[Federal Register Volume 84, Number 48 (Tuesday, March 12, 2019)]
[Notices]
[Pages 8906-8916]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-03911]


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NUCLEAR REGULATORY COMMISSION

[NRC-2019-0065]


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

AGENCY: Nuclear Regulatory Commission.

ACTION: Biweekly notice.

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SUMMARY: Pursuant to the Atomic Energy Act of 1954, as amended (the 
Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this 
regular biweekly notice. The Act requires the Commission to publish 
notice of any amendments issued, or proposed to be issued, and grants 
the Commission the authority to issue and make immediately effective 
any amendment to an operating license or combined license, as 
applicable, upon a determination by the Commission that such amendment 
involves no significant hazards consideration, notwithstanding the 
pendency before the Commission of a request for a hearing from any 
person.
    This biweekly notice includes all notices of amendments issued, or 
proposed to be issued, from February 12, 2019 to February 25, 2019. The 
last biweekly notice was published on February 26, 2019.

DATES: Comments must be filed by April 11, 2019. A request for a 
hearing must be filed by May 13, 2019. Comments received after this 
date will be considered if it is practical to do so, but the Commission 
is able to ensure consideration only for comments received before this 
date.

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-2019-0065. Address 
questions about NRC Docket IDs in Regulations.gov to Krupskaya 
Castellon; telephone: 301-287-9221; email: [email protected]. 
For technical questions, contact the individual listed in the FOR 
FURTHER INFORMATION CONTACT section of this document.
     Mail comments to: Office of Administration, Mail Stop: 
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
     For additional direction on obtaining information and 
submitting comments, see ``Obtaining Information and Submitting 
Comments'' in the SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Kay Goldstein, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 
20555-0001; telephone: 301-415-1506, email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2019-0065, facility name, unit 
number(s), plant docket number, application date, and subject when 
contacting the NRC about the availability of information for this 
action. You may obtain publicly-available information related to this 
action by any of the following methods:
     Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0065.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to [email protected]. The ADAMS accession number for each 
document referenced (if it is available in ADAMS) is provided the first 
time that it is mentioned in this document.

[[Page 8907]]

     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2019-0065, facility name, unit 
number(s), plant docket number, application date, and subject in your 
comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. Background

    Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as 
amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is 
publishing this regular biweekly notice. The Act requires the 
Commission to publish notice of any amendments issued, or proposed to 
be issued, and grants the Commission the authority to issue and make 
immediately effective any amendment to an operating license or combined 
license, as applicable, upon a determination by the Commission that 
such amendment involves no significant hazards consideration, 
notwithstanding the pendency before the Commission of a request for a 
hearing from any person.

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

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

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

    Within 60 days after the date of publication of this notice, any 
persons (petitioner) whose interest may be affected by this action may 
file a request for a hearing and petition for leave to intervene 
(petition) with respect to the action. Petitions shall be filed in 
accordance with the Commission's ``Agency Rules of Practice and 
Procedure'' in 10 CFR part 2. Interested persons should consult a 
current copy of 10 CFR 2.309. The NRC's regulations are accessible 
electronically from the NRC Library on the NRC's website at 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

[[Page 8908]]

by satisfying the three factors in 10 CFR 2.309(c)(1)(i) through (iii). 
The petition must be filed in accordance with the filing instructions 
in the ``Electronic Submissions (E-Filing)'' section of this document.
    If a hearing is requested, and the Commission has not made a final 
determination on the issue of no significant hazards consideration, the 
Commission will make a final determination on the issue of no 
significant hazards consideration. The final determination will serve 
to establish when the hearing is held. If the final determination is 
that the amendment request involves no significant hazards 
consideration, the Commission may issue the amendment and make it 
immediately effective, notwithstanding the request for a hearing. Any 
hearing would take place after issuance of the amendment. If the final 
determination is that the amendment request involves a significant 
hazards consideration, then any hearing held would take place before 
the issuance of the amendment unless the Commission finds an imminent 
danger to the health or safety of the public, in which case it will 
issue an appropriate order or rule under 10 CFR part 2.
    A State, local governmental body, Federally-recognized Indian 
Tribe, or agency thereof, may submit a petition to the Commission to 
participate as a party under 10 CFR 2.309(h)(1). The petition should 
state the nature and extent of the petitioner's interest in the 
proceeding. The petition should be submitted to the Commission no later 
than 60 days from the date of publication of this notice. The petition 
must be filed in accordance with the filing instructions in the 
``Electronic Submissions (E-Filing)'' section of this document, and 
should meet the requirements for petitions set forth in this section, 
except that under 10 CFR 2.309(h)(2) a State, local governmental body, 
or Federally-recognized Indian Tribe, or agency thereof does not need 
to address the standing requirements in 10 CFR 2.309(d) if the facility 
is located within its boundaries. Alternatively, a State, local 
governmental body, Federally-recognized Indian Tribe, or agency thereof 
may participate as a non-party under 10 CFR 2.315(c).
    If a hearing is granted, any person who is not a party to the 
proceeding and is not affiliated with or represented by a party may, at 
the discretion of the presiding officer, be permitted to make a limited 
appearance pursuant to the provisions of 10 CFR 2.315(a). A person 
making a limited appearance may make an oral or written statement of 
his or her position on the issues but may not otherwise participate in 
the proceeding. A limited appearance may be made at any session of the 
hearing or at any prehearing conference, subject to the limits and 
conditions as may be imposed by the presiding officer. Details 
regarding the opportunity to make a limited appearance will be provided 
by the presiding officer if such sessions are scheduled.

B. Electronic Submissions (E-Filing)

    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing and petition for leave to intervene (petition), any 
motion or other document filed in the proceeding prior to the 
submission of a request for hearing or petition to intervene, and 
documents filed by interested governmental entities that request to 
participate under 10 CFR 2.315(c), must be filed in accordance with the 
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR 
46562; August 3, 2012). The E-Filing process requires participants to 
submit and serve all adjudicatory documents over the internet, or in 
some cases to mail copies on electronic storage media. Detailed 
guidance on making electronic submissions may be found in the Guidance 
for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit 
paper copies of their filings unless they seek an exemption in 
accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 10 
days prior to the filing deadline, the participant should contact the 
Office of the Secretary by email at [email protected], or by 
telephone at 301-415-1677, to (1) request a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign submissions and access the E-Filing 
system for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a petition or 
other adjudicatory document (even in instances in which the 
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the 
Secretary will establish an electronic docket for the hearing in this 
proceeding if the Secretary has not already established an electronic 
docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a 
digital ID certificate and a docket has been created, the participant 
can then submit adjudicatory documents. Submissions must be in Portable 
Document Format (PDF). Additional guidance on PDF submissions is 
available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the 
time the document is submitted through the NRC's E-Filing system. To be 
timely, an electronic filing must be submitted to the E-Filing system 
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of 
a transmission, the E-Filing system time-stamps the document and sends 
the submitter an email notice confirming receipt of the document. The 
E-Filing system also distributes an email notice that provides access 
to the document to the NRC's Office of the General Counsel and any 
others who have advised the Office of the Secretary that they wish to 
participate in the proceeding, so that the filer need not serve the 
document on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before adjudicatory documents are 
filed so that they can obtain access to the documents via the E-Filing 
system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic 
Filing Help Desk through the ``Contact Us'' link located on the NRC's 
public website at http://www.nrc.gov/site-help/e-submittals.html, by 
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m. 
and 6 p.m., Eastern Time, Monday through Friday, excluding government 
holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
stating why there is good cause for not filing electronically and 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, 11555 
Rockville Pike, Rockville, Maryland 20852, Attention:

[[Page 8909]]

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

    Date of amendment request: December 19, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18353B049.
    Description of amendment request: The amendment would revise the 
ANO-2 Technical Specifications by establishing Actions and Allowable 
Outage Times applicable to conditions where the ANO-2 containment 
building sump is inoperable. The proposed changes are intended to 
support the licensee's resolution of Generic Safety Issue (GSI)-191, 
``Assessment of Debris Accumulation on PWR [Pressurized-Water Reactor] 
Sump Performance.''
    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 change adds a new specification to the TS for the 
containment sump. An existing SR [surveillance requirement] on the 
containment sump is moved to the new specification. The new 
specification retains the existing requirements on the containment 
sump and the actions to be taken when the containment sump is 
inoperable with the exception of adding new actions to be taken when 
the containment sump is inoperable due to containment accident 
generated and transported debris exceeding the analyzed limits. The 
new action provides time to evaluate and correct the condition 
instead of requiring an immediate plant shutdown.
    The containment sump is not an initiator of any accident 
previously evaluated. The containment sump is a passive component 
and the proposed change does not increase the likelihood of the 
malfunction. As a result, the probability of an accident is 
unaffected by the proposed change.
    The containment sump is used to mitigate accidents previously 
evaluated by providing a borated water source for the Emergency Core 
Cooling System and Containment Spray System. The design of the 
containment sump and the capability of the containment sump assumed 
in the accident analysis are not changed. The proposed action 
requires implementation of mitigating actions while the containment 
sump is inoperable and more frequent monitoring of reactor coolant 
leakage to detect any increased potential for an accident that would 
require the containment sump. The consequences of an accident during 
the proposed action are no different than the current consequences 
of an accident if the containment sump is inoperable.
    Therefore, 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.
    The proposed change adds a new specification to the TS for the 
containment sump. An existing SR on the containment sump is moved to 
the new specification. The new specification retains the existing 
requirements on the containment sump and the actions to be taken 
when the containment sump is inoperable with the exception of adding 
new actions to be taken when the containment sump is inoperable due 
to containment accident generated and transported debris exceeding 
the analyzed limits. The new action provides time to evaluate and 
correct the condition instead of requiring an immediate plant 
shutdown.
    The proposed change does not alter the design or design function 
of the containment sump or the plant. No new systems are installed 
or removed as part of the proposed change. The containment sump is a 
passive component and cannot initiate a malfunction or accident. No 
new credible accident is created that is not encompassed by the 
existing accident analyses that assume the function of the 
containment sump.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from an accident previously 
evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed change adds a new specification to the TS for the 
containment sump. An existing SR on the containment sump is moved to 
the new specification. The new specification retains the existing 
requirements on the containment sump and the actions to be taken 
when the containment sump is inoperable with the exception of adding 
new actions to be taken when the containment sump is inoperable due 
to containment accident generated and transported debris exceeding 
the analyzed limits. The new action provides time to evaluate and 
correct the condition instead of requiring an immediate plant 
shutdown.
    The proposed change does not affect the controlling values of 
parameters used to avoid exceeding regulatory or licensing limits. 
No Safety Limits are affected by the proposed change. The proposed 
change does not affect any assumptions in the accident analyses that 
demonstrate compliance with regulatory and licensing requirements.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Anna Vinson Jones, Senior Counsel, Entergy 
Services, Inc., 101 Constitution Avenue NW, Suite 200 East, L-ENT-WDC, 
Washington, DC 20001.
    NRC Branch Chief: Robert J. Pascarelli.

[[Page 8910]]

Entergy Operations, Inc., System Energy Resources, Inc., Cooperative 
Energy, A Mississippi Electric Cooperative, and Entergy Mississippi, 
LLC, Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne 
County, Mississippi

    Date of amendment request: January 23, 2019. A publicly-available 
version is in ADAMS under Accession No. ML19023A555.
    Description of amendment request: The proposed amendment revises 
Technical Specification (TS) Table 3.3.1.1-1, ``Reactor Protection 
System Instrumentation,'' Function 9, ``Turbine Stop Valve Closure, 
Trip Oil Pressure--Low,'' and Function 10, ``Turbine Control Valve Fast 
Closure, Trip Oil Pressure--Low,'' and TS 3.3.4.1, ``End of Cycle 
Recirculation Pump Trip (EOC-RPT) Instrumentation,'' Surveillance 
Requirement (SR) 3.3.4.1.2 and SR 3.3.4.1.3. The proposed change 
revises the Allowable Value (AV) for the Turbine Stop Valve Closure 
Trip Oil Pressure Function and Turbine Control Valve Fast Closure Trip 
Oil Pressure Function. Additionally, the proposed amendment adds new 
Notes to assess channel performance during testing that verifies 
instrument channel setting values established by the Entergy setpoint 
methodology.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change to the TS is due to the replacement of the 
pressure transmitters that sense Electrohydraulic Control (EHC) 
System pressure and provide signals to the Reactor Protection System 
(RPS). The turbine control valve fast closure signal is monitored by 
the turbine control fluid pressure transmitters and trip units which 
sense control fluid pressure decay which is indicative of fast 
control valve closure. The turbine stop valve closure signal 
originates from pressure transmitters and trip units which sense 
hydraulic trip fluid pressure decay which is indicative of stop 
valve motion away from fully open.
    A change in the turbine stop valve closure trip oil pressure and 
turbine control valve fast closure trip oil pressure TS AVs does not 
introduce any mechanisms that would increase the probability of an 
accident previously analyzed. The reactor trip on turbine stop valve 
closure or turbine control valve fast closure is initiated by the 
same protective signals. There is no change in form or function of 
this signal and the probability or consequences of previously 
analyzed accidents are not impacted.
    The proposed change also adds test requirements to the turbine 
stop valve closure trip oil pressure and turbine control valve fast 
closure trip oil pressure instrument functions related to those 
variables to ensure that instruments will function as required to 
initiate protective systems or actuate mitigating systems at the 
point assumed in the applicable setpoint calculation. Surveillance 
tests are not an initiator to any accident previously evaluated. As 
a result, the probability of any accident previously evaluated is 
not significantly increased. The systems and components required by 
these functions for which surveillance tests are added are still 
required to be operable, meet the acceptance criteria for the 
surveillance requirements, and be capable of performing any 
mitigation function.
    The capacity and the characteristics of both the original and 
replacement equipment meet the original plant design criteria. The 
proposed TS changes will not prevent the capability of structures, 
systems, and components (SSCs) to perform their intended functions 
for mitigating the consequences of an accident and meeting 
applicable acceptance limits.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed change involves a physical alteration of the plant, 
i.e., a change in instrument setpoint. The proposed change reflects 
the higher pressure that will be sensed after the replacement of the 
pressure transmitters with changing of the EHC System from a low 
pressure system to a high pressure system. Failure of the new 
pressure transmitters would not result in a different outcome than 
is considered in the current design basis. The new hardware (e.g., 
components, equipment, structure, etc.) serves (provides) the same 
purpose (e.g., function, integrity, etc.) as the hardware it 
replaces. Further, the change does not alter assumptions made in the 
safety analysis but ensures that the instruments perform as assumed 
in the accident analysis.
    Thus, the proposed amendment does not create the possibility of 
a new or different kind of accident from an accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The original pressure transmitter configuration and the new 
pressure transmitter configuration both generate the same reactor 
trip signal. The difference is that the initiation of the trip will 
now be adjusted to a system of higher pressure. This system function 
of sensing and transmitting a reactor trip signal on turbine stop 
valve closure or turbine control valve fast closure remains the 
same. Also, the proposed change adds test requirements that will 
assure that TS instrumentation AVs: (1) Will be limiting settings 
for assessing instrument channel operability and; (2) will be 
conservatively determined so that evaluation of instrument 
performance history and the as-left tolerance requirements of the 
calibration procedures will not have an adverse effect on equipment 
operability. The testing methods and acceptance criteria for 
systems, structures, and components, specified in applicable codes 
and standards, or alternatives approved for use by the NRC, will 
continue to be met as described in the plant licensing basis 
including the Updated Final Safety Analysis Report. The safety 
function of the setpoint is not altered as a result of the setpoint 
change and uncertainties are adequately accounted for.
    There will be no adverse effect on margins of safety since equal 
or more stringent design and surveillance requirements will be 
applied to the new component (e.g., equipment, system, etc.).
    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: Anna Vinson Jones, Senior Counsel/Legal 
Department, Entergy Services, Inc., 101 Constitution Avenue NW, Suite 
200 East, Washington, DC 20001.
    NRC Branch Chief: Robert J. Pascarelli.

FirstEnergy Nuclear Operating Company, et al., Docket No. 50-346, 
Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), Ottawa County, 
Ohio

    Date of amendment request: February 5, 2019. A publicly-available 
version is in ADAMS under Accession No. ML19036A524.
    Description of amendment request: The proposed amendment would 
revise the emergency plan for DBNPS following the permanent cessation 
of power operations to reflect the post-shutdown and permanently 
defueled condition. The proposed changes include revision of the 
emergency response organization (ERO) staffing and editorial changes.
    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.

[[Page 8911]]

    The proposed changes to the DBNPS 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 does it alter design 
assumptions. The proposed changes do not prevent the ability of the 
on-shift staff and augmented ERO to perform their intended functions 
to mitigate the consequences of any accident or event that will be 
credible in the permanently shutdown and defueled condition. The 
proposed changes only remove positions that will no longer be 
credited in the DBNPS Emergency Plan.
    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 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 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 (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 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 DBNPS Emergency Plan and do not impact operation 
of the plant or its response to transients or accidents. The change 
does 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. The revised DBNPS Emergency Plan will continue to provide 
the necessary response staff with the proposed changes.
    Therefore, the proposed amendment does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Rick Giannantonio, General Counsel, 
FirstEnergy Corporation, Mail Stop A-GO-15, 76 South Main Street, 
Akron, OH 44308.
    NRC Branch Chief: David J. Wrona.

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

    Date of amendment request: December 19, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18353B056.
    Description of amendment request: The amendments would revise the 
Conditions, Required Actions, and Completion Times in the Technical 
Specifications (TSs) for the Condition where one steam supply to the 
turbine driven Auxiliary Feedwater (AFW) pump is inoperable concurrent 
with an inoperable motor driven AFW train. In addition, the amendments 
would change the TSs to establish specific Actions: (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 amendments 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 Pump Inoperable.'' The availability of the TSTF was 
announced in the Federal Register on July 17, 2007 as part of the 
consolidated line item improvement 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 
consideration, which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of any accident previously 
evaluated?
    Response: No
    The Auxiliary/Emergency Feedwater (AFW/EFW) System is not an 
initiator of any design basis accident or event, and therefore the 
proposed changes do not increase the probability of any accident 
previously evaluated. The proposed changes to address the condition 
of one or two motor driven AFW/EFW trains inoperable and the turbine 
driven AFW/EFW train inoperable due to one steam supply inoperable 
do not change the response of the plant to any accidents.
    The proposed changes do 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 changes do not adversely 
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. The 
proposed changes do not affect the source term, containment 
isolation, or radiological release assumptions used in evaluating 
the radiological consequences of any accident previously evaluated. 
Further, the proposed changes do not increase the types and amounts 
of radioactive effluent that may be released offsite, nor 
significantly increase individual or cumulative occupational/public 
radiation exposures.
    Therefore, the changes do not involve a significant increase in 
the probability or consequences of any 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 do not result in a change in the manner in 
which the AFW/EFW System provides plant protection. The AFW/EFW 
System will continue to supply water to the steam generators to 
remove decay heat and other residual heat by delivering at least the 
minimum required flow rate to the steam generators. There are no 
design changes associated with the proposed changes. The changes to 
the Conditions and Required Actions do not change any existing 
accident scenarios, nor create any new or different accident 
scenarios. The changes do not involve a physical alteration of the 
plant (i.e., no new or different type of equipment will be 
installed) or a change in the methods governing normal plant 
operation. In addition, the changes do not impose any new or 
different requirements or eliminate any existing requirements.
    The changes do not alter assumptions made in the safety 
analysis. The proposed changes are consistent with the safety 
analysis assumptions and current plant operating practice.
    Therefore, the 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 do not alter the manner in which safety 
limits, limiting safety system settings or limiting conditions for 
operation are determined.
    The safety analysis acceptance criteria are not impacted by 
these changes. The proposed changes will not result in plant 
operation in a configuration outside the design basis.
    Therefore, it is concluded that the proposed change does not 
involve a significant reduction in a margin of safety.


[[Page 8912]]


    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: Millicent Ronnlund, Vice President and 
General Counsel, Southern Nuclear Operating Co., Inc., P.O. Box 1295, 
Birmingham, AL 35201-1295.
    NRC Branch Chief: Michael T. Markley.

IV. 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.

V. 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.

Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric 
Station, Unit 3 (Waterford 3), St. Charles Parish, Louisiana

    Date of amendment request: March 8, 2018, as supplemented by letter 
dated October 18, 2018.
    Brief description of amendment: The amendment updated Section 
15.4.3.1 of the Updated Final Safety Analysis Report for Waterford 3, 
which describes the dose consequence of the worst undetectable single 
fuel assembly misload. The updated analysis would reflect the use of 
Next Generation Fuel and integrated fuel burnable absorbers.
    Date of issuance: February 13, 2019.
    Effective date: As of the date of issuance and shall be implemented 
before the Waterford 3 restart following Refueling Outage 22.
    Amendment No.: 253. A publicly-available version is in ADAMS under 
Accession No. ML19022A337; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-38: The amendment 
revised the Updated Final Safety Analysis Report.
    Date of initial notice in Federal Register: June 19, 2018 (83 FR 
28459). The supplement dated October 18, 2018, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the NRC 
staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated February 13, 2019.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: February 7, 2018.
    Brief description of amendment: LSCS Surveillance Requirement (SR) 
3.6.1.3.8 associated with Technical Specifications (TS) 3.6 1.3, 
``Primary Containment Isolation Valves (PCIVs),'' currently requires 
testing of each excess flow check valve (EFCV) during each refueling 
outage. The amendments implemented Technical Specification Task Force 
(TSTF)-334, Revision 2, ``Relaxed Surveillance Frequency for Excess 
Flow Check Valve Testing,'' by revising the number of EFCVs required to 
be tested by SR 3.6.1.3.8 from ``each'' to a ``representative sample.'' 
The representative sample is approximately 20 percent of the reactor 
instrumentation line EFCVs such that each EFCV will be tested at least 
once every 10 years (nominal).
    Date of issuance: February 14, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 45 days of issuance.
    Amendment No.: Unit 1-235; Unit 2-221. A publicly-available version 
is in ADAMS under Accession No. ML19025A288; documents related to these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Renewed Facility Operating License Nos. NPF-11 and NPF-18: The 
amendments revised the Renewed Facility Operating Licenses and 
Technical Specifications.
    Date of initial notice in Federal Register: April 10, 2018 (83 FR 
15415).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated February 14, 2019.
    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: March 7, 2018, as supplemented by letter 
dated October 26, 2018.
    Brief description of amendment: The amendment revised Technical 
Specification 5.5.12 to replace the reference to Regulatory Guide 
1.163, ``Performance-Based Containment Leak-Test Program,'' with a 
reference to

[[Page 8913]]

Nuclear Energy Institute (NEI) 94-01, Revision 3-A, ``Industry 
Guideline for Implementing Performance-Based Option of 10 CFR part 50, 
Appendix J,'' and the conditions and limitations specified in NEI 94-
01, Revision 2-A, of the same name, and deleted two of the four listed 
exceptions to program guidelines in TS 5.5.12.
    Date of issuance: February 25, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment No.: 185. A publicly-available version is in ADAMS under 
Accession No. ML19022A324; 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 Technical Specifications.
    Date of initial notice in Federal Register: June 19, 2018 (83 FR 
28460). The supplemental letter dated October 26, 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 25, 2019.
    No significant hazards consideration comments received: No.

Nebraska Public Power District, Docket No. 50-298, Cooper Nuclear 
Station (CNS), Nemaha County, Nebraska

    Date of amendment request: June 11, 2018.
    Brief description of amendment: The amendment revised CNS Technical 
Specification (TS) 3.8.3, ``Diesel Fuel Oil, Lube Oil, and Starting 
Air,'' by removing the current stored diesel fuel oil volume and lube 
oil inventory numerical requirements and replacing them with duration-
based diesel operating time requirements. The changes are consistent 
with the Technical Specifications Task Force (TSTF) Traveler TSTF-501, 
Revision 1, ``Relocate Stored Fuel Oil and Lube Oil Volume Values to 
Licensee Control.'' The amendment also revised a surveillance 
requirement associated with TS 3.8.1, ``AC [Alternating Current] 
Sources--Operating,'' by replacing the day tank numerical volume 
requirement with a duration-based diesel operating time requirement.
    Date of issuance: February 21, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment No.: 262. A publicly-available version is in ADAMS under 
Accession No. ML18348B103; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-46: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: August 28, 2018 (83 FR 
43905).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated February 21, 2019.
    No significant hazards consideration comments received: No.

VI. 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 amendments. The Commission has 
determined for each of these amendments 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 amendments have 
been issued and made effective 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 51.12(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

[[Page 8914]]

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 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

[[Page 8915]]

unless they seek an exemption in accordance with the procedures 
described below.
    To comply with the procedural requirements of E-Filing, at least 10 
days prior to the filing deadline, the participant should contact the 
Office of the Secretary by email at [email protected], or by 
telephone at 301-415-1677, to (1) request a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign submissions and access the E-Filing 
system for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a petition or 
other adjudicatory document (even in instances in which the 
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the 
Secretary will establish an electronic docket for the hearing in this 
proceeding if the Secretary has not already established an electronic 
docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a 
digital ID certificate and a docket has been created, the participant 
can then submit adjudicatory documents. Submissions must be in Portable 
Document Format (PDF). Additional guidance on PDF submissions is 
available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the 
time the document is submitted through the NRC's E-Filing system. To be 
timely, an electronic filing must be submitted to the E-Filing system 
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of 
a transmission, the E-Filing system time-stamps the document and sends 
the submitter an email notice confirming receipt of the document. The 
E-Filing system also distributes an email notice that provides access 
to the document to the NRC's Office of the General Counsel and any 
others who have advised the Office of the Secretary that they wish to 
participate in the proceeding, so that the filer need not serve the 
document on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before adjudicatory documents are 
filed so that they can obtain access to the documents via the E-Filing 
system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic 
Filing Help Desk through the ``Contact Us'' link located on the NRC's 
public website at http://www.nrc.gov/site-help/e-submittals.html, by 
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m. 
and 6 p.m., Eastern Time, Monday through Friday, excluding government 
holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
stating why there is good cause for not filing electronically and 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, 11555 
Rockville Pike, 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 
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Northern States Power Company--Minnesota, Docket No. 50-306, Prairie 
Island Nuclear Generating Plant, Unit 2, Goodhue County, Minnesota

    Date of amendment request: January 29, 2019.
    Description of amendment: The amendment revised Technical 
Specification 3.8.1, Condition E, to allow a one-time extension to the 
completion time for two diesel generators out of service. This notice 
supplements the notice published February 26, 2019 (84 FR 6182).
    Date of issuance: January 29, 2019.
    Effective date: January 29, 2019.
    Amendment No: 213. A publicly-available version is in ADAMS under 
Accession No. ML19029A094; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-60: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Public comments requested as to proposed no significant hazards 
consideration (NSHC): No.
    The Commission's related evaluation of the amendment, finding of 
emergency circumstances, state consultation, and final NSHC 
determination are contained in a Safety Evaluation dated January 29, 
2019.
    Attorney for licensee: Peter M. Glass, Assistant General Counsel, 
Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401.
    NRC Branch Chief: David J. Wrona.

Southern Nuclear Operating Company, Inc., Georgia Power Company, 
Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, 
City of Dalton, Georgia, Docket Nos. 50-321 and 50-366, Edwin I. Hatch 
Nuclear Plant, Unit Nos. 1 and 2, Appling County, Georgia

    Date of amendment request: February 19, 2019, as supplemented by 
letter dated February 20, 2019.
    Brief description of amendments: The amendments revise the Unit No. 
1 and Unit No. 2 Technical Specifications (TS) requirements of TS 
3.8.1, ``AC Sources--Operating,'' to change

[[Page 8916]]

Surveillance Requirement 3.8.1.8 to increase the voltage limit for the 
emergency diesel generator full load rejection test for the Unit No. 2 
diesel generators and the swing diesel generator.
    Date of issuance: February 22, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment Nos.: Unit 1-294, Unit 2-239. A publicly-available 
version is in ADAMS under Accession No. ML19053A093; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-57 and NPF-5: 
Amendments revised the Renewed Facility Operating Licenses and 
Technical Specifications.
    Public comments requested as to proposed no significant hazards 
consideration (NSHC): No.
    The Commission's related evaluation of the amendments, finding of 
emergency circumstances, state consultation, and final NSHC 
determination are contained in a Safety Evaluation dated February 22, 
2019.
    Attorney for licensee: Millicent Ronnlund, Vice President and 
General Counsel, Southern Nuclear Operating Co., Inc., P.O. Box 1295, 
Birmingham, AL 35201-1295.
    NRC Branch Chief: Michael T. Markley.

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

    For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2019-03911 Filed 3-11-19; 8:45 am]
 BILLING CODE 7590-01-P