[Federal Register Volume 83, Number 59 (Tuesday, March 27, 2018)]
[Notices]
[Pages 13146-13156]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-05905]


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NUCLEAR REGULATORY COMMISSION

[NRC-2018-0059]


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

[[Page 13147]]

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 February 27, 2018, to March 12, 2018. The 
last biweekly notice was published on March 13, 2018.

DATES: Comments must be filed by April 26, 2018. A request for a 
hearing must be filed by May 29, 2018.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0059. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     Mail comments to: May Ma, Office of Administration, Mail 
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Ikeda Betts, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001; telephone: 301-415-1959, email: 
[email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2018-0059, facility name, unit 
number(s), plant docket number, application date, and subject when 
contacting the NRC about the availability of information for this 
action. You may obtain publicly-available information related to this 
action by any of the following methods:
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0059.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
ADAMS accession number for each document referenced (if it is available 
in ADAMS) is provided the first time that it is mentioned in this 
document.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2018-0059, facility name, unit 
number(s), plant docket number, application date, and subject in your 
comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

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

    The Commission has made a proposed determination that the following 
amendment requests involve no significant hazards consideration. Under 
the Commission's regulations in Sec.  50.92 of title 10 of the Code of 
Federal Regulations (10 CFR), this means that operation of the facility 
in accordance with the proposed amendment would not (1) involve a 
significant increase in the probability or consequences of an accident 
previously evaluated, or (2) create the possibility of a new or 
different kind of accident from any accident previously evaluated; or 
(3) involve a significant reduction in a margin of safety. The basis 
for this proposed determination for each amendment request is shown 
below.
    The Commission is seeking public comments on this proposed 
determination. Any comments received within 30 days after the date of 
publication of this notice will be considered in making any final 
determination.
    Normally, the Commission will not issue the amendment until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment 
involves no significant hazards consideration. In addition, the 
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment 
period such that failure to act in a timely way would result, for 
example in derating or shutdown of the facility. If the Commission 
takes action prior to the expiration of either the comment period or 
the notice period, it will publish in the Federal Register a notice of 
issuance. If the Commission makes a final no significant hazards 
consideration determination, any hearing will take place after 
issuance. The Commission expects that the need to take this action will 
occur very infrequently.

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

    Within 60 days after the date of publication of this notice, any 
persons (petitioner) whose interest may be affected by this action may 
file a request for a hearing and petition for leave to intervene 
(petition) with respect to the action. Petitions shall be filed in 
accordance with the Commission's ``Agency Rules of Practice and 
Procedure'' in 10 CFR part 2. Interested persons should consult a 
current copy of 10 CFR 2.309. The NRC's regulations are accessible 
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of 
the regulations is available at the NRC's Public Document Room, located 
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first 
floor), Rockville, Maryland 20852. If a petition is filed,

[[Page 13148]]

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 [email protected], or by 
telephone at 301-415-1677, to (1) request a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign submissions and access the E-Filing 
system for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a petition or 
other adjudicatory document (even in instances in which the 
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the 
Secretary will establish an electronic docket for the hearing in this 
proceeding if the Secretary has not already established an electronic 
docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant

[[Page 13149]]

has obtained a digital ID certificate and a docket has been created, 
the participant can then submit adjudicatory documents. Submissions 
must be in Portable Document Format (PDF). Additional guidance on PDF 
submissions is available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is 
considered complete at the time the document is submitted through the 
NRC's E-Filing system. To be timely, an electronic filing must be 
submitted to the E-Filing system no later than 11:59 p.m. Eastern Time 
on the due date. Upon receipt of a transmission, the E-Filing system 
time-stamps the document and sends the submitter an email notice 
confirming receipt of the document. The E-Filing system also 
distributes an email notice that provides access to the document to the 
NRC's Office of the General Counsel and any others who have advised the 
Office of the Secretary that they wish to participate in the 
proceeding, so that the filer need not serve the document on those 
participants separately. Therefore, applicants and other participants 
(or their counsel or representative) must apply for and receive a 
digital ID certificate before adjudicatory documents are filed so that 
they can obtain access to the documents via the E-Filing system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic 
Filing Help Desk through the ``Contact Us'' link located on the NRC's 
public website at http://www.nrc.gov/site-help/e-submittals.html, by 
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m. 
and 6 p.m., Eastern Time, Monday through Friday, excluding government 
holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
stating why there is good cause for not filing electronically and 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, 11555 
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and 
Adjudications Staff. Participants filing adjudicatory documents in this 
manner are responsible for serving the document on all other 
participants. Filing is considered complete by first-class mail as of 
the time of deposit in the mail, or by courier, express mail, or 
expedited delivery service upon depositing the document with the 
provider of the service. A presiding officer, having granted an 
exemption request from using E-Filing, may require a participant or 
party to use E-Filing if the presiding officer subsequently determines 
that the reason for granting the exemption from use of E-Filing no 
longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the 
Commission or the presiding officer. If you do not have an NRC-issued 
digital ID certificate as described above, click cancel when the link 
requests certificates and you will be automatically directed to the 
NRC's electronic hearing dockets where you will be able to access any 
publicly available documents in a particular hearing docket. 
Participants are requested not to include personal privacy information, 
such as social security numbers, home addresses, or personal phone 
numbers in their filings, unless an NRC regulation or other law 
requires submission of such information. For example, in some 
instances, individuals provide home addresses in order to demonstrate 
proximity to a facility or site. With respect to copyrighted works, 
except for limited excerpts that serve the purpose of the adjudicatory 
filings and would constitute a Fair Use application, participants are 
requested not to include copyrighted materials in their submission.
    For further details with respect to these license amendment 
applications, see the application for amendment which is available for 
public inspection in ADAMS and at the NRC's PDR. For additional 
direction on accessing information related to this document, see the 
``Obtaining Information and Submitting Comments'' section of this 
document.

Entergy Nuclear Operations, Inc., Docket No. 50-293, Pilgrim Nuclear 
Power Station (PNPS), Plymouth County, Massachusetts

    Date of amendment request: January 12, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18023A795.
    Description of amendment request: The amendment would revise the 
PNPS Site Emergency Plan (SEP) for the permanently shutdown and 
defueled condition. The amendment would revise the PNPS on-shift and 
Emergency Response Organization (ERO) staffing for the permanently 
shutdown and defueled condition.
    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 PNPS SEP do not impact the function 
of plant structures, systems, or components. The proposed changes do 
not affect accident initiators or precursors, nor does it alter 
design assumptions. The proposed changes do not prevent the ability 
of the on-shift and augmented ERO to perform their intended 
functions to mitigate the consequences of any accident or event that 
will be credible in the permanently shut down and defueled 
condition. The proposed changes only remove positions that will no 
longer be credited in the PNPS SEP.
    Therefore, the proposed 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 reduce the number of on-shift and augmented 
ERO positions commensurate with the hazards associated with a 
permanently shut down 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 amendment does not create the 
possibility of a new or different kind of accident from any 
previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    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 are 
associated with the PNPS SEP and do not impact operation of the 
plant or its response to transients or accidents. The 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.

[[Page 13150]]

    Safety analysis acceptance criteria are not affected by the 
proposed changes. The revised PNPS SEP will continue to provide the 
necessary response staff with the proposed changes.
    Therefore, 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 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: William B. Glew, Jr., Associate General 
Counsel--Nuclear, Legal Nuclear and Environmental, Entergy Nuclear 
Operations, Inc., 440 Hamilton Avenue, White Plains, NY 10601.
    NRC Branch Chief: Douglas A. Broaddus.

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

    Date of amendment request: January 29, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18029A509.
    Description of amendment request: The amendments would revise the 
Limerick Generating Station, Units 1 and 2, Technical Specifications 
(TSs). The proposed changes would lower the TS standby liquid control 
system (SLCS) surveillance requirement (SR) pump flowrate value, raise 
the TS SLCS SR Boron-10 enrichment value of the sodium pentaborate 
added to the SLCS tank, and expand the operating range in the sodium 
pentaborate solution temperature/concentration requirements figure. 
These changes will provide increased testing margin and operational 
flexibility.
    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.
    The proposed changes will lower the SLCS TS SR pump flowrate 
value, raise the TS SLCS SR Boron-10 (B-10) Enrichment value of the 
Sodium Pentaborate added to the SLCS tank and expand the operating 
range contained in the TS Figure for Sodium Pentaborate Solution 
Temperature/Concentration Requirements. These changes will provide 
greater operating flexibility. The proposed changes will maintain 
plant operation within the bounds of the current analysis for the 
ATWS [anticipated transient without scram] events and for accident 
source term dose limits in the Loss of Coolant Accident (LOCA) 
analysis.
    The proposed changes do not alter the physical design of any 
plant structure, system, or component; therefore, the proposed 
changes have no adverse effect on plant operation, or the 
availability or operation of any accident mitigation equipment. The 
plant response to the design basis accidents does not change. 
Operation or failure of the SLCS is not assumed to be an initiator 
of any analyzed event in the Updated Final Safety Analysis Report 
(UFSAR) and cannot cause an accident. The changes to the SLCS TS SRs 
are bounded by current analyses for the ATWS events and LOCA and 
therefore the changes do not adversely affect consequences of any 
accident previously evaluated.
    The proposed changes conform to NRC regulatory requirements 
regarding ATWS events and AST [alternative source term] dose 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 change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed changes will lower the TS SLCS SR pump flowrate 
value, raise the TS SLCS SR B-10 Enrichment value of the Sodium 
Pentaborate added to the SLCS tank and expand the operating range in 
the Sodium Pentaborate Solution Temperature/Concentration 
Requirements Figure. These changes will provide greater operating 
flexibility. The proposed changes will maintain plant operation 
within the bounds of the current analysis for the ATWS events and 
for accident source term dose limits in the LOCA analysis.
    The proposed changes do not alter the plant configuration (no 
new or different type of equipment is being installed) or require 
any new or unusual operator actions. The proposed changes do not 
alter the safety limits or safety analysis assumptions associated 
with the operation of the plant. The proposed changes do not 
introduce any new failure modes that could result in a new accident. 
The proposed changes do not reduce or adversely affect the 
capabilities of any plant structure, system, or component in the 
performance of their safety function. Also, the response of the 
plant and the operators following the design basis accidents is 
unaffected by the proposed changes.
    Therefore, the proposed changes do 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 will lower the TS SLCS SR pump flowrate 
value, raise the TS SLCS SR B-10 Enrichment value of the Sodium 
Pentaborate added to the SLCS tank and expand the operating range in 
the Sodium Pentaborate Solution Temperature/Concentration 
Requirements Figure. These changes will provide greater operating 
flexibility. The proposed changes will maintain plant operation 
within the bounds of the current analysis for the ATWS events and 
for accident source term dose limits in the LOCA analysis.
    The proposed changes have no adverse effect on plant operation, 
or the availability or operation of any accident mitigation 
equipment. The plant response to the design basis accidents does not 
change. 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 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.
    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.

Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50-
425, Vogtle Electric Generating Plant, Units 1 and 2 (VEGP), Burke 
County, Georgia

    Date of amendment request: October 11, 2017. A publicly-available 
version is in ADAMS under Accession No. ML17284A348.
    Description of amendment request: The proposed amendments would 
revise the VEGP Updated Final Safety Analysis Report (UFSAR) to 
incorporate a Tornado Missile Risk Evaluator (TMRE) Methodology based 
on Nuclear Energy Institute (NEI) 17-02, Revision 1, ``Tornado Missile 
Risk (TMRE) Industry Guidance Document,'' September 2017 (ADAMS 
Accession No. ML17268A036). This methodology can only be applied to 
discovered conditions where tornado missile protection is not currently 
provided, and cannot be used to avoid providing tornado missile 
protection in the plant modification process.
    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 13151]]

consideration, which is presented below with staff edits in square 
brackets:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendment does not involve an increase in the 
probability of an accident previously evaluated. The relevant 
accident previously evaluated is a Design Basis Tornado impacting 
the VEGP site. The probability of a Design Basis Tornado is driven 
by external factors and is not affected by the proposed amendment. 
There are no changes required to any of the previously evaluated 
accidents in the UFSAR.
    The proposed amendment does not involve a significant increase 
in the consequences of a Design Basis Tornado. [The methodology as 
proposed does not alter any input assumptions or results of the 
accident analyses. Instead, it reflects a methodology to more 
realistically evaluate the probability of unacceptable consequences 
of a Design Basis Tornado. As such, there is no significant increase 
in the consequence of an accident previously evaluated. A similar 
consideration would apply in the event additional non-conforming 
conditions are discovered in the future.]
    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 will involve no physical changes to the 
existing plant, so no new malfunctions could create the possibility 
of a new or different kind of accident. The proposed amendment makes 
no changes to conditions external to the plant that could create the 
possibility of a new or different kind of accident. The proposed 
change will not create the possibility of a new or different kind of 
accident due to new accident precursors, failure mechanisms, 
malfunctions, or accident initiators not considered in the design 
and licensing bases. The existing Updated Final Safety Analysis 
Report (UFSAR) accident analysis will continue to meet requirements 
for the scope and type of accidents that require analysis.
    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 amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed amendment does not exceed or alter any controlling 
numerical value for a parameter established in the UFSAR or 
elsewhere in the VEGP [licensing basis] related to design basis or 
safety limits. The change does not impact any UFSAR Chapter 6 or 15 
Safety Analyses, and those analyses remain valid. The change does 
not reduce diversity or redundancy as required by regulation or 
credited in the UFSAR. The change does not reduce defense-in-depth 
as described in the UFSAR. Therefore, the proposed amendment does 
not involve a significant reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis as edited by the 
NRC staff 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: Jennifer M. Buettner, Associate General 
Counsel, Southern Nuclear Operating Company, 40 Iverness Center 
Parkway, Birmingham, AL 35242.
    NRC Branch Chief: Douglas A. Broaddus.

III. Previously Published Notices of Consideration of Issuance of 
Amendments to Facility Operating Licenses and Combined Licenses, 
Proposed No Significant Hazards Consideration Determination, and 
Opportunity for a Hearing

    The following notices were previously published as separate 
individual notices. The notice content was the same as above. They were 
published as individual notices either because time did not allow the 
Commission to wait for this biweekly notice or because the action 
involved exigent circumstances. They are repeated here because the 
biweekly notice lists all amendments issued or proposed to be issued 
involving no significant hazards consideration.
    For details, see the individual notice in the Federal Register on 
the day and page cited. This notice does not extend the notice period 
of the original notice.

PSEG Nuclear LLC and Exelon Generation Company, LLC, Docket Nos. 50-272 
and 50-311, Salem Nuclear Generating Station, Unit Nos. 1 and 2, Salem 
County, New Jersey

    Date of amendment request: February 8, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18040A301.
    Brief description of amendment request: The proposed amendments 
would modify the Salem Nuclear Generating Station, Unit Nos. 1 and 2, 
Technical Specification (TS)-allowed outage time for more than one 
inoperable analog rod position indicator from 1 hour to 24 hours and 
change the basis for entry into the TS actions for inoperable rod 
position indicators from ``per bank'' to ``per group.'' The proposed 
amendments would also separate existing TS 3.1.3.2.1, Action a.1, into 
two separate actions and would remove the duplicative Action b (Unit 
No. 1 only).
    Date of publication of individual notice in Federal Register: March 
1, 2018 (83 FR 8904).
    Expiration date of individual notice: April 2, 2018 (public 
comments); April 30, 2018 (hearing requests).

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

    During the period since publication of the last biweekly notice, 
the Commission has issued the following amendments. The Commission has 
determined for each of these amendments that the application complies 
with the standards and requirements of the Atomic Energy Act of 1954, 
as amended (the Act), and the Commission's rules and regulations. The 
Commission has made appropriate findings as required by the Act and the 
Commission's rules and regulations in 10 CFR chapter I, which are set 
forth in the license amendment.
    A notice of consideration of issuance of amendment to facility 
operating license or combined license, as applicable, proposed no 
significant hazards consideration determination, and opportunity for a 
hearing in connection with these actions, was published in the Federal 
Register as indicated.
    Unless otherwise indicated, the Commission has determined that 
these amendments satisfy the criteria for categorical exclusion in 
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), 
no environmental impact statement or environmental assessment need be 
prepared for these 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.

Dominion Energy Nuclear Connecticut, Inc., Docket Nos. 50-245, 50-336, 
and 50-423, Millstone Power Station, Unit Nos. 1, 2, and 3 (Millstone 
1, 2, and 3), New London County, Connecticut

    Date of amendment request: June 15, 2017.
    Brief description of amendments: The amendments revised the 
facility operating licenses by replacing all references to the former 
company name, ``Dominion Nuclear Connecticut, Inc.'' (or DNC), with 
``Dominion Energy

[[Page 13152]]

Nuclear Connecticut, Inc.'' (or DENC), including the cover of the 
Environmental Protection Plan in Appendix B for Millstone 3 and the 
Design Features page for Millstone 1, 2, and 3. Additionally, 
references to DNC's former ultimate parent company, ``Dominion 
Resources, Inc.,'' were replaced with the new name ``Dominion Energy, 
Inc.''
    Date of issuance: February 26, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days.
    Amendment Nos.: 118, 334, and 271. A publicly-available version is 
in ADAMS under Accession No. ML18038B200; documents related to these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Facility Operating License Nos. DPR-21, DPR-65, and NPF-49: The 
amendments revised the facility operating licenses and technical 
specifications.
    Date of initial notice in Federal Register: October 10, 2017 (82 FR 
47035) .
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated February 26, 2018.
    No significant hazards consideration comments received: No.

Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear 
Plant (PNP), Van Buren County, Michigan

    Date of amendment request: November 1, 2017, as supplemented by 
letter dated January 24, 2018.
    Brief description of amendment: The amendment revised the fire 
protection program transition license condition 2.C.(3)(c)2. by 
extending the full implementation date by one fuel cycle from the fall 
2018 refueling outage to the summer 2020 refueling outage. The 
amendment also revised Paragraph 2.C.(3) of the Renewed Facility 
Operating License No. DPR-20 for PNP to incorporate the revised fire 
protection documentation and approvals.
    Date of issuance: February 27, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 265. A publicly-available version is in ADAMS under 
Accession No. ML18039A244; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-20: Amendment revised 
the Renewed Facility Operating License.
    Date of initial notice in Federal Register: December 5, 2017 (82 FR 
57472). The supplemental letter dated January 24, 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 February 27, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: July 19, 2017, as supplemented by 
letters dated December 6, 2017; February 19, 2018; and February 27, 
2018.
    Brief description of amendments: The amendments revised the 
existing Technical Specification requirements related to ``operations 
with a potential for draining the reactor vessel'' with new 
requirements on reactor pressure vessel water inventory control to 
protect Safety Limit 2.1.4. Safety Limit 2.1.4 requires reactor 
pressure vessel water level to be greater than the top of active 
irradiated fuel. The changes are based on Technical Specifications Task 
Force Traveler TSTF-542, Revision 2, ``Reactor Pressure Vessel Water 
Inventory Control.''
    Date of issuance: February 27, 2018.
    Effective date: As of the date of issuance and shall be implemented 
no later than May 31, 2019.
    Amendment Nos.: 227 (Unit 1) and 190 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18017A201; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. NPF-39 and NPF-85: 
Amendments revised the Renewed Facility Operating Licenses and 
Technical Specifications.
    Date of initial notice in Federal Register: September 12, 2017 (82 
FR 42848). The supplemental letters dated December 6, 2017; February 
19, 2018; and February 27, 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 February 27, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: April 24, 2017.
    Brief description of amendments: The amendments revised the 
existing technical specification (TS) requirements associated with the 
main condenser offgas monitoring instrumentation and gaseous effluents. 
Specifically, certain requirements are relocated from the TSs to 
licensee-controlled documents such that future changes can be made to 
these provisions pursuant to 10 CFR 50.59 or by the regulatory 
requirements applicable to the licensee-controlled document.
    Date of issuance: February 28, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days.
    Amendment Nos.: 228 (Unit 1) and 191 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18025B769; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. NPF-39 and NPF-85: The 
amendments revised the Renewed Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: July 5, 2017 (82 FR 
31096).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated February 28, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: May 31, 2017.
    Brief description of amendment: The amendment revised the run time 
for Surveillance Requirement (SR) 3.6.4.3.1 for Technical Specification 
(TS) 3.6.4.3, ``Standby Gas Treatment (SGT) System,'' and SR 3.7.2.1 
for TS 3.7.2, ``Control Room Envelope Filtration (CREF) System.'' The 
run time for SR 3.6.4.3.1 would be reduced from a continuous 10 hours 
to a continuous 15 minutes, and the run time for SR 3.7.2.1 would be 
reduced from 1 hour to 15 minutes at

[[Page 13153]]

frequencies controlled in accordance with the Surveillance Frequency 
Control Program.
    Date of issuance: March 6, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 166. A publicly-available version is in ADAMS under 
Accession No. ML18032A177; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-69: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: August 1, 2017 (82 FR 
35839). The Commission's related evaluation of the amendment is 
contained in a Safety Evaluation dated March 6, 2018.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-219, Oyster Creek Nuclear 
Generating Station (Oyster Creek), Ocean County, New Jersey

    Date amendment request: February 28, 2017, as supplemented by 
letters dated September 20 and November 10, 2017.
    Brief description of amendment: The amendment changed the site 
emergency plan to revise the on-shift staffing and the Emergency 
Response Organization staffing for the permanently defueled condition.
    Date of issuance: March 7, 2018.
    Effective date: Following the docketing of the certifications 
required by 10 CFR 50.82(a)(1) that Oyster Creek has been permanently 
defueled and shall be implemented within 60 days, as noted, but will 
not exceed March 29, 2020.
    Amendment No.: 293. A publicly-available version is in ADAMS under 
Accession No. ML17356A213; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-16: Amendment revised 
the renewed facility operating license.
    Date of initial notice in Federal Register; April 25, 2017 (82 FR 
19103). The supplemental letters dated September 20 and November 10, 
2017, provided additional information that clarified the application, 
did not expand the scope of the application as originally noticed, and 
did not change the staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 7, 2018.
    No significant hazards consideration comments received: No.

FirstEnergy Nuclear Operating Company, et al., Docket Nos. 50-334 and 
50-412, Beaver Valley Power Station, Unit Nos. 1 and 2, Beaver County, 
Pennsylvania

    Date of amendment request: April 9, 2017.
    Brief description of amendments: The amendments revised Technical 
Specifications Section 4.2.1, ``Fuel Assemblies,'' and Section 5.6.3, 
``Core Operating Limits Report (COLR),'' to allow the use of Optimized 
ZIRLO\TM\ as an approved fuel rod cladding material. In the letter 
dated April 9, 2017, the licensee also requested an exemption from 
certain requirements of 10 CFR 50.46 and 10 CFR part 50, Appendix K, in 
accordance with 10 CFR 50.12, to support the license amendments.
    Date of issuance: March 1, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days.
    Amendment Nos.: 302 (Unit No. 1) and 191 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18022B116; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. DPR-66 and NPF-73: 
Amendments revised the Renewed Facility Operating Licenses and 
Technical Specifications.
    Date of initial notice in Federal Register: July 18, 2017 (82 FR 
32881).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 1, 2018.
    No significant hazards consideration comments received: No.

NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold 
Energy Center (DAEC), Linn County, Iowa

    Date of amendment request: March 24, 2017.
    Brief description of amendment: The amendment revised the DAEC 
technical specification (TS) Table 3.3.2.1-1, ``Control Rod Block 
Instrumentation,'' by relocating certain cycle-specific Minimum 
Critical Power Ratio values to the DAEC Core Operating Limits Report. 
The amendment also adds a requirement to DAEC TS 5.6.5, ``Core 
Operating Limits Report.''
    Date of issuance: March 7, 2018.
    Effective date: As of the date of its issuance and shall be 
implemented within 180 days of the date of issuance.
    Amendment No.: 303. A publicly-available version is in ADAMS under 
Accession No. ML18011A059; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-49: Amendment revised 
the Renewed Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: May 23, 2017 (82 FR 
23627).
    The Commission's related evaluation of the amendment is contained 
in a Safety evaluation dated March 7, 2018.
    No significant hazards consideration comments received: No.

NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold 
Energy Center (DAEC), Linn County, Iowa

    Date of amendment request: April 20, 2017.
    Brief description of amendment: The amendment revised the DAEC 
Technical Specification 3.1.2, ``Reactivity Anomalies,'' to change the 
method used to perform the reactivity anomaly surveillance. The new 
method would allow performance of the surveillance based on the 
difference between the monitored (i.e., actual) core reactivity and the 
predicted core reactivity. The surveillance is currently performed 
based on the difference between the monitored control rod density and 
the predicted control rod density.
    Date of issuance: March 9, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of the date of issuance.
    Amendment No.: 304. A publicly-available version is in ADAMS under 
Accession No. ML18016A627; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-49: The amendment 
revised the Technical Specifications.
    Date of initial notice in Federal Register: June 19, 2017 (82 FR 
27889).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 9, 2018.
    No significant hazards consideration comments received: No.

Northern States Power Company (NSPM), Docket No. 50-263, Monticello 
Nuclear Generating Plant, Wright County, Minnesota

    Date of amendment request: March 24, 2017, as supplemented by 
letter dated September 20, 2017.
    Brief description of amendment: The amendment revises the 
Monticello Nuclear Generating Plant Emergency

[[Page 13154]]

Plan to increase the staff augmentation times for certain emergency 
response organization positions from 30 and 60 minutes to 60 and 90 
minutes, respectively. Additionally, the amendment defines facility 
activation, removes references to augmenting resources from the Prairie 
Island Nuclear Generating Plant, removes a 30-minute Electrical 
Maintenance Responder, clarifies transfer of Direction and Control 
responsibilities, and implements various administrative changes to 
position titles, figures, etc.
    Date of issuance: March 5, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days of issuance.
    Amendment No.: 196. A publicly-available version is in ADAMS under 
Accession No. ML17349A916; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-22: The amendment 
revised the Monticello Nuclear Generating Plant Site Emergency Plan.
    Date of initial notice in Federal Register: May 9, 2017 (82 FR 
21559). The supplemental letter dated September 20, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 5, 2018.
    No significant hazards consideration comments received: No.

Northern States Power Company--Minnesota, Docket No. 50-263, Monticello 
Nuclear Generating Plant, Wright County, Minnesota

    Date of amendment request: March 31, 2017, as supplemented by 
letter dated September 25, 2017.
    Brief description of amendment: The amendment revised the emergency 
action level scheme to one based on the Nuclear Energy Institute (NEI) 
document NEI 99 01, Revision 6, ``Development of Emergency Action 
Levels for Non-Passive Reactors,'' dated November 21, 2012. NEI 99-01, 
Revision 6, was endorsed by the NRC by letter dated March 28, 2013.
    Date of issuance: March 6, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days of issuance.
    Amendment No.: 197. A publicly-available version is in ADAMS under 
Accession No. ML17345A046; documents related to this amendment are 
listed in the safety evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-22: The amendment 
revised the Monticello Nuclear Generating Plant Emergency Plan.
    Date of initial notice in Federal Register: June 6, 2017 (82 FR 
26134). The supplemental letter dated September 25, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the NRC staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a safety evaluation dated March 6, 2018.
    No significant hazards consideration comments received: No.

Northern States Power Company, Docket Nos. 50-282 and 50-306, Prairie 
Island

Nuclear Generating Plant, Units 1 and 2, Goodhue County, Minnesota

    Date of amendment request: February 23, 2017, as supplemented by 
letter dated September 20, 2017.
    Brief description of amendments: The amendment revised the Prairie 
Island Nuclear Generating Plant, Units 1 and 2, Emergency Plan to 
increase the staff augmentation times for certain emergency response 
organization positions from 30 and 60 minutes to 60 and 90 minutes. 
Additionally, the changes defined facility activation, removed 
references to augmenting resources from the Monticello Nuclear 
Generating Plant, removed 30-minute Electrical Maintenance and 30-
minute Radwaste Operator Responders, clarified transfer of Direction 
and Control responsibilities, and implemented various administrative 
changes to position titles, figures, etc.
    Date of issuance: March 5, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days of issuance.
    Amendment Nos.: 223--Unit 1; 210--Unit 2. A publicly-available 
version is in ADAMS under Accession No. ML17362A202; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-42 and DPR-60: The 
amendments revised the Prairie Island Nuclear Generating Plant, Units 1 
and 2, Emergency Plan.
    Date of initial notice in Federal Register: April 11, 2017 (82 FR 
17459). The supplemental letter dated September 20, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 5, 2018.
    No significant hazards consideration comments received: No.

Northern States Power Company--Minnesota, Docket Nos. 50-282 and 50-
306, Prairie Island

Nuclear Generating Plant, Units 1 and 2, Goodhue County, Minnesota

    Date of amendment request: March 29, 2017, as supplemented by 
letter dated September 27, 2017.
    Brief description of amendments: The amendments revised the 
emergency action level scheme to one based on the Nuclear Energy 
Institute (NEI) document NEI 99-01, Revision 6, ``Development of 
Emergency Action Levels for Non-Passive Reactors,'' dated November 21, 
2012. NEI 99-01, Revision 6, was endorsed by the NRC by letter dated 
March 28, 2013.
    Date of issuance: March 6, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days of issuance.
    Amendment Nos.: 224 (Unit 1) and 211 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML17346A361; documents related 
to these amendments are listed in the safety evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-42 and DPR-60: The 
amendments revised the Prairie Island Nuclear Generating Plant, Units 1 
and 2, Emergency Plan.
    Date of initial notice in Federal Register: May 23, 2017 (82 FR 
23628). The supplemental letter dated September 27, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the NRC staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a safety evaluation dated March 6, 2018.
    No significant hazards consideration comments received: No.

[[Page 13155]]

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

    Date of amendment request: March 31, 2017, as supplemented by 
letter dated September 26, 2017.
    Brief description of amendment: The amendment revised the FCS 
renewed facility operating license, definitions, and Technical 
Specification (TS) sections to align with those required for the 
Permanently Defueled TS that will reflect decommissioning requirements.
    Date of issuance: March 6, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 297. A publicly-available version is in ADAMS under 
Accession No. ML18010A087; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-40: The amendment 
revised the renewed facility operating license and TS.
    Date of initial notice in Federal Register: June 6, 2017 (82 FR 
26135). The supplemental letter dated September 26, 2017, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the NRC staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 6, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: November 15, 2016, as supplemented by 
letters dated June 22, 2017; September 11, 2017; October 12, 2017; and 
February 9, 2018.
    Brief description of amendments: The amendments revise Technical 
Specification 5.5.17, ``Containment Leakage Rate Testing Program.'' 
Specifically, the amendments increased the existing Type A integrated 
leakage rate test program test interval from 10 years to 15 years; 
adopted an extension of the containment isolation valve leakage testing 
(Type C) frequency from 60 months to 75 months; adopted the use of 
American National Standards Institute/American Nuclear Society (ANSI/
ANS) 56.8-2002, ``Containment System Leakage Testing Requirements''; 
and adopted a grace interval of 9 months for Type A, Type B, and Type C 
leakage tests, in accordance with Nuclear Energy Institute (NEI) 94-01, 
Revision 2-A and Revision 3-A, ``Industry Guideline for Implementing 
Performance-Based Option of 10 CFR part 50, Appendix J.''
    Date of issuance: February 28, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 217 (Unit 1) and 214 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML17261A087; 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 
Technical Specifications.
    Date of initial notice in Federal Register: January 3, 2017 (82 FR 
161). The supplemental letters dated June 22, 2017; September 11, 2017; 
October 12, 2017; and February 9, 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 February 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, Units 1 and 2, Houston County, Alabama

    Date of amendment request: March 22, 2017.
    Brief description of amendments: The amendment revised Technical 
Specification 3.7.1, ``Main Steam Safety Valves (MSSVs),'' to resolve a 
non-conservative moderator temperature coefficient value.
    Date of issuance: March 1, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment Nos.: 218 (Unit 1) and 215 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML17291A781; 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 
Technical Specifications.
    Date of initial notice in Federal Register: May 9, 2017 (82 FR 
21562).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 1, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: September 22, 2017, as supplemented by 
letter dated January 19, 2018.
    Description of amendments: The amendment authorized changes to the 
VEGP, Units 3 and 4, Updated Final Safety Analysis Report in the form 
of departures from the incorporated plant-specific Design Control 
Document Tier 2 and Tier 2* information to modify the licensing 
requirements for the American Society of Mechanical Engineers (ASME) 
Class 1 piping component analysis from limited to design-by-rule 
evaluations described in ASME Section III, NB-3600, to include the 
ability to perform design-by-analysis evaluations, as described in ASME 
Section III, NB-3200.
    Date of issuance: February 22, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 109 (Unit 3) and 108 (Unit 4). A publicly-available 
version is in ADAMS under Accession No. ML18026A765; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendment.
    Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment 
revised the Facility Combined License.
    Date of initial notice in Federal Register: October 24, 2017 (82 FR 
49241). The supplement dated January 19, 2018, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the NRC 
staff's original proposed no significant hazards consideration 
determination.
    The Commission's related evaluation of the amendments is contained 
in the Safety Evaluation dated February 22, 2018.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, on March 19, 2018.


[[Page 13156]]


    For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2018-05905 Filed 3-26-18; 8:45 am]
 BILLING CODE 7590-01-P