the NRC approved 
methodology described in Boiling Water Reactor Owner's Group (BWROG) 
Licensing Topical Report (LTR) (BWROG-TP-11-022-A, SIR-05-044, 
Revision 1-A), ``Pressure Temperature Limits Report Methodology for 
Boiling Water Reactors.'' The BSEP PTLR was developed based on the 
methodology and template provided in the BWROG LTR.
    10 CFR 50, Appendix G, establishes requirements to protect the 
integrity of the reactor coolant pressure boundary (RCPB) in nuclear 
power plants.
    Implementing this NRC approved methodology does not reduce the 
ability to protect the reactor coolant pressure boundary as 
specified in Appendix G, nor will this change increase the 
probability of malfunction of plant equipment, or the failure of 
plant structures, systems, or components. Incorporation of the new 
methodology for calculating pressure and temperature limit curves, 
and the relocation of the pressure and temperature limit curves from 
the TS to the PTLR provides an equivalent level of assurance that 
the reactor coolant pressure boundary is capable of performing its 
intended safety functions.
    The proposed changes do not adversely affect accident initiators 
or precursors, and do not alter the design assumptions, conditions, 
or configuration of the plant or the manner in which the plant is 
operated and maintained. The ability of structures, systems, and 
components to perform their intended safety functions is not altered 
or prevented by the proposed changes, and the assumptions used in 
determining the radiological consequences of previously evaluated 
accidents are not affected.
    Therefore, the proposed amendment does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    Creation of the possibility of a new or different kind of 
accident requires creating one or more new accident precursors. New 
accident precursors may be created by modifications of plant 
configuration, including changes in allowable modes of operation.
    The change in methodology for calculating pressure and 
temperature limits and the relocation of those limits to the PTLR do 
not alter or involve any design basis accident initiators. Reactor 
coolant pressure boundary integrity will continue to be maintained 
in accordance with 10 CFR part 50, Appendix G, and the assumed 
accident performance of plant structures, systems and components 
will not be affected. The proposed changes do not involve a physical 
alteration of the plant (i.e., no new or different type of equipment 
will be installed), and the installed equipment is not being 
operated in a new or different manner.
    Therefore, 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 change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed changes do not affect the function of the reactor 
coolant pressure boundary or its response during plant transients. 
Calculating the Brunswick pressure temperature limits using the NRC 
approved structural integrity methodology ensures adequate margins 
of safety relating to reactor coolant pressure boundary integrity 
are maintained. The proposed changes do not alter the manner in 
which the Limiting Conditions for Operation pressure and temperature 
limits for the reactor coolant pressure boundary are determined. 
There are no changes to the setpoints at which protective actions 
are initiated, and the operability requirements for equipment 
assumed to operate for accident mitigation are not affected.
    Therefore, the proposed amendment does not result in a 
significant reduction in the 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: Kathryn B. Nolan, Deputy General Counsel, 
550 South Tryon Street, M/C DEC45A, Charlotte, NC 28202.
    NRC Acting Branch Chief: Booma Venkataraman.

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

    Date of amendment request: January 31, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18037A782.
    Description of amendment request: The amendment would revise 
FitzPatrick's emergency plan by changing the emergency action level 
(EAL) schemes. The proposed changes are based on the Nuclear Energy 
Institute's (NEI's) guidance in NEI 99-01, Revision 6, ``Development of 
Emergency Action Levels for Non-Passive Reactors,'' which was endorsed 
by the NRC in a letter dated March 28, 2013 (ADAMS Accession No. 
ML12346A463).
    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 changes to FitzPatrick's EAL schemes to adopt the 
NRC-endorsed guidance in NEI 99-01, Revision 6 do not reduce the 
capability to meet the emergency planning requirements established 
in 10 CFR 50.47 and 10 CFR part 50, Appendix E. The proposed changes 
do not reduce the functionality, performance, or capability of 
FitzPatrick's ERO [emergency response organization] to respond in 
mitigating the consequences of any design basis accident.
    The probability of a reactor accident requiring implementation 
of Emergency Plan EALs has no relevance in determining whether the 
proposed changes to the EALs reduce the effectiveness of the 
Emergency Plans. As discussed in Section D, ``Planning Basis,'' of 
NUREG-0654, Revision 1, ``Criteria for Preparation and Evaluation of 
Radiological Emergency Response Plants and Preparedness in Support 
of Nuclear Power Plants:''
    ``. . . The overall objective of emergency response plans is to 
provide dose savings (and in some cases immediate life saving) for a 
spectrum of accidents that could produce offsite doses in excess of 
Protective Action Guides (PAGs). No single specific accident 
sequence should be isolated as the one for which to plan because 
each accident could have different consequences, both in nature and 
degree. Further, the range of possible selection for a planning 
basis is very large, starting with a zero point of requiring no 
planning at all because significant offsite radiological accident 
consequences are unlikely to occur, to planning for the worst 
possible accident, regardless of its extremely low likelihood. . . 
.''
    Therefore, Exelon did not consider the risk insights regarding 
any specific accident initiation or progression in evaluating the 
proposed changes.
    The proposed changes do not involve any physical changes to 
plant equipment or systems, nor do they alter the assumptions of any 
accident analyses. The proposed changes do not adversely affect 
accident initiators or precursors nor do they alter the design 
assumptions, conditions, and configuration or the manner in which 
the plants are operated and maintained. The proposed changes do not 
adversely affect the ability of Structures, Systems, or Components 
(SSCs) to perform their intended safety functions in mitigating the 
consequences of an initiating event within the assumed acceptance 
limits.
    Therefore, the proposed changes 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

[[Page 33268]]

accident from any accident previously evaluated?
    Response: No.
    The proposed changes to FitzPatrick's EAL schemes to adopt the 
NRC-endorsed guidance in NEI 99-01, Revision 6 do not involve any 
physical changes to plant systems or equipment. The proposed changes 
do not involve the addition of any new plant equipment. The proposed 
changes will not alter the design configuration, or method of 
operation of plant equipment beyond its normal functional 
capabilities. All FitzPatrick ERO functions will continue to be 
performed as required. The proposed changes do not create any new 
credible failure mechanisms, malfunctions, or accident initiators.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from those that have been 
previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed changes to FitzPatrick's EAL schemes to adopt the 
NRC-endorsed guidance in NEI 99-01, Revision 6 do not alter or 
exceed a design basis or safety limit. There is no change 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. There are no changes to setpoints or 
environmental conditions of any SSC or the manner in which any SSC 
is operated. Margins of safety are unaffected by the proposed 
changes to adopt the NEI 99-01, Revision 6 EAL scheme guidance. The 
applicable requirements of 10 CFR 50.47 and 10 CFR part 50, Appendix 
E will continue to be met.
    Therefore, the proposed changes do not involve any 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: 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. 50-289 and 50-320, Three 
Mile Island Nuclear Station (TMI), Unit Nos. 1 and 2, Dauphin County, 
Pennsylvania

    Date of amendment request: March 19, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18078A578.
    Description of amendment request: The amendment would revise the 
TMI Site Emergency Plan (SEP) on-shift and emergency response 
organization (ERO) staffing to support the planned permanent cessation 
of operations and permanent defueling of TMI, Unit 1. Specifically, the 
proposed changes would eliminate the on-shift positions not needed for 
the safe storage of spent fuel in the spent fuel pool during the 
initial decommissioning period and eliminate the ERO positions not 
necessary to effectively respond to credible accidents for a 
permanently shutdown and defueled power reactor facility. The proposed 
changes will also relocate full augmentation position requirements from 
the SEP to the Emergency Preparedness Implementing Procedures.
    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 changes to the TMI Emergency Plan do not impact the 
function of plant Structures, Systems, or Components (SSCs). The 
proposed changes do not involve the modification of any plant 
equipment or affect plant operation. The proposed changes do not 
affect accident initiators or precursors, nor do the proposed 
changes alter design assumptions. The proposed changes do not 
prevent the ability of the on-shift staff and ERO to perform their 
intended functions to mitigate the consequences of any accident or 
event that will be credible in the permanently defueled condition. 
The proposed changes only remove positions that will no longer be 
needed or credited in the Emergency Plan in the permanently defueled 
condition.
    Therefore, the proposed changes 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 reduce the number of on-shift and ERO 
positions commensurate with the hazards associated with a 
permanently shutdown and defueled facility. The proposed changes do 
not involve installation of new equipment or modification of 
existing equipment, so that no new equipment failure modes are 
introduced. Also, the proposed changes do not result in a change to 
the way that the equipment or facility is operated so that no new 
accident initiators are created.
    Therefore, the proposed changes do 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.
    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. The proposed changes are 
associated with the Emergency Plan and 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 the 
proposed changes and margins of safety are maintained. The revised 
Emergency Plan will continue to provide the necessary response staff 
with the proposed changes.
    Therefore, 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 
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.

Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick 
Generating Station, Unit Nos. 1 and 2, Montgomery County, Pennsylvania

Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
171, 50-277, and 50-278, Peach Bottom Atomic Power Station, Unit Nos. 
1, 2, and 3, York and Lancaster Counties, Pennsylvania

    Date of amendment request: May 10, 2018. Publicly-available version 
is in ADAMS under Package Accession No. ML18149A290.
    Description of amendment request: The amendments would revise the 
emergency response organization (ERO) positions identified in the 
emergency plan for each site.
    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

[[Page 33269]]

consideration for each site, 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 changes to the [site] 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 [site] 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 [site] 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 [site] 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 [site] Emergency Plan do 
not involve a significant reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis for each site 
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.

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 4, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18129A219.
    Description of amendment request: The proposed change would modify 
technical specification (TS) requirements regarding Limiting Condition 
for Operation (LCO) and Surveillance Requirement (SR) usage, in 
accordance with NRC-approved Technical Specifications Task Force (TSTF) 
Traveler TSTF-529, Revision 4, ``Clarify Use and Application Rules.''
    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 changes to Section 1.3 and LCO 3.0.4 have no effect 
on the requirement for systems to be Operable and have no effect on 
the application of TS actions. The proposed change to SR 3.0.3 
states that the allowance may only be used when there is a 
reasonable expectation the surveillance will be met when performed. 
Since the proposed change does not significantly affect system 
Operability, the proposed change will have no effect on the 
initiating events for accidents previously evaluated and will have 
no significant effect on the ability of the systems to mitigate 
accidents previously evaluated.
    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 change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed change to the TS usage rules does not affect the 
design or function of any plant systems. The proposed change does 
not change the Operability requirements for plant systems or the 
actions taken when plant systems are not operable.
    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 change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed change clarifies the application of Section 1.3 and 
LCO 3.0.4 and does not result in changes in plant operation. SR 
3.0.3 is revised to allow application of SR 3.0.3 when an SR has not 
been previously performed if there is reasonable expectation that 
the SR will be met when performed. This expands the use of SR 3.0.3 
while ensuring the affected system is capable of performing its 
safety function. As a result, plant safety is either improved or 
unaffected.
    Therefore, it is concluded that this 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: Robert B. Haemer, Senior Nuclear Counsel, 
One Cook Place, Bridgman, MI 49106.
    NRC Branch Chief: David J. Wrona.

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

    Date of amendment request: May 18, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18138A396.
    Description of amendment request: The amendment request proposes to 
change Technical Specifications Limiting Condition for Operation 3.3.8, 
Engineered Safety Feature Actuation System (ESFAS) Instrumentation, 
related to Safeguard Actuation Functions. Various ESFAS Functions 
require applicability and corresponding actions changes to more 
accurately reflect their operation and related safety analysis 
assumptions. This submittal requests approval of the license amendment 
necessary to implement these changes.

[[Page 33270]]

    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 changes do not involve changes to current plant 
design or safety analysis assumptions. These changes provide 
Technical Specifications consistency with the approved plant design 
and safety analysis assumptions. The changes do not affect the 
operation of any systems or equipment that initiate an analyzed 
accident or alter any structures, systems, and components (SSCs) 
accident initiator or initiating sequence of events. The proposed 
changes do not result in any increase in the probability of an 
analyzed accident occurring. Therefore, the requested amendment 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 changes do not involve changes to current plant 
design or safety analysis assumptions. These changes provide 
Technical Specifications consistency with the approved plant design 
and safety analysis assumptions. The proposed changes do not affect 
plant protection instrumentation systems, and do not affect the 
design function, support, design, or operation of mechanical and 
fluid systems. The proposed changes do not result in a new failure 
mechanism or introduce any new accident precursors. No design 
function described in the Updated Final Safety Analysis Report 
(UFSAR) is affected by the proposed changes. Therefore, the 
requested amendment does not create the possibility of a new or 
different kind accident from any accident previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed changes do not involve changes to current plant 
design or safety analysis assumptions. These changes provide 
Technical Specifications consistency with the approved plant design 
and safety analysis assumptions. No safety analysis or design basis 
acceptance limit/criterion is involved. 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.

Tennessee Valley Authority (TVA), Docket Nos. 50-259, 50-260, and 50-
296, Browns Ferry Nuclear Plant (BFN), Unit Nos. 1, 2, and 3, Limestone 
County, Alabama

    Date of amendment request: May 3, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18124A053.
    Description of amendment request: The amendments would revise the 
BFN Units 1, 2, and 3 renewed facility operating licenses (RFOLs) to 
provide a correction to previously submitted information in relation to 
their approved fire protection program under 10 CFR 50.48(c), 
``National Fire Protection Association Standard NFPA 805.'' 
Specifically, TVA requested to modify the BFN licenses to reflect 
changes to Item 3.3.4 in Table B-1, ``Transition of Fundamental Fire 
Protection Program & Design Elements,'' of Attachment A in its NFPA 805 
license amendment request dated March 27, 2013 (ADAMS Accession No. 
ML13092A393).
    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 amendment adds the reference to this letter to the 
BFN RFOL License Condition paragraphs 2.C.(13), 2.C.(14), and 
2.C.(7) for BFN Units 1, 2, and 3, respectively. The change 
encompassed by the proposed amendment is to correct the entry in 
Attachment A Table B-1 of the BFN Transition Report.
    The proposed change does not adversely affect accident 
initiators or precursors nor alter the design assumptions, 
conditions, and configuration of the facility or the manner in which 
the plant is operated and maintained. The proposed change does not 
affect the ability of structures, systems and components (SSCs) to 
perform their intended safety function to mitigate the consequences 
of an initiating event within the assumed acceptance limits.
    Therefore, these proposed changes do not involve a significant 
increase in the probability of consequences of an accident 
previously identified.
    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 amendment adds the reference to this letter to the 
BFN RFOL License Condition paragraphs 2.C.(13), 2.C.(14), and 
2.C.(7) for BFN Units 1, 2, and 3, respectively. The change 
encompassed by the proposed amendment is to correct the entry in 
Attachment A Table B-1 of the BFN Transition Report.
    There is no risk impact to Core Damage Frequency (CDF) or Large 
Early Release Frequency (LERF) because this is an administrative 
change. Plant secondary combustibles, including insulating 
materials, are considered in the fire modeling input to the Fire PRA 
[Probabilistic Risk Assessment].
    The proposed change does not result in any new or different 
kinds of accident from that previously evaluated because it does not 
change any precursors or equipment that is previously credited for 
accident mitigation.
    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 proposed amendment adds the reference to this letter to the 
BFN RFOL License Condition paragraphs 2.C.(13), 2.C.(14), and 
2.C.(7) for BFN Units 1, 2, and 3, respectively. The change 
encompassed by the proposed amendment are to correct the entry in 
Attachment A Table B-1 of the BFN Transition Report.
    This proposed change corrects erroneous information to 
previously approved information in the BFN Transition Report. This 
proposed change will have an insignificant impact on the accident 
analysis as it is a clarifying or administrative change. Plant 
secondary combustibles, including insulating materials, are 
considered in the fire modeling input to the Fire PRA.
    The proposed change will not result in any new or different 
kinds of accident from that previously evaluated because it does not 
change any precursors or equipment that is previously credited for 
accident mitigation.
    Therefore, based on the above discussion, these proposed changes 
do not involve a reduction in the 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: General Counsel, Tennessee Valley Authority, 
400 West Summit Hill Drive, 6A West Tower, Knoxville, TN 37902.
    NRC Acting Branch Chief: Booma Venkataraman.

[[Page 33271]]

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 No. 1, Wake and Chatham Counties, North Carolina

    Date of amendment request: June 5, 2017, as supplemented by letters 
dated October 30, 2017, November 27, 2017, and January 28, 2018.
    Brief description of amendment: The amendment revised the Technical 
Specifications (TSs) to restrict the steady-state voltage and frequency 
limits for emergency diesel generator (EDG) operation to ensure that 
accident mitigation equipment can perform as designed. In addition, the 
amendment revised a TS to increase the voltage limit for the EDG full 
load rejection test to provide additional operating margin to test 
acceptance criteria.
    Date of issuance: June 20, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 165. A publicly-available version is in ADAMS under 
Accession No. ML18130A270; 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 and TSs.
    Date of initial notice in Federal Register: September 26, 2017 (82 
FR 44851). The supplemental letters dated October 30, 2017, November 
27, 2017, and January 28, 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 June 20, 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: July 13, 2017.
    Brief description of amendment: The amendment approved the removal 
of the existing cyber security license condition from the facility 
operating license.
    Date of issuance: June 27, 2018.
    Effective date: 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 independent spent fuel storage installation, and shall be 
implemented within 60 days of the effective date.
    Amendment No.: 268. A publicly-available version is in ADAMS under 
Accession No. ML18145A208; documents related to this amendment are 
referenced in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-28: This amendment 
revised the License.
    Date of initial notice in Federal Register: September 26, 2017 (82 
FR 44852).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated June 27, 2018.
    No significant hazards consideration comments received: No.

Entergy Operations, Inc., Docket No. 50-313, Arkansas Nuclear One, Unit 
1 (ANO-1), Pope County, Arkansas

    Date of amendment request: July 17, 2017.
    Brief description of amendment: The amendment revised the Technical 
Specifications (TSs) for ANO-1 and established a new Completion Time in 
ANO-1 TS 3.7.5, ``Emergency Feedwater (EFW) System,'' where one steam 
supply to the turbine-driven EFW pump is inoperable concurrent with an 
inoperable motor-driven EFW train. The amendment is consistent with 
NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-
412, Revision 3, ``Provide Actions for One Steam Supply to Turbine 
Driven AFW [Auxiliary Feedwater]/EFW Pump Inoperable,'' with certain 
plant-specific deviations.
    Date of issuance: June 19, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 260. A publicly-available version is in ADAMS under 
Accession No. ML18115A282; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-51: Amendment revised 
the Renewed Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: October 10, 2017 (82 FR 
47036).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated June 19, 2018.
    No significant hazards consideration comments received: No.

Entergy Operations, Inc., Docket No. 50-368, Arkansas Nuclear One, Unit 
No. 2 (ANO-2), Pope County, Arkansas

    Date of amendment request: July 17, 2017.
    Brief description of amendment: The amendment revised the Technical 
Specifications (TSs) for ANO-2 and established Actions and Allowable 
Outage Times in ANO-2 TS 3.7.1.2, ``Emergency Feedwater System,'' for 
several combinations of inoperable Emergency Feedwater (EFW) trains 
consistent with NUREG-1432, ``Standard Technical Specifications--
Combustion Engineering Plants,'' Revision 4. The amendment includes

[[Page 33272]]

changes incorporated by Technical Specifications Task Force (TSTF)-340, 
``Allow 7 Day Completion Time for a Turbine-Driven AFW [Auxiliary 
Feedwater] Pump Inoperable,'' Revision 3 and TSTF-412, ``Provide 
Actions for One Steam Supply to Turbine Driven AFW/EFW Pump 
Inoperable,'' Revision 3.
    Date of issuance: June 19, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 310. A publicly-available version is in ADAMS under 
Accession No. ML18134A253; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-6: Amendment revised the 
Renewed Facility Operating License and TSs.
    Date of initial notice in Federal Register: October 10, 2017 (82 FR 
47036).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated June 19, 2018.
    No significant hazards consideration comments received: No.

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 Nos. 50-220 and 50-
410, Nine Mile, Point, Nuclear Station, Unit Nos. 1 and 2, Oswego 
County, New York, Exelon Generation Company, LLC, Docket No. 50-244, 
R.E. Ginna Nuclear Power Plant, Wayne County, New York

    Date of amendment request: May 31, 2017.
    Brief description of amendments: The amendments revised the 
emergency plans for each facility by changing the emergency action 
level schemes. The changes are based on the Nuclear Energy Institute's 
(NEI's) guidance in NEI 99-01, Revision 6, ``Development of Emergency 
Action Levels for Non-Passive Reactors,'' which was endorsed by the NRC 
by letter dated March 28, 2013 (ADAMS Package Accession No. 
ML13091A209).
    Date of issuance: June 26, 2018.
    Effective date: As of the date of issuance and shall be implemented 
on or before June 28, 2019.
    Amendment Nos.: Calvert Cliffs--324/302; Nine Mile Point--230/171; 
and, Ginna--128. A publicly-available version is in ADAMS under 
Accession No. ML18137A614; documents related to these amendments are 
listed in the Safety Evaluation enclosed with the amendments.
    Facility Operating License Nos. DPR-53, DPR-69, DPR-63, NPF-69, and 
DPR-18: Amendments revised the emergency plans.
    Date of initial notice in Federal Register: August 1, 2017 (82 FR 
35838).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated June 26, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: May 3, 2017, as supplemented by letter 
dated February 14, 2018.
    Brief description of amendments: The amendments revised the DNPS 
Technical Specification (TS) 5.5.12, ``Primary Containment Leakage Rate 
Testing Program,'' to allow for the permanent extension of the Type A 
integrated leak rate testing and the Type C leak rate testing 
frequencies.
    Date of issuance: June 29, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 257 (Unit 2) and 250 (Unit 3). A publicly-available 
version is in ADAMS under Accession No. ML18137A271; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-19 and DPR-25: 
Amendments revised the Renewed Facility Operating Licenses and TS.
    Date of initial notice in Federal Register: August 1, 2017 (82 FR 
35838). The supplemental letter dated February 14, 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 amendments is contained 
in a Safety Evaluation dated June 29, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: June 30, 2017, as supplemented by 
letters dated October 25, 2017, and June 5, 2018.
    Brief description of amendment: The amendment revised the license 
to delete the modification to install overcurrent protection on its 
emergency diesel generators which was required as part of Ginna's 
implementation of its risk-informed, performance-based fire protection 
program in accordance with 10 CFR 50.48(c).
    Date of issuance: June 25, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 127. A publicly-available version is in ADAMS under 
Accession No. ML18114A025; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-18: Amendment revised 
the Renewed Facility Operating License.
    Date of initial notice in Federal Register: October 3, 2017 (82 FR 
46097). The supplemental letters dated October 25, 2017, and June 5, 
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 June 25, 2018.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, 
Braidwood Station, Unit Nos. 1 and 2, Will County, Illinois and Docket 
Nos. STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle 
County, Illinois

    Date of amendment request: June 30, 2017, as supplemented by 
letters dated October 25, 2017, and May 29, 2018.
    Brief description of amendments: The amendments revised Technical 
Specification (TS) 3.1.4, ``Rod Group Alignment Limits,'' TS 3.1.5, 
``Shutdown Bank Insertion Limits,'' TS 3.1.6, ``Control Bank Insertion 
Limits,'' and TS 3.1.7, ``Rod Position Indication.''
    Date of issuance: June 27, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos: 196 (Braidwood, Unit 1) and 196 (Braidwood, Unit 2); 
202 (Bryon, Unit 1) and 202 (Bryon, Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18065A529; documents related 
to these amendments are listed in the

[[Page 33273]]

related Safety Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. NPF-72, NPF-77, NPF-37, and 
NPF-66: The amendments revised the Renewed Facility Operating Licenses 
and TSs.
    Date of initial notice in Federal Register: August 29, 2017 (82 FR 
41069). The supplemental letters dated October 25, 2017, and May 29, 
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 amendments is contained 
in a Safety Evaluation dated June 27, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: September 11, 2017.
    Brief description of amendment: The amendment revised the 
requirements in Technical Specification (TS) 3.3.6.1, ``Primary 
Containment and Drywell Isolation Instrumentation,'' by adding an 
ACTIONS note to Limiting Condition of Operation 3.3.6.1 to allow 
intermittent opening, under administrative control, of containment and 
drywell penetration flow paths that are isolated.
    Date of issuance: June 25, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 181. A publicly-available version is in ADAMS under 
Accession No. ML18157A084; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. NPF-58: Amendment revised the 
Facility Operating License and TS.
    Date of initial notice in Federal Register: November 7, 2017 (82 FR 
51652).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated June 25, 2018.
    No significant hazards consideration comments received: No.

South Carolina Electric & Gas Company, South Carolina Public Service 
Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station, Unit 
No. 1, Fairfield County, South Carolina

    Date of amendment request: October 6, 2017, as supplemented by 
letter dated April 19, 2018.
    Brief description of amendment: This amendment increased the 
Integrated Leak Rate Test Peak Calculated Containment Internal 
Pressure, Pa, listed in Technical Specification (TS) 6.8.4.g, 
``Containment Leakage Rate Testing Program,'' from 45.1 pounds per 
square inch gauge (psig) to 46.0 psig. It also removed the reference to 
Regulatory Guide 1.163, ``Performance-Based Containment Leak Test 
Program,'' and American National Standards Institute/American Nuclear 
Society (ANSI/ANS)-56.8-2002, ``Containment System Leakage Testing 
Requirements,'' and replaced the reference of Nuclear Energy Institute 
(NEI) 94-01, Revision 3-A, ``Industry Guideline for Implementing 
Performance-Based Option of 10 CFR part 50, Appendix J,'' with NEI 94-
01, Revision 2-A.
    Date of issuance: June 28, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 210. A publicly-available version is in ADAMS under 
Accession No. ML18141A668, documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-12: Amendment revised 
the Renewed Facility Operating License and the TS.
    Date of initial notice in Federal Register: November 21, 2017 (82 
FR 55409). The supplemental letter dated April 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 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 June 28, 2018.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Docket Nos. 50-348 and 50-364, 
Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2, Houston County, 
Alabama

    Date of amendment request: December 21, 2017.
    Brief description of amendments: The amendments modified Technical 
Specification (TS) 3.7.5, ``Auxiliary Feedwater (AFW) System,'' to 
establish a new Completion Time for the Condition where one steam 
supply to the turbine driven AFW pump is inoperable concurrent with an 
inoperable motor driven AFW train. In addition, the amendments added 
specific Conditions and Action requirements: (1) For when two motor 
driven AFW trains are inoperable at the same time and; (2) for when the 
turbine driven AFW train is inoperable either (a) due solely to one 
inoperable steam supply, or (b) due to reasons other than one 
inoperable steam supply. The proposed changes are consistent with NRC-
approved Technical Specification Task Force (TSTF) Traveler, TSTF-412, 
Revision 3, ``Provide Actions for One Steam Supply to Turbine Driven 
AFW/EFW [Emergency Feedwater] Pump Inoperable'' dated January 10, 2007.
    Date of issuance: June 27, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment Nos.: 219 (Unit 1) and 216 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18151A174. Documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. NPF-2 and NPF-8: The 
amendments revised the Renewed Facility Operating Licenses and TS.
    Date of initial notice in Federal Register: February 13, 2018 (83 
FR 6234).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated June 27, 2018.
    No significant hazards consideration comments received: No.

Susquehanna Nuclear, LLC, Docket Nos. 50-387 and 50-388, Susquehanna 
Steam Electric Station, Unit Nos. 1 and 2, Luzerne County, Pennsylvania

    Date of amendment request: December 14, 2017.
    Brief description of amendments: The amendments revised Technical 
Specification (TS) 3.6.4.1, ``Secondary Containment,'' Surveillance 
Requirement (SR) 3.6.4.1.1. The SR was revised to address conditions 
during which the secondary containment pressure may not meet the SR 
pressure requirements. The changes are based on Technical Specification 
Task Force (TSTF) Traveler TSTF-551, Revision 3, ``Revise Secondary 
Containment Surveillance Requirements.''
    Date of issuance: June 26, 2018.

[[Page 33274]]

    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment Nos.: 270 (Unit 1) and 252 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18150A281. Documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. NPF-14 and NPF-22: The 
amendments revised the Renewed Facility Operating Licenses and TS.
    Date of initial notice in Federal Register: February 27, 2018 (83 
FR 8520).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated June 26, 2018.
    No significant hazards consideration comments received: No.

Tennessee Valley Authority, Docket Nos. 50-390 and 50-391, Watts Bar 
Nuclear Plant, Units 1 and 2, Rhea County, Tennessee

    Date of amendment request: November 23, 2016, as supplemented by 
letters dated September 29, November 16, and December 27, 2017, and May 
11, 2018.
    Brief description of amendments: The amendments revised the 
Technical Specification (TS) requirements on control and shutdown rods, 
and rod and bank position indication in the Units 1 and 2, TS 3.1.5, 
``Rod Group Alignment Limits,'' TS 3.1.6, ``Shutdown Bank Insertion 
Limits,'' TS 3.1.7, ``Control Bank Insertion Limits,'' and TS 3.1.8, 
``Rod Position Indication.''
    Date of issuance: June 26, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 120 (Unit 1) and 20 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18079A029; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Facility Operating License Nos. NPF-90 and NPF-96: Amendments 
revised the Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: March 14, 2017 (82 FR 
13672). The supplemental letters dated September 29, November 16, and 
December 27, 2017, expanded the scope of the amendment request as 
originally noticed in the Federal Register. A second notice was 
published in the Federal Register on February 21, 2018 (83 FR 7500), 
which superseded the original notice in its entirety. The supplemental 
letter dated May 11, 2018, provided additional information that 
clarified the application, did not expand the scope of the application 
as re-noticed, and did not change the NRC staff's 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 June 26, 2018.
    No significant hazards consideration comments received: No.

IV. Notice of Issuance of Amendments to Facility Operating Licenses and 
Combined Licenses and Final Determination of No Significant Hazards 
Consideration and Opportunity for a Hearing (Exigent Public 
Announcement or Emergency Circumstances)

    During the period since publication of the last biweekly notice, 
the Commission has issued the following amendment. The Commission has 
determined for this amendment that the application for the amendment 
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.
    Because of exigent or emergency circumstances associated with the 
date the amendment was needed, there was not time for the Commission to 
publish, for public comment before issuance, its usual notice of 
consideration of issuance of amendment, proposed no significant hazards 
consideration determination, and opportunity for a hearing.
    For exigent circumstances, the Commission has either issued a 
Federal Register notice providing opportunity for public comment or has 
used local media to provide notice to the public in the area 
surrounding a licensee's facility of the licensee's application and of 
the Commission's proposed determination of no significant hazards 
consideration. The Commission has provided a reasonable opportunity for 
the public to comment, using its best efforts to make available to the 
public means of communication for the public to respond quickly, and in 
the case of telephone comments, the comments have been recorded or 
transcribed as appropriate and the licensee has been informed of the 
public comments.
    In circumstances where failure to act in a timely way would have 
resulted, for example, in derating or shutdown of a nuclear power plant 
or in prevention of either resumption of operation or of increase in 
power output up to the plant's licensed power level, the Commission may 
not have had an opportunity to provide for public comment on its no 
significant hazards consideration determination. In such case, the 
license amendment has been issued without opportunity for comment. If 
there has been some time for public comment but less than 30 days, the 
Commission may provide an opportunity for public comment. If comments 
have been requested, it is so stated. In either event, the State has 
been consulted by telephone whenever possible.
    Under its regulations, the Commission may issue and make an 
amendment immediately effective, notwithstanding the pendency before it 
of a request for a hearing from any person, in advance of the holding 
and completion of any required hearing, where it has determined that no 
significant hazards consideration is involved.
    The Commission has applied the standards of 10 CFR 50.92 and has 
made a final determination that the amendment involves no significant 
hazards consideration. The basis for this determination is contained in 
the documents related to this action. Accordingly, the amendment has 
been issued and made effective as indicated.
    Unless otherwise indicated, the Commission has determined that this 
amendment satisfies 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 this amendment. If the Commission has prepared an 
environmental assessment under the special circumstances provision in 
10 CFR 51.12(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 
application for amendment, (2) the amendment to Facility Operating 
License or Combined License, as applicable, 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.

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

    The Commission is also offering an opportunity for a hearing with 
respect to the issuance of the amendment. Within 60 days after the date 
of publication of this notice, any persons (petitioner) whose interest 
may be affected by this

[[Page 33275]]

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 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 <a href="/cdn-cgi/l/email-protection#88e0ede9fae1e6efa6ece7ebe3edfcc8e6faeba6efe7fe"><span class="__cf_email__" data-cfemail="167e7377647f7871387279757d73625678647538717960">[email protected]</span></a>, 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

[[Page 33276]]

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 <a href="/cdn-cgi/l/email-protection#723f213a365c2017011d07001117321c00115c151d04"><span class="__cf_email__" data-cfemail="612c3229254f3304120e14130204210f13024f060e17">[email protected]</span></a>, 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.

Exelon Generation Company, LLC, Docket Nos. 50-277 and 50-278, Peach 
Bottom Atomic Power Station, Unit Nos. 2 and 3 (Peach Bottom), York 
County, Pennsylvania

    Date of amendment request: June 21, 2018.
    Description of amendments: The amendments revised the Peach Bottom 
Technical Specifications (TSs) for a one-time suspension of the 
emergency diesel generator (EDG) No. 4 (E-4) surveillance requirements. 
Specifically, the amendments revised TS Surveillance Requirements 
3.8.1.2, 3.8.1.3, 3.8.1.6, and 3.8.3.4 to suspend performing required 
monthly surveillance testing on the E-4 EDG until the E-3 EDG is 
returned to operable status, not to exceed 2205 hours Eastern Time on 
June 27, 2018.
    Date of issuance: June 23, 2018.
    Effective date: June 23, 2018.
    Amendment Nos.: 318 (Unit 1) and 321 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18173A042. Documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-44 and DPR-56: The 
amendments revised the Renewed Facility Operating Licenses and TSs.
    Public comments requested as to proposed no significant hazards 
consideration: No.
    The Commission's related evaluation of the amendments, finding of 
emergency circumstances, State consultation, and final no significant 
hazards consideration determination are contained in a Safety 
Evaluation dated June 23, 2018.
    Attorney for licensee: J. Bradley Fewell, Vice President and Deputy 
General Counsel, Exelon Generation Company, LLC, 200 Exelon Way, 
Kennett Square, PA 19348.
    NRC Branch Chief: James G. Danna.

    Dated at Rockville, Maryland, this 5th day of July 2018.

    For the Nuclear Regulatory Commission.
Gregory F. Suber,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2018-14779 Filed 7-16-18; 8:45 am]
 BILLING CODE 7590-01-P


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