[Federal Register Volume 83, Number 186 (Tuesday, September 25, 2018)]
[Notices]
[Pages 48463-48470]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-20333]
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NUCLEAR REGULATORY COMMISSION
[NRC-2018-0208]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice.
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SUMMARY: Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954,
as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is
publishing this regular biweekly notice. The Act requires the
Commission to publish notice of any amendments issued, or proposed to
be issued, and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license or combined
license, as applicable, upon a determination by the Commission that
such amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
[[Page 48464]]
This biweekly notice includes all notices of amendments issued, or
proposed to be issued, from August 28, 2018 to September 10, 2018. The
last biweekly notice was published on September 11, 2018.
DATES: Comments must be filed by October 25, 2018. A request for a
hearing must be filed by November 26, 2018.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0208. Address
questions about Docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this document.
Mail comments to: May Ma, Office of Administration, Mail
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: 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-2018-0208 facility name, unit
number(s), plant docket number, application date, and subject when
contacting the NRC about the availability of information for this
action. You may obtain publicly-available information related to this
action by any of the following methods:
Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0208.
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.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2018-0208, facility name, unit
number(s), plant docket number, application date, and subject in your
comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination.
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated, or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment
period such that failure to act in a timely way would result, for
example in derating or shutdown of the facility. If the Commission
takes action prior to the expiration of either the comment period or
the notice period, it will publish in the Federal Register a notice of
issuance. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed, 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
[[Page 48465]]
telephone number of the petitioner; (2) the nature of the petitioner's
right under the Act to be made a party to the proceeding; (3) the
nature and extent of the petitioner's property, financial, or other
interest in the proceeding; and (4) the possible effect of any decision
or order which may be entered in the proceeding on the petitioner's
interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the petitioner to relief. A petitioner who
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that party's admitted
contentions, including the opportunity to present evidence, consistent
with the NRC's regulations, policies, and procedures.
Petitions must be filed no later than 60 days from the date of
publication of this notice. Petitions and motions for leave to file new
or amended contentions that are filed after the deadline will not be
entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the three factors in 10
CFR 2.309(c)(1)(i) through (iii). The petition must be filed in
accordance with the filing instructions in the ``Electronic Submissions
(E-Filing)'' section of this document.
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to establish when the hearing is held. If the final determination is
that the amendment request involves no significant hazards
consideration, the Commission may issue the amendment and make it
immediately effective, notwithstanding the request for a hearing. Any
hearing would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of the amendment unless the Commission finds an imminent
danger to the health or safety of the public, in which case it will
issue an appropriate order or rule under 10 CFR part 2.
A State, local governmental body, Federally-recognized Indian
Tribe, or agency thereof, may submit a petition to the Commission to
participate as a party under 10 CFR 2.309(h)(1). The petition should
state the nature and extent of the petitioner's interest in the
proceeding. The petition should be submitted to the Commission no later
than 60 days from the date of publication of this notice. The petition
must be filed in accordance with the filing instructions in the
``Electronic Submissions (E-Filing)'' section of this document, and
should meet the requirements for petitions set forth in this section,
except that under 10 CFR 2.309(h)(2) a State, local governmental body,
or Federally-recognized Indian Tribe, or agency thereof does not need
to address the standing requirements in 10 CFR 2.309(d) if the facility
is located within its boundaries. Alternatively, a State, local
governmental body, Federally-recognized Indian Tribe, or agency thereof
may participate as a non-party under 10 CFR 2.315(c).
If a hearing is granted, any person who is not a party to the
proceeding and is not affiliated with or represented by a party may, at
the discretion of the presiding officer, be permitted to make a limited
appearance pursuant to the provisions of 10 CFR 2.315(a). A person
making a limited appearance may make an oral or written statement of
his or her position on the issues but may not otherwise participate in
the proceeding. A limited appearance may be made at any session of the
hearing or at any prehearing conference, subject to the limits and
conditions as may be imposed by the presiding officer. Details
regarding the opportunity to make a limited appearance will be provided
by the presiding officer if such sessions are scheduled.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing and petition for leave to intervene (petition), any
motion or other document filed in the proceeding prior to the
submission of a request for hearing or petition to intervene, and
documents filed by interested governmental entities that request to
participate under 10 CFR 2.315(c), must be filed in accordance with the
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR
46562; August 3, 2012). The E-Filing process requires participants to
submit and serve all adjudicatory documents over the internet, or in
some cases to mail copies on electronic storage media. Detailed
guidance on making electronic submissions may be found in the Guidance
for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit
paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to (1) request a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign submissions and access the E-Filing
system for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a petition or
other adjudicatory document (even in instances in which the
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant 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
[[Page 48466]]
the document is submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
document on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before adjudicatory documents are
filed so that they can obtain access to the documents via the E-Filing
system.
A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic
Filing Help Desk through the ``Contact Us'' link located on the NRC's
public website at http://www.nrc.gov/site-help/e-submittals.html, by
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m.
and 6 p.m., Eastern Time, Monday through Friday, excluding government
holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
stating why there is good cause for not filing electronically and
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and
Adjudications Staff. Participants filing adjudicatory documents in this
manner are responsible for serving the document on all other
participants. Filing is considered complete by first-class mail as of
the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service. A presiding officer, having granted an
exemption request from using E-Filing, may require a participant or
party to use E-Filing if the presiding officer subsequently determines
that the reason for granting the exemption from use of E-Filing no
longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the
Commission or the presiding officer. If you do not have an NRC-issued
digital ID certificate as described above, click cancel when the link
requests certificates and you will be automatically directed to the
NRC's electronic hearing dockets where you will be able to access any
publicly available documents in a particular hearing docket.
Participants are requested not to include personal privacy information,
such as social security numbers, home addresses, or personal phone
numbers in their filings, unless an NRC regulation or other law
requires submission of such information. For example, in some
instances, individuals provide home addresses in order to demonstrate
proximity to a facility or site. With respect to copyrighted works,
except for limited excerpts that serve the purpose of the adjudicatory
filings and would constitute a Fair Use application, participants are
requested not to include copyrighted materials in their submission.
For further details with respect to these license amendment
applications, see the application for amendment which is available for
public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing information related to this document, see the
``Obtaining Information and Submitting Comments'' section of this
document.
Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50-
364, Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County,
Alabama
Date of amendment request: July 27, 2018. A publicly-available
version is in ADAMS under Accession No. ML18208A619.
Description of amendment request: The proposed amendment would
modify Technical Specification requirements to permit use of Risk
Informed Completion Times in accordance with NEI 06-09, Revision 0-A,
``Risk-Informed Technical Specifications Initiative 4b, Risk-Managed
Technical Specifications (RMTS) Guidelines.''
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 [change] involve a significant
increase in the probability or consequences of an accident
previously evaluated?
Response: No.
The proposed change permits the extension of completion times
provided risk is assessed and managed within the Risk Informed
Completion Time Program. The proposed change does not involve a
significant increase in the probability of an accident previously
evaluated because the changes involve no change to the plant or its
mode of operation. The proposed change does not increase the
consequences of an accident because the design-basis mitigation
function of the affected systems is not changed and the consequences
of an accident during the extended completion time are no different
from those during the existing COMPLETION TIME.
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 TS revision does not change the design,
configuration, or method of plant operation. The proposed change
does not involve a physical alteration of the plant in that no new
or different kind of equipment will be installed.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change permits the extension of completion times
provided risk is assessed and managed within the Risk Informed
Completion Time Program. The proposed change implements a risk-
informed configuration management program to assure that adequate
safety margins are maintained. Application of these new
specifications and the configuration management program considers
cumulative effects of multiple systems or components being out of
service and does so more effectively than the current TS.
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: Millicent Ronnlund, Vice President and
General
[[Page 48467]]
Counsel, Southern Nuclear Operating Company, Inc., P.O. Box 1295,
Birmingham, AL 35201-1295.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia
Date of amendment request: July 19, 2018. A publicly-available
version is in ADAMS under Accession No. ML18200A415.
Description of amendment request: The amendment request proposes
changes to combined license Appendix C (and plant-specific design
control document Tier 1) to revise Inspections, Tests, Analysis, and
Acceptance Criteria (ITAAC) related to flow testing of low pressure
makeup from the cask loading pit to the reactor coolant system via the
normal residual heat removal system (RNS) and RNs pump testing at
reduced inventory.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes to the RNS ITAAC revise the acceptance
criteria for flow testing of low pressure makeup from the CLP [cask
loading pit] to the RCS [reactor coolant system] (via RNS) and
clarify the acceptance criteria for RNS pump flow testing at reduced
inventory. The proposed changes do not have any adverse effects on
the design functions of the RNS. The probabilities of accidents
evaluated in the UFSAR [Updated Safety Analysis Report] are not
affected.
The changes do not adversely impact the support, design, or
operation of mechanical and fluid systems. The changes do not impact
the support, design, or operation of any safety-related structures.
There is no change to the plant systems or response of systems to
postulated accident conditions. There is no change to the predicted
radioactive releases due to normal operation or postulated accident
conditions. The plant response to previously evaluated accidents or
external events is not adversely affected, nor do the proposed
changes create any new accident precursors.
Therefore, the requested amendment does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes to the RNS ITAAC revise the acceptance
criteria for flow testing of low pressure makeup from the CLP to the
RCS (via RNS) and clarify the acceptance criteria for RNS pump flow
testing at reduced inventory. The proposed changes do not have any
adverse effects on the design function of the RNS, the structures
and systems in which the RNS is used, or any other SSC [structure
system or component] design functions or methods of operation that
result in a new failure mode, malfunction, or sequence of events
that affect safety-related or non-safety related equipment. This
activity does not allow for a new fission product release path,
result in a new fission product barrier failure mode, or create a
new sequence of events that result in significant fuel cladding
failures.
Therefore, the requested 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 to the RNS ITAAC revise the acceptance
criteria for flow testing of low pressure makeup from the CLP to the
RCS (via RNS) and clarify the acceptance criteria for RNS pump flow
testing at reduced inventory.
Because no safety analysis or design basis acceptance limit/
criterion is challenged or exceeded by these changes, no significant
margin of safety is reduced. Therefore, the proposed changes do not
involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: M. Stanford Blanton, Balch & Bingham LLP,
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
NRC Branch Chief: Jennifer Dixon-Herrity.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia
Date of amendment request: August 10, 2018. A publicly-available
version is in ADAMS under Accession No. ML18222A254.
Description of amendment request: The requested amendment proposes
changes to Combined License Appendix A, Technical Specifications, to
change Technical Specifications Limiting Condition for Operation (LCO)
3.1.8, ``Physics Tests Exception--Mode 2,'' related to Functions of LCO
3.3.1, ``Reactor Trip System (RTS) Instrumentation,'' for which the
required number of channels may be reduced from 4 channels to 3
channels, to include Function 4. Additionally, for LCO 3.8.3,
``Inverters--Operating,'' the request proposes to make an editorial
nomenclature change from ``constant voltage source transformer'' to
``voltage regulating transformer.''
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes do not involve changes to current plant
design or safety analysis assumptions. These changes provide
Technical Specifications consistency with the approved plant design
and safety analysis assumptions. The changes do not affect the
operation of any systems or equipment that initiate an analyzed
accident or alter any structures, systems, and components (SSCs)
accident initiator or initiating sequence of events. The proposed
changes do not adversely impact the ability of any SSCs provided
for, or credited in, mitigating any analyzed accident. Therefore,
the requested amendment does not involve a significant increase in
the probability or consequences of an accident previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes do not involve changes to current plant
design or safety analysis assumptions. These changes provide
Technical Specifications consistency with the approved plant design
and safety analysis assumptions. The proposed changes do not
adversely affect plant protection instrumentation systems, and do
not affect the design function, support, design, or operation of
mechanical and fluid systems. The proposed changes do not result in
a new failure mechanism or introduce any new accident precursors. No
design function described in the Updated Final Safety Analysis
Report (UFSAR) is affected by the proposed changes. Therefore, the
requested amendment does not create the possibility of a new or
different kind 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 involve changes to current plant
design or safety analysis assumptions. These changes provide
Technical Specifications consistency with the approved plant design
and safety analysis assumptions. No safety analysis or design basis
acceptance limit/criterion is involved. Therefore, the proposed
amendment does not involve a significant reduction in a margin of
safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
[[Page 48468]]
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: M. Stanford Blanton, Balch & Bingham LLP,
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
NRC Branch Chief: Jennifer Dixon-Herrity.
Southern Nuclear Operating Company, Inc., Docket Nos.: 52-025 and 52-
026, Vogtle Electric Generating Plant (VEGP) Units 3 and 4, Burke
County, Georgia
Date of amendment request: August 3, 2018. A publicly-available
version is in ADAMS under Accession No. ML18215A382.
Description of amendment request: The requested amendment requires
changes to the Updated Final Safety Analysis Report (UFSAR) in the form
of departures from the incorporated plant-specific Design Control
Document (DCD) Tier 2* and Tier 2 information and related changes to
the VEGP Units 3 and 4 Combined License (COL) and COL Appendix C (and
corresponding plant-specific DCD Tier 1) information. Specifically, the
requested amendment includes changes to credit previously completed
first plant only and first three plant only testing as described in the
licensing basis documents, including COL Condition 2.D.(2)(a) and
plant-specific Tier 1 Section 2.1.3. In particular, the proposed
changes would revise the COL to delete conditions requiring the
following tests: In-Containment Refueling Water Storage Tank (IRWST)
Heatup Test, Reactor Vessel Internals Vibration Testing, and Core
Makeup Tank (CMT) Heated Recirculation Tests. The documentation to
establish a valid prototype reactor internals in accordance with
Regulatory Guide 1.20 is also included.
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 does not affect the operation of any systems
or equipment that initiates an analyzed accident or alter any
structures, systems, or components (SSC) accident initiator or
initiating sequence of events. The proposed changes remove first
plant and first three plant only tests including the IRWST heatup
test, reactor vessel internals vibration testing, and CMT
recirculation tests based on the successful completion of the tests
at the lead AP1000 units. The change does not adversely affect any
methodology which would increase the probability or consequences of
a previously evaluated accident.
The change does not impact the support, design, or operation of
mechanical or fluid systems. There is no change to plant systems or
the response of systems to postulated accident conditions. There is
no change to predicted radioactive releases due to normal operation
or postulated accident conditions. The plant response to previously
evaluated accidents or external events is not adversely affected,
nor does the proposed change create any new accident precursors.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of a previously
evaluated accident.
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 does not affect the operation of any systems
or equipment that may 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.
The proposed change credits previously completed first plant and
first three plant only tests including the IRWST heatup test,
reactor vessel internals vibration testing, and CMT recirculation
tests based on the successful completion of the tests at the lead
AP1000 units. The proposed changes do not adversely affect any
design function of any SSC design functions or methods of operation
in a manner that results in a new failure mode, malfunction, or
sequence of events that affect safety-related or non-safety-related
equipment. This activity does not allow for a new fission product
release path, result in a new fission product barrier failure mode,
or create a new sequence of events that result in significant fuel
cladding failures.
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 change maintains existing safety margin and
provides adequate protection through continued application of the
existing requirement in the UFSAR. The proposed change satisfies the
same design functions in accordance with the same codes and
standards as stated in the UFSAR. This change does not adversely
affect any design code, function, design analysis, safety analysis
input or result, or design/safety margin. No safety analysis or
design basis acceptance limit/criterion is challenged or exceeded by
the proposed change.
Since no safety analysis or design basis acceptance limit/
criterion is challenged or exceeded by this change, no significant
margin of safety is reduced.
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: Mr. M. Stanford Blanton, Balch & Bingham
LLP, 1710 Sixth Avenue North Birmingham, AL 35203-2015.
NRC Branch Chief: Jennifer Dixon-Herrity.
III. Notice of Issuance of Amendments to Facility Operating Licenses
and Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items can be accessed as described in the
``Obtaining Information and Submitting Comments'' section of this
document.
[[Page 48469]]
Energy Northwest, Docket No. 50-397, Columbia Generating Station,
Benton County, Washington
Date of amendment request: December 12, 2017.
Brief description of amendment: The amendment revised Technical
Specification (TS) 3.6.4.1, ``Secondary Containment.'' The changes are
based on Technical Specifications Task Force (TSTF) Traveler TSTF-551,
Revision 3, ``Revise Secondary Containment Surveillance Requirements.''
Date of issuance: September 6, 2018.
Effective date: As of its date of issuance and shall be implemented
within 60 days from the date of issuance.
Amendment No.: 250. A publicly-available version is in ADAMS under
Accession No. ML18221A107; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-21: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: March 13, 2018 (83 FR
10915).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 6, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna Nuclear
Power Plant, Wayne County, New York
Date of amendment request: October 31, 2017.
Brief description of amendment: The amendment revised Technical
Specification (TS) Surveillance Requirement 3.8.4.3, ``DC [Direct
Current] Sources--MODES 1, 2, 3, and 4,'' to allow for a modified
performance discharge test.
Date of issuance: August 31, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No.: 130. A publicly-available version is in ADAMS under
Accession No. ML18214A176; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-18: Amendment revised
the Renewed Facility Operating License and TS.
Date of initial notice in Federal Register: January 2, 2018 (83 FR
168).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 31, 2018.
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: May 10, 2018.
Brief description of amendment: The amendment modified CNS
Technical Specification 2.1.1.2 by revising the values of the safety
limit minimum critical power ratio for two recirculation loop operation
and for single recirculation loop operation to reflect the results of a
cycle-specific calculation.
Date of issuance: September 6, 2018.
Effective date: As of the date of issuance and shall be implemented
prior to startup from Refuel Outage 30.
Amendment No.: 261. A publicly-available version is in ADAMS under
Accession No. ML18218A483; 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: July 2, 2018 (83 FR
30984).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 6, 2018.
No significant hazards consideration comments received: No.
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: July 10, 2017. A publicly-available
version is in ADAMS under Accession No. ML17191B163.
Brief description of amendments: The amendments revise the
Technical Specifications (TSs) by: (1) Adding a Note to the
Surveillance Requirements (SRs) of TS 3.7.7 to clarify that the SRs are
not required to be met when the Limiting Condition for Operation (LCO)
does not require the Main Turbine Bypass System to be operable; (2)
clarifying that LCO 3.2.3, ``LINEAR HEAT GENERATION RATE,'' also has
limits for an inoperable Main Turbine Bypass System that are made
applicable as specified in the Core Operating Limits Report; and (3)
deleting an outdated footnote for LCO 3.2.3.
Date of issuance: August 29, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment Nos.: Unit 1--292, Unit 2--237. A publicly-available
version is in ADAMS under Accession No. ML18222A296; 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.
Date of initial notice in Federal Register: November 21, 2017 (82
FR 55412).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated August 29, 2018.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County,
Georgia
Date of amendment request: January 31, 2018, as supplemented by
letters dated April 25, and June 21, 2018.
Description of amendment: The amendments make changes to the VEGP
Units 3 and 4 Combined Operating License (COL) in the form of departure
from the approved COL Appendix A, Technical Specifications. The
amendments make changes to COL Appendix A, Surveillance Requirement
3.8.7.6 to align the test frequency with the expected life of the
AP1000 Class 1E batteries.
Date of issuance: The amendments were issued on July 26, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment Nos.: 135 (Unit 3) and 134 (Unit 4). A publicly-available
version is in ADAMS under Accession No. ML18173A301; documents related
to this amendment are listed in the Safety Evaluation enclosed with the
amendment.
Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment
revised the Facility Combined License.
Date of initial notice in Federal Register: April 24, 2018 (83 FR
17858). The supplements dated April 25, 2018 and June 21, 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
[[Page 48470]]
original proposed no significant hazards consideration determination.
The Commission's related evaluation of the amendment is contained
in the Safety Evaluation dated July 26, 2018.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County,
Georgia
Date of amendment request: June 15, 2018 and supplemented on June
25, 2018 and July 10, 2018.
Description of amendment: The amendment revises commitments related
to the construction fitness-for-duty (FFD) program described in the
VEGP Units 3 and 4 Updated Final Safety Analysis Report. Specifically,
the change involves the creation of a new type of FFD Authorization
that allows construction workers temporary access to the construction
site pending completion of all pre-access FFD requirements. The
individuals will not be given assignments to work on safety or
security-related structures, systems, and components prior to the
completion of the FFD requirements.
Date of issuance: August 29, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment Nos.: 141 (Unit 3) and 140 (Unit 4). A publicly-available
version is in ADAMS under Accession No. ML18214A659; documents related
to this amendment are listed in the Safety Evaluation enclosed with the
amendment.
Facility Combined Licenses No. NPF-91 and NPF-92: Amendment revised
the Facility Combined Licenses.
Date of initial notice in Federal Register: June 27, 2018 (83 FR
30199). The supplements dated June 25, 2018, and July 10, 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 the Safety Evaluation dated August 29, 2018.
No significant hazards consideration comments received: No.
Tennessee Valley Authority (TVA) Docket Nos. 50-327 and 50-328,
Sequoyah Nuclear Plant (SQN), Units 1 and 2, Hamilton County, Tennessee
TVA Docket Nos. 50-390 and 50-391, Watts Bar Nuclear Plant (WBN), Units
1 and 2, Rhea County, Tennessee
Date of amendment request: August 7, 2017.
Brief description of amendments: The amendments revised technical
specifications (TSs) limiting conditions for operation and surveillance
requirements related to the reactor trip system instrumentation for all
four units.
Date of issuance: August 30, 2018.
Effective date: As of the date of issuance and shall be implemented
in 30 days.
Amendment Nos.: SQN, 343 (Unit 1) and 336 (Unit 2); and WBN, 122
(Unit 1) and 21 (Unit 2). A publicly-available version is in ADAMS
under Accession No. ML18197A307; documents related to these amendments
are listed in the Safety Evaluation (SE) enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-77, DPR-79 and Facility
Operating License Nos, NPF-90 and NPF-96: Amendments revised the
Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: November 21, 2017 (82
FR 55416).
The Commission's related evaluation of the amendments is contained
in SE dated August 30, 2018.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, on September 14, 2018.
For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Acting Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2018-20333 Filed 9-24-18; 8:45 am]
BILLING CODE 7590-01-P