[Federal Register Volume 83, Number 59 (Tuesday, March 27, 2018)]
[Notices]
[Pages 13146-13156]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-05905]
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NUCLEAR REGULATORY COMMISSION
[NRC-2018-0059]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice.
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SUMMARY: Pursuant to Section 189a. (2) of the Atomic Energy Act of
1954, as amended (the Act), the U.S. Nuclear Regulatory Commission
(NRC) is
[[Page 13147]]
publishing this regular biweekly notice. The Act requires the
Commission to publish notice of any amendments issued, or proposed to
be issued, and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license or combined
license, as applicable, upon a determination by the Commission that
such amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued, from February 27, 2018, to March 12, 2018. The
last biweekly notice was published on March 13, 2018.
DATES: Comments must be filed by April 26, 2018. A request for a
hearing must be filed by May 29, 2018.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0059. Address
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: May Ma, Office of Administration, Mail
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Ikeda Betts, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001; telephone: 301-415-1959, email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2018-0059, facility name, unit
number(s), plant docket number, application date, and subject when
contacting the NRC about the availability of information for this
action. You may obtain publicly-available information related to this
action by any of the following methods:
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0059.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to [email protected]. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in this
document.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2018-0059, facility name, unit
number(s), plant docket number, application date, and subject in your
comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated, or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment
period such that failure to act in a timely way would result, for
example in derating or shutdown of the facility. If the Commission
takes action prior to the expiration of either the comment period or
the notice period, it will publish in the Federal Register a notice of
issuance. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed,
[[Page 13148]]
the Commission or a presiding officer will rule on the petition and, if
appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the petitioner to relief. A petitioner who
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that party's admitted
contentions, including the opportunity to present evidence, consistent
with the NRC's regulations, policies, and procedures.
Petitions must be filed no later than 60 days from the date of
publication of this notice. Petitions and motions for leave to file new
or amended contentions that are filed after the deadline will not be
entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the three factors in 10
CFR 2.309(c)(1)(i) through (iii). The petition must be filed in
accordance with the filing instructions in the ``Electronic Submissions
(E-Filing)'' section of this document.
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to establish when the hearing is held. If the final determination is
that the amendment request involves no significant hazards
consideration, the Commission may issue the amendment and make it
immediately effective, notwithstanding the request for a hearing. Any
hearing would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of the amendment unless the Commission finds an imminent
danger to the health or safety of the public, in which case it will
issue an appropriate order or rule under 10 CFR part 2.
A State, local governmental body, Federally-recognized Indian
Tribe, or agency thereof, may submit a petition to the Commission to
participate as a party under 10 CFR 2.309(h)(1). The petition should
state the nature and extent of the petitioner's interest in the
proceeding. The petition should be submitted to the Commission no later
than 60 days from the date of publication of this notice. The petition
must be filed in accordance with the filing instructions in the
``Electronic Submissions (E-Filing)'' section of this document, and
should meet the requirements for petitions set forth in this section,
except that under 10 CFR 2.309(h)(2) a State, local governmental body,
or Federally-recognized Indian Tribe, or agency thereof does not need
to address the standing requirements in 10 CFR 2.309(d) if the facility
is located within its boundaries. Alternatively, a State, local
governmental body, Federally-recognized Indian Tribe, or agency thereof
may participate as a non-party under 10 CFR 2.315(c).
If a hearing is granted, any person who is not a party to the
proceeding and is not affiliated with or represented by a party may, at
the discretion of the presiding officer, be permitted to make a limited
appearance pursuant to the provisions of 10 CFR 2.315(a). A person
making a limited appearance may make an oral or written statement of
his or her position on the issues but may not otherwise participate in
the proceeding. A limited appearance may be made at any session of the
hearing or at any prehearing conference, subject to the limits and
conditions as may be imposed by the presiding officer. Details
regarding the opportunity to make a limited appearance will be provided
by the presiding officer if such sessions are scheduled.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing and petition for leave to intervene (petition), any
motion or other document filed in the proceeding prior to the
submission of a request for hearing or petition to intervene, and
documents filed by interested governmental entities that request to
participate under 10 CFR 2.315(c), must be filed in accordance with the
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR
46562, August 3, 2012). The E-Filing process requires participants to
submit and serve all adjudicatory documents over the internet, or in
some cases to mail copies on electronic storage media. Detailed
guidance on making electronic submissions may be found in the Guidance
for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit
paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to (1) request a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign submissions and access the E-Filing
system for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a petition or
other adjudicatory document (even in instances in which the
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant
[[Page 13149]]
has obtained a digital ID certificate and a docket has been created,
the participant can then submit adjudicatory documents. Submissions
must be in Portable Document Format (PDF). Additional guidance on PDF
submissions is available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is
considered complete at the time the document is submitted through the
NRC's E-Filing system. To be timely, an electronic filing must be
submitted to the E-Filing system no later than 11:59 p.m. Eastern Time
on the due date. Upon receipt of a transmission, the E-Filing system
time-stamps the document and sends the submitter an email notice
confirming receipt of the document. The E-Filing system also
distributes an email notice that provides access to the document to the
NRC's Office of the General Counsel and any others who have advised the
Office of the Secretary that they wish to participate in the
proceeding, so that the filer need not serve the document on those
participants separately. Therefore, applicants and other participants
(or their counsel or representative) must apply for and receive a
digital ID certificate before adjudicatory documents are filed so that
they can obtain access to the documents via the E-Filing system.
A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic
Filing Help Desk through the ``Contact Us'' link located on the NRC's
public website at http://www.nrc.gov/site-help/e-submittals.html, by
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m.
and 6 p.m., Eastern Time, Monday through Friday, excluding government
holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
stating why there is good cause for not filing electronically and
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and
Adjudications Staff. Participants filing adjudicatory documents in this
manner are responsible for serving the document on all other
participants. Filing is considered complete by first-class mail as of
the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service. A presiding officer, having granted an
exemption request from using E-Filing, may require a participant or
party to use E-Filing if the presiding officer subsequently determines
that the reason for granting the exemption from use of E-Filing no
longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the
Commission or the presiding officer. If you do not have an NRC-issued
digital ID certificate as described above, click cancel when the link
requests certificates and you will be automatically directed to the
NRC's electronic hearing dockets where you will be able to access any
publicly available documents in a particular hearing docket.
Participants are requested not to include personal privacy information,
such as social security numbers, home addresses, or personal phone
numbers in their filings, unless an NRC regulation or other law
requires submission of such information. For example, in some
instances, individuals provide home addresses in order to demonstrate
proximity to a facility or site. With respect to copyrighted works,
except for limited excerpts that serve the purpose of the adjudicatory
filings and would constitute a Fair Use application, participants are
requested not to include copyrighted materials in their submission.
For further details with respect to these license amendment
applications, see the application for amendment which is available for
public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing information related to this document, see the
``Obtaining Information and Submitting Comments'' section of this
document.
Entergy Nuclear Operations, Inc., Docket No. 50-293, Pilgrim Nuclear
Power Station (PNPS), Plymouth County, Massachusetts
Date of amendment request: January 12, 2018. A publicly-available
version is in ADAMS under Accession No. ML18023A795.
Description of amendment request: The amendment would revise the
PNPS Site Emergency Plan (SEP) for the permanently shutdown and
defueled condition. The amendment would revise the PNPS on-shift and
Emergency Response Organization (ERO) staffing for the permanently
shutdown and defueled condition.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes to the PNPS SEP do not impact the function
of plant structures, systems, or components. The proposed changes do
not affect accident initiators or precursors, nor does it alter
design assumptions. The proposed changes do not prevent the ability
of the on-shift and augmented ERO to perform their intended
functions to mitigate the consequences of any accident or event that
will be credible in the permanently shut down and defueled
condition. The proposed changes only remove positions that will no
longer be credited in the PNPS SEP.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes reduce the number of on-shift and augmented
ERO positions commensurate with the hazards associated with a
permanently shut down and defueled facility. The proposed changes do
not involve installation of new equipment or modification of
existing equipment, so that no new equipment failure modes are
introduced. Also, the proposed changes do not result in a change to
the way that the equipment or facility is operated so that no new
accident initiators are created.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
Margin of safety is associated with confidence in the ability of
the fission product barriers (i.e., fuel cladding, reactor coolant
system pressure boundary, and containment structure) to limit the
level of radiation dose to the public. The proposed changes are
associated with the PNPS SEP and do not impact operation of the
plant or its response to transients or accidents. The changes do not
affect the Technical Specifications. The proposed changes do not
involve a change in the method of plant operation, and no accident
analyses will be affected by the proposed changes.
[[Page 13150]]
Safety analysis acceptance criteria are not affected by the
proposed changes. The revised PNPS SEP will continue to provide the
necessary response staff with the proposed changes.
Therefore, the proposed amendment does not involve a significant
reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: William B. Glew, Jr., Associate General
Counsel--Nuclear, Legal Nuclear and Environmental, Entergy Nuclear
Operations, Inc., 440 Hamilton Avenue, White Plains, NY 10601.
NRC Branch Chief: Douglas A. Broaddus.
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick
Generating Station, Units 1 and 2, Montgomery County, Pennsylvania
Date of amendment request: January 29, 2018. A publicly-available
version is in ADAMS under Accession No. ML18029A509.
Description of amendment request: The amendments would revise the
Limerick Generating Station, Units 1 and 2, Technical Specifications
(TSs). The proposed changes would lower the TS standby liquid control
system (SLCS) surveillance requirement (SR) pump flowrate value, raise
the TS SLCS SR Boron-10 enrichment value of the sodium pentaborate
added to the SLCS tank, and expand the operating range in the sodium
pentaborate solution temperature/concentration requirements figure.
These changes will provide increased testing margin and operational
flexibility.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes will lower the SLCS TS SR pump flowrate
value, raise the TS SLCS SR Boron-10 (B-10) Enrichment value of the
Sodium Pentaborate added to the SLCS tank and expand the operating
range contained in the TS Figure for Sodium Pentaborate Solution
Temperature/Concentration Requirements. These changes will provide
greater operating flexibility. The proposed changes will maintain
plant operation within the bounds of the current analysis for the
ATWS [anticipated transient without scram] events and for accident
source term dose limits in the Loss of Coolant Accident (LOCA)
analysis.
The proposed changes do not alter the physical design of any
plant structure, system, or component; therefore, the proposed
changes have no adverse effect on plant operation, or the
availability or operation of any accident mitigation equipment. The
plant response to the design basis accidents does not change.
Operation or failure of the SLCS is not assumed to be an initiator
of any analyzed event in the Updated Final Safety Analysis Report
(UFSAR) and cannot cause an accident. The changes to the SLCS TS SRs
are bounded by current analyses for the ATWS events and LOCA and
therefore the changes do not adversely affect consequences of any
accident previously evaluated.
The proposed changes conform to NRC regulatory requirements
regarding ATWS events and AST [alternative source term] dose limits.
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes will lower the TS SLCS SR pump flowrate
value, raise the TS SLCS SR B-10 Enrichment value of the Sodium
Pentaborate added to the SLCS tank and expand the operating range in
the Sodium Pentaborate Solution Temperature/Concentration
Requirements Figure. These changes will provide greater operating
flexibility. The proposed changes will maintain plant operation
within the bounds of the current analysis for the ATWS events and
for accident source term dose limits in the LOCA analysis.
The proposed changes do not alter the plant configuration (no
new or different type of equipment is being installed) or require
any new or unusual operator actions. The proposed changes do not
alter the safety limits or safety analysis assumptions associated
with the operation of the plant. The proposed changes do not
introduce any new failure modes that could result in a new accident.
The proposed changes do not reduce or adversely affect the
capabilities of any plant structure, system, or component in the
performance of their safety function. Also, the response of the
plant and the operators following the design basis accidents is
unaffected by the proposed changes.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed changes will lower the TS SLCS SR pump flowrate
value, raise the TS SLCS SR B-10 Enrichment value of the Sodium
Pentaborate added to the SLCS tank and expand the operating range in
the Sodium Pentaborate Solution Temperature/Concentration
Requirements Figure. These changes will provide greater operating
flexibility. The proposed changes will maintain plant operation
within the bounds of the current analysis for the ATWS events and
for accident source term dose limits in the LOCA analysis.
The proposed changes have no adverse effect on plant operation,
or the availability or operation of any accident mitigation
equipment. The plant response to the design basis accidents does not
change. The proposed changes do not adversely affect existing plant
safety margins or the reliability of the equipment assumed to
operate in the safety analyses. There is no change being made to
safety analysis assumptions, safety limits or limiting safety system
settings that would adversely affect plant safety as a result of the
proposed changes.
Therefore, the proposed changes do not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: James G. Danna.
Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50-
425, Vogtle Electric Generating Plant, Units 1 and 2 (VEGP), Burke
County, Georgia
Date of amendment request: October 11, 2017. A publicly-available
version is in ADAMS under Accession No. ML17284A348.
Description of amendment request: The proposed amendments would
revise the VEGP Updated Final Safety Analysis Report (UFSAR) to
incorporate a Tornado Missile Risk Evaluator (TMRE) Methodology based
on Nuclear Energy Institute (NEI) 17-02, Revision 1, ``Tornado Missile
Risk (TMRE) Industry Guidance Document,'' September 2017 (ADAMS
Accession No. ML17268A036). This methodology can only be applied to
discovered conditions where tornado missile protection is not currently
provided, and cannot be used to avoid providing tornado missile
protection in the plant modification process.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
[[Page 13151]]
consideration, which is presented below with staff edits in square
brackets:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment does not involve an increase in the
probability of an accident previously evaluated. The relevant
accident previously evaluated is a Design Basis Tornado impacting
the VEGP site. The probability of a Design Basis Tornado is driven
by external factors and is not affected by the proposed amendment.
There are no changes required to any of the previously evaluated
accidents in the UFSAR.
The proposed amendment does not involve a significant increase
in the consequences of a Design Basis Tornado. [The methodology as
proposed does not alter any input assumptions or results of the
accident analyses. Instead, it reflects a methodology to more
realistically evaluate the probability of unacceptable consequences
of a Design Basis Tornado. As such, there is no significant increase
in the consequence of an accident previously evaluated. A similar
consideration would apply in the event additional non-conforming
conditions are discovered in the future.]
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed amendment will involve no physical changes to the
existing plant, so no new malfunctions could create the possibility
of a new or different kind of accident. The proposed amendment makes
no changes to conditions external to the plant that could create the
possibility of a new or different kind of accident. The proposed
change will not create the possibility of a new or different kind of
accident due to new accident precursors, failure mechanisms,
malfunctions, or accident initiators not considered in the design
and licensing bases. The existing Updated Final Safety Analysis
Report (UFSAR) accident analysis will continue to meet requirements
for the scope and type of accidents that require analysis.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed amendment does not exceed or alter any controlling
numerical value for a parameter established in the UFSAR or
elsewhere in the VEGP [licensing basis] related to design basis or
safety limits. The change does not impact any UFSAR Chapter 6 or 15
Safety Analyses, and those analyses remain valid. The change does
not reduce diversity or redundancy as required by regulation or
credited in the UFSAR. The change does not reduce defense-in-depth
as described in the UFSAR. Therefore, the proposed amendment does
not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis as edited by the
NRC staff and, based on this review, it appears that the three
standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff
proposes to determine that the amendment request involves no
significant hazards consideration.
Attorney for licensee: Jennifer M. Buettner, Associate General
Counsel, Southern Nuclear Operating Company, 40 Iverness Center
Parkway, Birmingham, AL 35242.
NRC Branch Chief: Douglas A. Broaddus.
III. Previously Published Notices of Consideration of Issuance of
Amendments to Facility Operating Licenses and Combined Licenses,
Proposed No Significant Hazards Consideration Determination, and
Opportunity for a Hearing
The following notices were previously published as separate
individual notices. The notice content was the same as above. They were
published as individual notices either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. They are repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
PSEG Nuclear LLC and Exelon Generation Company, LLC, Docket Nos. 50-272
and 50-311, Salem Nuclear Generating Station, Unit Nos. 1 and 2, Salem
County, New Jersey
Date of amendment request: February 8, 2018. A publicly-available
version is in ADAMS under Accession No. ML18040A301.
Brief description of amendment request: The proposed amendments
would modify the Salem Nuclear Generating Station, Unit Nos. 1 and 2,
Technical Specification (TS)-allowed outage time for more than one
inoperable analog rod position indicator from 1 hour to 24 hours and
change the basis for entry into the TS actions for inoperable rod
position indicators from ``per bank'' to ``per group.'' The proposed
amendments would also separate existing TS 3.1.3.2.1, Action a.1, into
two separate actions and would remove the duplicative Action b (Unit
No. 1 only).
Date of publication of individual notice in Federal Register: March
1, 2018 (83 FR 8904).
Expiration date of individual notice: April 2, 2018 (public
comments); April 30, 2018 (hearing requests).
IV. Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items can be accessed as described in the
``Obtaining Information and Submitting Comments'' section of this
document.
Dominion Energy Nuclear Connecticut, Inc., Docket Nos. 50-245, 50-336,
and 50-423, Millstone Power Station, Unit Nos. 1, 2, and 3 (Millstone
1, 2, and 3), New London County, Connecticut
Date of amendment request: June 15, 2017.
Brief description of amendments: The amendments revised the
facility operating licenses by replacing all references to the former
company name, ``Dominion Nuclear Connecticut, Inc.'' (or DNC), with
``Dominion Energy
[[Page 13152]]
Nuclear Connecticut, Inc.'' (or DENC), including the cover of the
Environmental Protection Plan in Appendix B for Millstone 3 and the
Design Features page for Millstone 1, 2, and 3. Additionally,
references to DNC's former ultimate parent company, ``Dominion
Resources, Inc.,'' were replaced with the new name ``Dominion Energy,
Inc.''
Date of issuance: February 26, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days.
Amendment Nos.: 118, 334, and 271. A publicly-available version is
in ADAMS under Accession No. ML18038B200; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Facility Operating License Nos. DPR-21, DPR-65, and NPF-49: The
amendments revised the facility operating licenses and technical
specifications.
Date of initial notice in Federal Register: October 10, 2017 (82 FR
47035) .
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 26, 2018.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear
Plant (PNP), Van Buren County, Michigan
Date of amendment request: November 1, 2017, as supplemented by
letter dated January 24, 2018.
Brief description of amendment: The amendment revised the fire
protection program transition license condition 2.C.(3)(c)2. by
extending the full implementation date by one fuel cycle from the fall
2018 refueling outage to the summer 2020 refueling outage. The
amendment also revised Paragraph 2.C.(3) of the Renewed Facility
Operating License No. DPR-20 for PNP to incorporate the revised fire
protection documentation and approvals.
Date of issuance: February 27, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment No.: 265. A publicly-available version is in ADAMS under
Accession No. ML18039A244; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-20: Amendment revised
the Renewed Facility Operating License.
Date of initial notice in Federal Register: December 5, 2017 (82 FR
57472). The supplemental letter dated January 24, 2018, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated February 27, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick
Generating Station, Units 1 and 2, Montgomery County, Pennsylvania
Date of amendment request: July 19, 2017, as supplemented by
letters dated December 6, 2017; February 19, 2018; and February 27,
2018.
Brief description of amendments: The amendments revised the
existing Technical Specification requirements related to ``operations
with a potential for draining the reactor vessel'' with new
requirements on reactor pressure vessel water inventory control to
protect Safety Limit 2.1.4. Safety Limit 2.1.4 requires reactor
pressure vessel water level to be greater than the top of active
irradiated fuel. The changes are based on Technical Specifications Task
Force Traveler TSTF-542, Revision 2, ``Reactor Pressure Vessel Water
Inventory Control.''
Date of issuance: February 27, 2018.
Effective date: As of the date of issuance and shall be implemented
no later than May 31, 2019.
Amendment Nos.: 227 (Unit 1) and 190 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML18017A201; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-39 and NPF-85:
Amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: September 12, 2017 (82
FR 42848). The supplemental letters dated December 6, 2017; February
19, 2018; and February 27, 2018, provided additional information that
clarified the application, did not expand the scope of the application
as originally noticed, and did not change the NRC staff's original
proposed no significant hazards consideration determination as
published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 27, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick
Generating Station, Units 1 and 2, Montgomery County, Pennsylvania
Date of amendment request: April 24, 2017.
Brief description of amendments: The amendments revised the
existing technical specification (TS) requirements associated with the
main condenser offgas monitoring instrumentation and gaseous effluents.
Specifically, certain requirements are relocated from the TSs to
licensee-controlled documents such that future changes can be made to
these provisions pursuant to 10 CFR 50.59 or by the regulatory
requirements applicable to the licensee-controlled document.
Date of issuance: February 28, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days.
Amendment Nos.: 228 (Unit 1) and 191 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML18025B769; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-39 and NPF-85: The
amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: July 5, 2017 (82 FR
31096).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 28, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point
Nuclear Station, Unit 2, Oswego County, New York
Date of amendment request: May 31, 2017.
Brief description of amendment: The amendment revised the run time
for Surveillance Requirement (SR) 3.6.4.3.1 for Technical Specification
(TS) 3.6.4.3, ``Standby Gas Treatment (SGT) System,'' and SR 3.7.2.1
for TS 3.7.2, ``Control Room Envelope Filtration (CREF) System.'' The
run time for SR 3.6.4.3.1 would be reduced from a continuous 10 hours
to a continuous 15 minutes, and the run time for SR 3.7.2.1 would be
reduced from 1 hour to 15 minutes at
[[Page 13153]]
frequencies controlled in accordance with the Surveillance Frequency
Control Program.
Date of issuance: March 6, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No.: 166. A publicly-available version is in ADAMS under
Accession No. ML18032A177; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-69: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: August 1, 2017 (82 FR
35839). The Commission's related evaluation of the amendment is
contained in a Safety Evaluation dated March 6, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-219, Oyster Creek Nuclear
Generating Station (Oyster Creek), Ocean County, New Jersey
Date amendment request: February 28, 2017, as supplemented by
letters dated September 20 and November 10, 2017.
Brief description of amendment: The amendment changed the site
emergency plan to revise the on-shift staffing and the Emergency
Response Organization staffing for the permanently defueled condition.
Date of issuance: March 7, 2018.
Effective date: Following the docketing of the certifications
required by 10 CFR 50.82(a)(1) that Oyster Creek has been permanently
defueled and shall be implemented within 60 days, as noted, but will
not exceed March 29, 2020.
Amendment No.: 293. A publicly-available version is in ADAMS under
Accession No. ML17356A213; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-16: Amendment revised
the renewed facility operating license.
Date of initial notice in Federal Register; April 25, 2017 (82 FR
19103). The supplemental letters dated September 20 and November 10,
2017, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 7, 2018.
No significant hazards consideration comments received: No.
FirstEnergy Nuclear Operating Company, et al., Docket Nos. 50-334 and
50-412, Beaver Valley Power Station, Unit Nos. 1 and 2, Beaver County,
Pennsylvania
Date of amendment request: April 9, 2017.
Brief description of amendments: The amendments revised Technical
Specifications Section 4.2.1, ``Fuel Assemblies,'' and Section 5.6.3,
``Core Operating Limits Report (COLR),'' to allow the use of Optimized
ZIRLO\TM\ as an approved fuel rod cladding material. In the letter
dated April 9, 2017, the licensee also requested an exemption from
certain requirements of 10 CFR 50.46 and 10 CFR part 50, Appendix K, in
accordance with 10 CFR 50.12, to support the license amendments.
Date of issuance: March 1, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days.
Amendment Nos.: 302 (Unit No. 1) and 191 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18022B116;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-66 and NPF-73:
Amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: July 18, 2017 (82 FR
32881).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated March 1, 2018.
No significant hazards consideration comments received: No.
NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold
Energy Center (DAEC), Linn County, Iowa
Date of amendment request: March 24, 2017.
Brief description of amendment: The amendment revised the DAEC
technical specification (TS) Table 3.3.2.1-1, ``Control Rod Block
Instrumentation,'' by relocating certain cycle-specific Minimum
Critical Power Ratio values to the DAEC Core Operating Limits Report.
The amendment also adds a requirement to DAEC TS 5.6.5, ``Core
Operating Limits Report.''
Date of issuance: March 7, 2018.
Effective date: As of the date of its issuance and shall be
implemented within 180 days of the date of issuance.
Amendment No.: 303. A publicly-available version is in ADAMS under
Accession No. ML18011A059; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-49: Amendment revised
the Renewed Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: May 23, 2017 (82 FR
23627).
The Commission's related evaluation of the amendment is contained
in a Safety evaluation dated March 7, 2018.
No significant hazards consideration comments received: No.
NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold
Energy Center (DAEC), Linn County, Iowa
Date of amendment request: April 20, 2017.
Brief description of amendment: The amendment revised the DAEC
Technical Specification 3.1.2, ``Reactivity Anomalies,'' to change the
method used to perform the reactivity anomaly surveillance. The new
method would allow performance of the surveillance based on the
difference between the monitored (i.e., actual) core reactivity and the
predicted core reactivity. The surveillance is currently performed
based on the difference between the monitored control rod density and
the predicted control rod density.
Date of issuance: March 9, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days of the date of issuance.
Amendment No.: 304. A publicly-available version is in ADAMS under
Accession No. ML18016A627; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-49: The amendment
revised the Technical Specifications.
Date of initial notice in Federal Register: June 19, 2017 (82 FR
27889).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 9, 2018.
No significant hazards consideration comments received: No.
Northern States Power Company (NSPM), Docket No. 50-263, Monticello
Nuclear Generating Plant, Wright County, Minnesota
Date of amendment request: March 24, 2017, as supplemented by
letter dated September 20, 2017.
Brief description of amendment: The amendment revises the
Monticello Nuclear Generating Plant Emergency
[[Page 13154]]
Plan to increase the staff augmentation times for certain emergency
response organization positions from 30 and 60 minutes to 60 and 90
minutes, respectively. Additionally, the amendment defines facility
activation, removes references to augmenting resources from the Prairie
Island Nuclear Generating Plant, removes a 30-minute Electrical
Maintenance Responder, clarifies transfer of Direction and Control
responsibilities, and implements various administrative changes to
position titles, figures, etc.
Date of issuance: March 5, 2018.
Effective date: As of the date of issuance and shall be implemented
within 180 days of issuance.
Amendment No.: 196. A publicly-available version is in ADAMS under
Accession No. ML17349A916; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-22: The amendment
revised the Monticello Nuclear Generating Plant Site Emergency Plan.
Date of initial notice in Federal Register: May 9, 2017 (82 FR
21559). The supplemental letter dated September 20, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 5, 2018.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota, Docket No. 50-263, Monticello
Nuclear Generating Plant, Wright County, Minnesota
Date of amendment request: March 31, 2017, as supplemented by
letter dated September 25, 2017.
Brief description of amendment: The amendment revised the emergency
action level scheme to one based on the Nuclear Energy Institute (NEI)
document NEI 99 01, Revision 6, ``Development of Emergency Action
Levels for Non-Passive Reactors,'' dated November 21, 2012. NEI 99-01,
Revision 6, was endorsed by the NRC by letter dated March 28, 2013.
Date of issuance: March 6, 2018.
Effective date: As of the date of issuance and shall be implemented
within 180 days of issuance.
Amendment No.: 197. A publicly-available version is in ADAMS under
Accession No. ML17345A046; documents related to this amendment are
listed in the safety evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-22: The amendment
revised the Monticello Nuclear Generating Plant Emergency Plan.
Date of initial notice in Federal Register: June 6, 2017 (82 FR
26134). The supplemental letter dated September 25, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the NRC staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a safety evaluation dated March 6, 2018.
No significant hazards consideration comments received: No.
Northern States Power Company, Docket Nos. 50-282 and 50-306, Prairie
Island
Nuclear Generating Plant, Units 1 and 2, Goodhue County, Minnesota
Date of amendment request: February 23, 2017, as supplemented by
letter dated September 20, 2017.
Brief description of amendments: The amendment revised the Prairie
Island Nuclear Generating Plant, Units 1 and 2, Emergency Plan to
increase the staff augmentation times for certain emergency response
organization positions from 30 and 60 minutes to 60 and 90 minutes.
Additionally, the changes defined facility activation, removed
references to augmenting resources from the Monticello Nuclear
Generating Plant, removed 30-minute Electrical Maintenance and 30-
minute Radwaste Operator Responders, clarified transfer of Direction
and Control responsibilities, and implemented various administrative
changes to position titles, figures, etc.
Date of issuance: March 5, 2018.
Effective date: As of the date of issuance and shall be implemented
within 180 days of issuance.
Amendment Nos.: 223--Unit 1; 210--Unit 2. A publicly-available
version is in ADAMS under Accession No. ML17362A202; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-42 and DPR-60: The
amendments revised the Prairie Island Nuclear Generating Plant, Units 1
and 2, Emergency Plan.
Date of initial notice in Federal Register: April 11, 2017 (82 FR
17459). The supplemental letter dated September 20, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated March 5, 2018.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota, Docket Nos. 50-282 and 50-
306, Prairie Island
Nuclear Generating Plant, Units 1 and 2, Goodhue County, Minnesota
Date of amendment request: March 29, 2017, as supplemented by
letter dated September 27, 2017.
Brief description of amendments: The amendments revised the
emergency action level scheme to one based on the Nuclear Energy
Institute (NEI) document NEI 99-01, Revision 6, ``Development of
Emergency Action Levels for Non-Passive Reactors,'' dated November 21,
2012. NEI 99-01, Revision 6, was endorsed by the NRC by letter dated
March 28, 2013.
Date of issuance: March 6, 2018.
Effective date: As of the date of issuance and shall be implemented
within 180 days of issuance.
Amendment Nos.: 224 (Unit 1) and 211 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML17346A361; documents related
to these amendments are listed in the safety evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-42 and DPR-60: The
amendments revised the Prairie Island Nuclear Generating Plant, Units 1
and 2, Emergency Plan.
Date of initial notice in Federal Register: May 23, 2017 (82 FR
23628). The supplemental letter dated September 27, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the NRC staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a safety evaluation dated March 6, 2018.
No significant hazards consideration comments received: No.
[[Page 13155]]
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station,
Unit 1 (FCS), Washington County, Nebraska
Date of amendment request: March 31, 2017, as supplemented by
letter dated September 26, 2017.
Brief description of amendment: The amendment revised the FCS
renewed facility operating license, definitions, and Technical
Specification (TS) sections to align with those required for the
Permanently Defueled TS that will reflect decommissioning requirements.
Date of issuance: March 6, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment No.: 297. A publicly-available version is in ADAMS under
Accession No. ML18010A087; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-40: The amendment
revised the renewed facility operating license and TS.
Date of initial notice in Federal Register: June 6, 2017 (82 FR
26135). The supplemental letter dated September 26, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the NRC staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 6, 2018.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Docket Nos. 50-348 and 50-364,
Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, Alabama
Date of amendment request: November 15, 2016, as supplemented by
letters dated June 22, 2017; September 11, 2017; October 12, 2017; and
February 9, 2018.
Brief description of amendments: The amendments revise Technical
Specification 5.5.17, ``Containment Leakage Rate Testing Program.''
Specifically, the amendments increased the existing Type A integrated
leakage rate test program test interval from 10 years to 15 years;
adopted an extension of the containment isolation valve leakage testing
(Type C) frequency from 60 months to 75 months; adopted the use of
American National Standards Institute/American Nuclear Society (ANSI/
ANS) 56.8-2002, ``Containment System Leakage Testing Requirements'';
and adopted a grace interval of 9 months for Type A, Type B, and Type C
leakage tests, in accordance with Nuclear Energy Institute (NEI) 94-01,
Revision 2-A and Revision 3-A, ``Industry Guideline for Implementing
Performance-Based Option of 10 CFR part 50, Appendix J.''
Date of issuance: February 28, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 217 (Unit 1) and 214 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML17261A087; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-2 and NPF-8: The
amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: January 3, 2017 (82 FR
161). The supplemental letters dated June 22, 2017; September 11, 2017;
October 12, 2017; and February 9, 2018, provided additional information
that clarified the application, did not expand the scope of the
application as originally noticed, and did not change the staff's
original proposed no significant hazards consideration determination as
published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 28, 2018.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Docket Nos. 50-348 and 50-364,
Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, Alabama
Date of amendment request: March 22, 2017.
Brief description of amendments: The amendment revised Technical
Specification 3.7.1, ``Main Steam Safety Valves (MSSVs),'' to resolve a
non-conservative moderator temperature coefficient value.
Date of issuance: March 1, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 218 (Unit 1) and 215 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML17291A781; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-2 and NPF-8: The
amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: May 9, 2017 (82 FR
21562).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated March 1, 2018.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County,
Georgia
Date of amendment request: September 22, 2017, as supplemented by
letter dated January 19, 2018.
Description of amendments: The amendment authorized changes to the
VEGP, Units 3 and 4, Updated Final Safety Analysis Report in the form
of departures from the incorporated plant-specific Design Control
Document Tier 2 and Tier 2* information to modify the licensing
requirements for the American Society of Mechanical Engineers (ASME)
Class 1 piping component analysis from limited to design-by-rule
evaluations described in ASME Section III, NB-3600, to include the
ability to perform design-by-analysis evaluations, as described in ASME
Section III, NB-3200.
Date of issuance: February 22, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment Nos.: 109 (Unit 3) and 108 (Unit 4). A publicly-available
version is in ADAMS under Accession No. ML18026A765; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendment.
Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment
revised the Facility Combined License.
Date of initial notice in Federal Register: October 24, 2017 (82 FR
49241). The supplement dated January 19, 2018, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the NRC
staff's original proposed no significant hazards consideration
determination.
The Commission's related evaluation of the amendments is contained
in the Safety Evaluation dated February 22, 2018.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, on March 19, 2018.
[[Page 13156]]
For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2018-05905 Filed 3-26-18; 8:45 am]
BILLING CODE 7590-01-P