Vogtle Electric Generating Plant, Units 3 and 4, 47375-47379 [2018-20324]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 83, Number 182 (Wednesday, September 19, 2018)]
[Notices]
[Pages 47375-47379]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-20324]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 052-00025 and 052-00026; NRC-2008-0252]


Vogtle Electric Generating Plant, Units 3 and 4

AGENCY: Nuclear Regulatory Commission.

ACTION: License amendment application; opportunity to comment, request 
a hearing, and petition for leave to intervene.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of an amendment and exemption to Combined Licenses (NPF-91 and 
NPF-92), issued to Southern Nuclear Operating Company, Inc. (SNC), 
Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM, 
LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, Authority of Georgia, 
and the City of Dalton, Georgia (collectively, SNC), for construction 
and operation of the Vogtle Electric Generating Plant (VEGP), Units 3 
and 4, located in Burke County, Georgia.

DATES: Comments must be filed by October 19, 2018. A request for a 
hearing must be filed by November 19, 2018.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2008-0252. Address 
questions about Docket IDs in Regulations.gov 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-A60, 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: William (Billy) Gleaves, Office of New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-5848; email: [email protected].

SUPPLEMENTARY INFORMATION: 

[[Page 47376]]

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2008-0252 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 https://www.regulations.gov and search for Docket ID NRC-2008-0252.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://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 
application for amendment is dated August 10, 2018, is available in 
ADAMS under Accession No. ML18222A599.
     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-2008-0252 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 posts all comment submissions at https://www.regulations.gov as well as entering 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 submissions into ADAMS.

II. Introduction

    The NRC is considering issuance of an amendment to facility 
Combined License Nos. NPF-91 and NPF-92, issued to SNC for operation of 
the VEGP Units 3 and 4, located in Burke County, Georgia.
    The proposed changes would revise the Combined Licenses to relocate 
the power operated relief valve (PORV) branch lines upstream of the 
main steam safety valves in Inspections, Tests, Analyses, and 
Acceptance Criteria (ITAAC) Figure 2.2.4-1 (Sheets 1 of 2) of the COL 
Appendix C. In addition to the relocation of the PORV branch lines, the 
PORV block valves would be changed from gate valves to globe valves in 
the VEGP Updated Final Safety Analysis Report (UFSAR). The requested 
amendment proposes changes to the UFSAR in the form of departures from 
the incorporated plant-specific Design Control Document (DCD) Tier 2 
information in the UFSAR and involves changes to COL Appendix C, and 
corresponding changes to plant-specific Tier 1 information. Because, 
these proposed changes require a departure from Tier 1 information in 
the Westinghouse Electric Company's AP1000 Design Control Document 
(DCD), the licensee also requested an exemption from the requirements 
of the Generic DCD Tier 1 in accordance with section 52.63(b)(1) of 
title 10 of the Code of Federal Regulations (10 CFR).
    Before any issuance of the proposed license amendment, the NRC will 
need to make the findings required by the Atomic Energy Act of 1954, as 
amended (the Act), and NRC's regulations.
    The NRC has made a proposed determination that the license 
amendment request involves no significant hazards consideration. Under 
the NRC's regulations in 10 CFR 50.92, 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. As 
required by 10 CFR 50.91(a), the licensee has provided its analysis of 
the issue of no significant hazards consideration, which is presented 
below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes do not affect the operation or reliability 
of any system, structure or component (SSC) required to maintain a 
normal power operating condition or to mitigate anticipated 
transients without safety-related systems.
    With the proposed changes, the PORV block valves are still able 
to perform the safety-related functions of containment isolation, 
steam generator isolation, and steam generator relief isolation. 
There is no change to the PORV block valves safety class or safety-
related functions.
    The relocation of the branch line in which the PORV block valves 
are installed in allows the PORV block valves to be closer to the 
containment penetration and maintain compliance with General Design 
Criterion (GDC) 57 for locating containment isolation valves as 
close to the containment as practical.
    There is no impact to Chapter 15 evaluations. Changes to the 
PORV block valve and line size do not impact the mass releases to 
the atmosphere during a Steam Generator Tube Rupture accident. The 
mass release is limited by the PORV which is more restrictive than 
the PORV block valve and line size.
    There is no impact to any assumed leakage through the PORV line. 
The existing 12-inch PORV has a design function to limit leakage 
through the PORV line. Increasing the PORV block valve to 12 inches 
will increase the leakage through the PORV block valve however it 
will be that same leakage rate as the 12-inch PORV. Therefore, the 
leakage rate through the PORV line does not increase and there is no 
impact to radiation doses.
    There is no impact to the assumptions or analysis in the 
completed safety analysis for radiation doses as a result of the 
change.
    There is no impact to the conclusions of the Pipe Rupture Hazard 
Analysis (PRHA) because the PORV line is Break Exclusion Zone (BEZ) 
piping. The proposed changes do not result in any new postulated 
break locations. Updated analyses confirm that the integrity of the 
wall adjacent to the [main control room] MCR is unaffected by a 
postulated main steam line break that causes the PORV line to impact 
the wall.
    There is no change to the valve motor operator. The current 
motor operator is sufficient to operate the new 12-inch globe valve. 
Therefore, there is no impact to the Class 1E dc and UPS System 
(IDS) battery sizing. There is no change to the valve stroke time, 
therefore there is no impact to valve open/closure times.
    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 do not affect the operation of systems or 
equipment that could initiate a new or different kind of accident, 
or alter any SSC such that a new accident initiator or initiating 
sequence of events is created. With the proposed changes, the PORV 
block valves are still able to perform the safety related functions 
of containment isolation, steam generator isolation, and steam 
generator relief isolation. There is no change to the PORV block 
valves safety class or safety-related functions.
    The relocation of the branch line in which the PORV block valves 
are installed in allows the PORV block valves to be closer to the

[[Page 47377]]

containment penetration and maintain compliance with General Design 
Criterion (GDC) 57 for locating containment isolation valves as 
close to the containment as practical.
    There is no impact to Chapter 15 evaluations. Changes to the 
PORV block valve and line size do not impact the mass releases to 
the atmosphere during a Steam Generator Tube Rupture accident. The 
mass release is limited by the PORV which is more restrictive than 
the PORV block valve and line size.
    There is no impact to any assumed leakage through the PORV line. 
The existing 12-inch PORV has a design function to limit leakage 
through the PORV line. Increasing the PORV block valve to 12 inches 
will increase the leakage through the PORV block valve however it 
will be that same leakage rate as the 12-inch PORV. Therefore, the 
leakage rate through the PORV line does not increase and there is no 
impact to radiation doses.
    There is no impact to the assumptions or analysis in the 
completed safety analysis for radiation doses as a result of the 
change.
    There is no impact to the conclusions of the Pipe Rupture Hazard 
Analysis (PRHA) because the PORV line is Break Exclusion Zone (BEZ) 
piping. The proposed changes do not result in any new postulated 
break locations. Updated analyses confirm that the integrity of the 
wall adjacent to the MCR is unaffected by a postulated main steam 
line break that causes the PORV line to impact the wall.
    There is no change to the valve motor operator. The current 
motor operator is sufficient to operate the new 12-inch globe valve. 
Therefore, there is no impact to the Class 1E dc and UPS System 
(IDS) battery sizing. There is no change to the valve stroke time, 
therefore there is no impact to valve open/closure times.
    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 changes do not affect existing safety margins. With 
the proposed changes, the PORV block valves are still able to 
perform the safety-related functions of containment isolation, steam 
generator isolation, and steam generator relief isolation. There is 
no change to the PORV block valves safety class or safety-related 
functions.
    The relocation of the branch line in which the PORV block valves 
are installed in allows the PORV block valves to be closer to the 
containment penetration and maintain compliance with General Design 
Criterion (GDC) 57 for locating containment isolation valves as 
close to the containment as practical.
    There is no impact to Chapter 15 evaluations. Changes to the 
PORV block valve and line size do not impact the mass releases to 
the atmosphere during a Steam Generator Tube Rupture accident. The 
mass release is limited by the PORV which is more restrictive than 
the PORV block valve and line size.
    There is no impact to any assumed leakage through the PORV line. 
The existing 12-inch PORV has a design function to limit leakage 
through the PORV line. Increasing the PORV block valve to 12 inches 
will increase the leakage through the PORV block valve however it 
will be that same leakage rate as the 12-inch PORV. Therefore, the 
leakage rate through the PORV line does not increase and there is no 
impact to radiation doses.
    There is no impact to the assumptions or analysis in the 
completed safety analysis for radiation doses as a result of the 
change.
    There is no impact to the conclusions of the Pipe Rupture Hazard 
Analysis (PRHA) because the PORV line is Break Exclusion Zone (BEZ) 
piping. The proposed changes do not result in any new postulated 
break locations. Updated analyses confirm that the integrity of the 
wall adjacent to the MCR is unaffected by a postulated main steam 
line break that causes the PORV line to impact the wall.
    There is no change to the valve motor operator. The current 
motor operator is sufficient to operate the new 12-inch globe valve. 
Therefore, there is no impact to the Class 1E dc and UPS System 
(IDS) battery sizing. There is no change to the valve stroke time, 
therefore there is no impact to valve open/closure times.
    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 
license amendment request involves no significant hazards 
consideration.
    The NRC is seeking public comments on this proposed determination 
that the license amendment request involves no significant hazards 
consideration. 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 notice period if the Commission concludes 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 should 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. Should the Commission take action 
prior to the expiration of either the comment period or the notice 
period, the Commission will publish a notice of issuance in the Federal 
Register. Should the Commission make 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.

III. 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 a petition 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, which is available at the NRC's PDR, located at One White Flint 
North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, 
Maryland 20852. The NRC's regulations are accessible electronically 
from the NRC Library on the NRC's website at https://www.nrc.gov/reading-rm/doc-collections/cfr/. If a petition is filed within 60 days, 
the Commission or a presiding officer designated by the Commission or 
by the Chief Administrative Judge of the Atomic Safety and Licensing 
Board Panel, will rule on the petition; and the Secretary or the Chief 
Administrative Judge of the Atomic Safety and Licensing Board Panel 
will issue a notice of a hearing or an appropriate order.
    As required by 10 CFR 2.309, a petition shall set forth with 
particularity the interest of the petitioner in the proceeding, and how 
that interest may be affected by the results of the proceeding. The 
petition should specifically explain the reasons why intervention 
should be permitted with particular reference to the following general 
requirements: (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. The petition 
must also set forth the specific contentions which the petitioner seeks 
to have litigated at 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 shall 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

[[Page 47378]]

which the petitioner intends to rely in proving the contention at the 
hearing. The petitioner must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
petitioner intends to rely to establish those facts or expert opinion 
to support its position on the issue. The petition must include 
sufficient information to show that a genuine dispute exists with the 
applicant on a material issue of law or fact. Contentions shall 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 these requirements 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, 
and have the opportunity to participate fully in the conduct of the 
hearing with respect to resolution of that person's admitted 
contentions consistent with the NRC's regulations, policies, and 
procedures.
    Petitions for leave to intervene must be filed no later than 60 
days from the date of publication of this notice. Requests for hearing, 
petitions for leave to intervene, and motions for leave to file new or 
amended contentions that are filed after the 60-day 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).
    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 decide 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 held 
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 any 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 by November 19, 2018. 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. A State, local governmental body, Federally-recognized 
Indian Tribe, or agency thereof may also have the opportunity to 
participate under 10 CFR 2.315(c).
    If a hearing is granted, any person who does not wish, or is not 
qualified, to become a party to the proceeding may, in 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 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.

IV. Electronic Submissions (E-Filing)

    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing, a petition for leave to intervene, any motion or 
other document filed in the proceeding prior to the submission of a 
request for hearing or petition to intervene (hereinafter 
``petition''), and documents filed by interested governmental entities 
participating 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. 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 request (1) a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign documents and access the E-Submittal 
server for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a petition (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 https://www.nrc.gov/site-help/e-submittals/getting-started.html. System requirements for accessing 
the E-Submittal server are available on the NRC's public website at 
https://www.nrc.gov/site-help/e-submittals/adjudicatory-sub.html. 
Participants may attempt to use other software not listed on the 
website, but should note that the NRC's E-Filing system does not 
support unlisted software, and the NRC Electronic Filing Help Desk will 
not be able to offer assistance in using unlisted software.
    Once a participant has obtained a digital ID certificate and a 
docket has been created, the participant can then submit a petition. 
Submissions should be in Portable Document Format (PDF). Additional 
guidance on PDF submissions is available on the NRC's public website at 
https://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is 
considered complete at the time the documents are 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 documents on those

[[Page 47379]]

participants separately. Therefore, applicants and other participants 
(or their counsel or representative) must apply for and receive a 
digital ID certificate before a hearing petition to intervene is filed 
so that they can obtain access to the document via the E-Filing system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC Electronic 
Filing Help Desk through the ``Contact Us'' link located on the NRC's 
public website at https://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 7 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 a document 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. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law requires submission of such information. 
However, in some instances, a request to intervene will require 
including information on local residence in order to demonstrate a 
proximity assertion of interest in the proceeding. 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 this action, see the 
application for license amendment dated August 10, 2018.
    Attorney for licensee: Mr. M. Stanford Blanton, Balch & Bingham 
LLP, 1710 Sixth Avenue North, Birmingham, AL 35203-2015.
    NRC Branch Chief: Jennifer Dixon-Herrity.

    Dated at Rockville, Maryland, this 14th day of September 2018.

    For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of Licensing, Siting, and 
Environmental Analysis, Office of New Reactors.
[FR Doc. 2018-20324 Filed 9-18-18; 8:45 am]
 BILLING CODE 7590-01-P