[Federal Register Volume 84, Number 21 (Thursday, January 31, 2019)]
[Notices]
[Pages 808-816]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-00358]
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NUCLEAR REGULATORY COMMISSION
[NRC-2018-0287; NRC-2019-0020]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice; extension of comment period.
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SUMMARY: Pursuant to the Atomic Energy Act of 1954, as amended (the
Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this
regular biweekly notice. The Act requires the Commission to publish
notice of any amendments issued, or proposed to be issued, and grants
the Commission the authority to issue and make immediately effective
any amendment to an operating license or combined license, as
applicable, upon a determination by the Commission that such amendment
involves no significant hazards consideration, notwithstanding the
pendency before the Commission of a request for a hearing from any
person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued, from December 15, 2018, to December 28, 2018.
The last biweekly notice was published on January 2, 2019 (84 FR 20).
The comment period for the document published in the Federal Register
on January 2, 2019 (84 FR 20), was originally scheduled to close on
February 1, 2019. Because this document was posted to Regulations.gov
on January 18, 2019, the NRC has decided to extend the public comment
period to allow more time for stakeholders to develop and submit their
comments. Due to the Federal government shutdown, there was no biweekly
publication on January 15, 2019.
DATES: Comments must be filed by March 4, 2019. A request for a hearing
must be filed by April 1, 2019. The due date for comments requested in
the document published on January 2, 2019 (84 FR 20) is extended.
Comments should be filed no later than March 4, 2019. Comments received
after this date will be considered, if it is practical to do so, but
the Commission is able to ensure consideration only for comments
received on or before this date.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0020. Address
questions about Docket IDs in Regulations.gov to Krupskaya Castellon;
telephone: 301-287-9221; email: [email protected]. For
technical questions, contact the individual(s) listed in the FOR
FURTHER INFORMATION CONTACT section of this document.
Mail comments to: Office of Administration, Mail Stop:
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Shirley Rohrer, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC
20555-0001; telephone: 301-415-5411, [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2019-0020, facility name, unit
number(s), plant docket number, application date, and subject when
contacting the NRC about the availability of information for this
action. You may obtain publicly-available information related to this
action by any of the following methods:
Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0020.
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-2019-0020, facility name, unit
number(s), plant docket number, application date, and subject in your
comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is
publishing this regular biweekly notice. The Act requires the
Commission to publish notice of any amendments issued, or proposed to
be issued, and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license or combined
license, as applicable, upon a determination by the Commission that
such amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
[[Page 809]]
III. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment
period such that failure to act in a timely way would result, for
example in derating or shutdown of the facility. If the Commission
takes action prior to the expiration of either the comment period or
the notice period, it will publish in the Federal Register a notice of
issuance. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed, the
Commission or a presiding officer will rule on the petition and, if
appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the petitioner to relief. A petitioner who
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that party's admitted
contentions, including the opportunity to present evidence, consistent
with the NRC's regulations, policies, and procedures.
Petitions must be filed no later than 60 days from the date of
publication of this notice. Petitions and motions for leave to file new
or amended contentions that are filed after the deadline will not be
entertained absent a determination by the presiding officer that the
filing demonstrates good cause 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
[[Page 810]]
its boundaries. Alternatively, a State, local governmental body,
Federally-recognized Indian Tribe, or agency thereof may participate as
a non-party under 10 CFR 2.315(c).
If a hearing is granted, any person who is not a party to the
proceeding and is not affiliated with or represented by a party may, at
the discretion of the presiding officer, be permitted to make a limited
appearance pursuant to the provisions of 10 CFR 2.315(a). A person
making a limited appearance may make an oral or written statement of
his or her position on the issues but may not otherwise participate in
the proceeding. A limited appearance may be made at any session of the
hearing or at any prehearing conference, subject to the limits and
conditions as may be imposed by the presiding officer. Details
regarding the opportunity to make a limited appearance will be provided
by the presiding officer if such sessions are scheduled.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing and petition for leave to intervene (petition), any
motion or other document filed in the proceeding prior to the
submission of a request for hearing or petition to intervene, and
documents filed by interested governmental entities that request to
participate under 10 CFR 2.315(c), must be filed in accordance with the
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR
46562; August 3, 2012). The E-Filing process requires participants to
submit and serve all adjudicatory documents over the internet, or in
some cases to mail copies on electronic storage media. Detailed
guidance on making electronic submissions may be found in the Guidance
for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit
paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to (1) request a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign submissions and access the E-Filing
system for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a petition or
other adjudicatory document (even in instances in which the
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a
digital ID certificate and a docket has been created, the participant
can then submit adjudicatory documents. Submissions must be in Portable
Document Format (PDF). Additional guidance on PDF submissions is
available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the
time the document is submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
document on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before adjudicatory documents are
filed so that they can obtain access to the documents via the E-Filing
system.
A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic
Filing Help Desk through the ``Contact Us'' link located on the NRC's
public website at http://www.nrc.gov/site-help/e-submittals.html, by
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m.
and 6 p.m., Eastern Time, Monday through Friday, excluding government
holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
stating why there is good cause for not filing electronically and
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: 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
[[Page 811]]
information related to this document, see the ``Obtaining Information
and Submitting Comments'' section of this document.
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287,
Oconee Nuclear Station, Units 1, 2, and 3, Oconee County, South
Carolina
Date of amendment request: November 1, 2018. A publicly-available
version is in ADAMS under Accession No. ML18318A320.
Description of amendment request: The amendments would revise the
dose consequences for the facility, as described in the Updated Final
Safety Analysis Report, to provide fission gas gap release fractions
for high-burnup fuel rods that exceed the linear heat generation rate
limit detailed in Regulatory Guide (RG) 1.183, ``Alternative
Radiological Source Terms for Evaluating Design Basis Accidents at
Nuclear Power Reactors'' (ADAMS Accession No. ML003716792), Table 3,
Footnote 11. The amendments would allow a higher bounding rod power
history and the removal of a restriction on the number of rods per
assembly that can exceed the rod power burnup criteria of Footnote 11
in RG 1.183.
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?
The proposed change involves using gap release fractions for
high-burnup fuel rods (i.e., greater than 54 GWD/MTU [gigawatt days
per metric ton of uranium]) that exceed the 6.3 kW/ft [kilowatt per
foot] linear heat generation rate (LHGR) limit detailed in Table 3,
Footnote 11 of RG 1.183. Increased gap release fractions were
determined and accounted for in the dose analysis for ONS [Oconee
Nuclear Station]. The dose consequences reported in the ONS Updated
Final Safety Analysis Report (UFSAR) were reanalyzed for fuel
handling accidents only. Dose consequences were not reanalyzed for
other non-fuel-handling accidents since no fuel rod that is
predicted to enter departure from nucleate boiling (DNB) will be
permitted to operate beyond the limits of RG 1.183, Table 3,
Footnote 11. The current NRC requirements, as described in 10 CFR
50.67, specifies [sic] dose acceptance criteria in terms of Total
Effective Dose Equivalent (TEDE). The revised dose consequence
analyses for the fuel handling events at ONS meet the applicable
TEDE dose acceptance criteria (specified also in RG 1.183).
The changes proposed do not affect the precursors for fuel
handling accidents analyzed in Chapter 15 of the ONS UFSAR. The
probability remains unchanged since the accident analyses performed
and discussed in the basis for the UFSAR changes involve no change
to a system, structure or component that affects initiating events
for any UFSAR Chapter 15 accident evaluated.
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 previously evaluated?
The proposed change involves using gap release fractions for
high-burnup fuel rods (i.e., greater than 54 GWD/MTU) that exceed
the 6.3 kW/ft LHGR limit detailed in Table 3, Footnote 11 of RG
1.183. Increased gap release fractions were determined for certain
isotopes, and were accounted for in the dose analysis for ONS. The
dose consequences reported in the ONS UFSAR were reanalyzed for fuel
handling accidents only. Dose consequences were not reanalyzed for
other non-fuel-handling accidents since no fuel rod that is
predicted to enter departure from nucleate boiling (DNB) will be
permitted to operate beyond the limits of RG 1.183, Table 3,
Footnote 11.
The proposed change does not involve the addition or
modification of any plant equipment. The proposed change has the
potential to affect future core designs for ONS. However, the impact
will not be beyond the standard function capabilities of the
equipment. The proposed change involves using gap release fractions
that would allow high-burnup fuel rods (i.e., greater than 54 GWD/
MTU) to exceed the 6.3 kW/ft LHGR limit detailed in Table 3,
Footnote 11 of RG 1.183. Accounting for these new gap release
fractions in the dose analysis for ONS does not create the
possibility of a new accident.
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?
The proposed change involves using gap release fractions for
high-burnup fuel rods (i.e., greater than 54 GWD/MTU) that exceed
the 6.3 kW/ft LHGR limit detailed in Table 3, Footnote 11 of RG
1.183. Increased gap release fractions were determined for certain
isotopes, and were accounted for in the dose analysis for ONS. The
dose consequences reported in the ONS UFSAR were reanalyzed for fuel
handling accidents only. Dose consequences were not reanalyzed for
other non-fuel-handling accidents since no fuel rod that is
predicted to enter departure from nucleate boiling (DNB) will be
permitted to operate beyond the limits of RG 1.183, Table 3,
Footnote 11.
The proposed change has the potential for an increased
postulated accident dose at ONS. However, the analysis demonstrates
that the resultant doses are within the appropriate acceptance
criteria. The margin of safety, as defined by 10 CFR 50.67 and
Regulatory Guide 1.183, has been maintained. Furthermore, the
assumptions and input used in the gap release and dose consequences
calculations are conservative. These conservative assumptions ensure
that the radiation doses calculated pursuant to Regulatory Guide
1.183 and cited in this LAR are the upper bounds to radiological
consequences of the fuel handling accidents analyzed. The analysis
shows that with increased gap release fractions accounted for in the
dose consequences calculations there is margin between the offsite
radiation doses calculated and the dose limits of 10 CFR 50.67 and
acceptance criteria of Regulatory Guide 1.183. The proposed change
will not degrade the plant protective boundaries, will not cause a
release of fission products to the public, and will not degrade the
performance of any structures, systems or components important to
safety.
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: Kate Nolan, Deputy General Counsel, Duke
Energy Carolinas, 550 South Tryon Street, Charlotte, NC 28202.
NRC Branch Chief: Michael T. Markley.
Duke Energy Progress, LLC, Docket Nos. 50-325 and 50-324, Brunswick
Steam Electric Plant, Units 1 and 2, Brunswick County, North Carolina
Date of amendment request: October 18, 2018. A publicly-available
version is in ADAMS under Accession No. ML18291A628.
Description of amendment request: The proposed amendments would
revise the allowable value associated with Function 1.b (i.e., 4.16
kiloVolt Emergency Bus Undervoltage (Loss of Voltage)--Time Delay) of
Table 3.3.8.1-1, ``Loss of Power Instrumentation,'' in Technical
Specification 3.3.8.1.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change does not involve a physical alteration of
the plant (i.e., no new or different type of equipment will be
installed). The proposed change revises the Allowable Value for the
Time Delay Loss of Voltage relays to resolve a design vulnerability
potentially impacting the Emergency Diesel Generator (EDG) output
[[Page 812]]
breaker logic; thereby ensuring reliability of the onsite AC
electrical sources. Therefore, the proposed change does not
adversely affect the ability of structures, systems and components
(SSCs) to perform their intended safety function to mitigate the
consequences of an initiating event within the assumed acceptance
limits. Further, the proposed change does not increase the types and
the amounts of radioactive effluent that may be released, nor
significantly increase individual or cumulative occupation/public
radiation exposures.
Therefore, the proposed amendments 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 change revises the Allowable Value for the Time
Delay Loss of Voltage relays. It does not require any modification
to the plant and it does not alter the design configuration, or
method of operation of plant equipment beyond its normal functional
capabilities. The proposed change will not introduce failure modes
that could result in a new accident, and the change does not alter
assumptions made in the safety analysis.
Therefore, the proposed amendments 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 change revises the Allowable Value for the Time
Delay Loss of Voltage relays to resolve a design vulnerability
potentially impacting the EDG output breaker logic; thereby ensuring
reliability of the onsite AC electrical sources. It does not alter
or exceed a design basis or safety limit. There is no change being
made to safety analysis assumptions or the safety limits that would
adversely affect plant safety as a result of the proposed change.
Margins of safety are unaffected by the proposed change and the
applicable requirements of 10 CFR 50.36(c)(3) and 10 CFR 50,
Appendix A will continue to be met.
Therefore, the proposed amendments do not result in 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 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: Kathryn B. Nolan, Deputy General Counsel,
550 South Tryon Street, M/C DEC45A, Charlotte, NC 28202.
NRC Branch Chief: Undine Shoop.
Northern States Power Company, Docket Nos. 50-282 and 50-306, Prairie
Island Nuclear Generating Plant, Units 1 and 2 (PINGP), Goodhue County,
Minnesota
Date of amendment request: October 2, 2018, as supplemented by
letter dated December 4, 2018. Publicly-available versions are in ADAMS
under Accession Nos. ML18275A370 and ML18338A431, respectively.
Description of amendment request: The amendments would revise the
PINGP licensing basis regarding the safety classification of certain
fuel handling equipment. The amendments would revise the PINGP Updated
Safety Analysis Report (USAR) regarding specific fuel handling
equipment to relax the PINGP-specific classification scheme to allow
them to be classified as quality assurance (QA) Type III, non-safety
related.
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 fuel handling accident is the only previously evaluated
accident for the fuel handling equipment being addressed. The
proposed amendment does not result in a significant increase in the
probability of an accident because the change in definition of
substantial amount of radioactivity as applied to determining the
safety classification of the specified fuel handling equipment will
not alter the results of fuel handling accidents analyzed in Chapter
14 of the PINGP Updated Safety Analysis Report.
[Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.]
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any previously evaluated?
Response: No.
The proposed reclassification of specified refueling handling
equipment does not alter existing system interactions or introduce
new system interactions. The change will not affect how the
specified equipment is operated or maintained. Neither will the
change affect the QA requirements for equipment that is required to
maintain integrity for seismic category II/I requirements, so no new
potential accidents need be postulated as a result of the proposed
change.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated in the USAR.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed amendment revises the current licensing basis to
apply a criterion for designating equipment as safety-related that
is consistent with the definition of ``Comparable Off-site
Exposures'' in [American Nuclear Standards Institute/American
Nuclear Society (ANSl/ANS)-58.14-1993] for the purposes of equipment
quality assurance type. The proposed amendment is consistent with
existing regulatory guidance. The proposed amendment does not reduce
compliance with [Atomic Energy Commission (AEC) General Design
Criteria (GDC) 1]. Therefore, the proposed amendment does not
involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Peter M. Glass, Assistant General Counsel,
Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401.
NRC Branch Chief: David J. Wrona.
Southern Nuclear Operating Company, Inc., Docket Nos. 52-025 and 52-
026, Vogtle Electric Generating Plant, Units 3 and 4, Burke County,
Georgia
Date of amendment request: November 20, 2018. A publicly-available
version is in ADAMS under Accession No. ML18324A823.
Description of amendment request: The requested amendment proposes
to depart from information in the Updated Final Safety Analysis Report
(UFSAR) (which includes the plant-specific Design Control Document Tier
2 information) and involves related changes to plant-specific Tier 1
information, with corresponding changes to the associated Combined
License (COL) Appendix C information. Specifically, the requested
amendment proposes changes that are editorial in nature to promote
consistency with the licensing basis.
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 consistency and editorial changes to Tier 2
information in the UFSAR, COL Appendix C (and associated plant-
specific Tier 1) information, and COL Appendix A Technical
Specifications do not
[[Page 813]]
involve a technical change (e.g., there is no design parameter or
requirement, calculation, analysis, function or qualification
change). No structure, system, or component (SSC) design or function
would be affected. No design or safety analysis would be affected.
The proposed changes do not affect any accident initiating event or
component failure, thus the probabilities of the accidents
previously evaluated are not affected. No function used to mitigate
a radioactive material release and no radioactive material release
source term is involved, thus the radioactive releases in the
accident analyses are not affected.
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 consistency and editorial changes to Tier 2
information in the UFSAR, COL Appendix C (and associated plant-
specific Tier 1) information, and COL Appendix A Technical
Specifications do not change the design of safety-related SSCs. The
proposed changes do not affect plant electrical systems, and does
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 UFSAR is affected by the proposed
changes.
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 consistency and editorial changes to Tier 2
information in the UFSAR, COL Appendix C (and associated plant-
specific Tier 1) information, and COL Appendix A Technical
Specifications do not involve any change to the design as described
in the COL. There would be no change to an existing design basis,
design function, regulatory criterion, or analyses. 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
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 L. Dixon-Herrity.
IV. Previously Published Notices of Consideration of Issuance of
Amendments to Facility Operating Licenses and Combined Licenses,
Proposed No Significant Hazards Consideration Determination, and
Opportunity for a Hearing
The following notices were previously published as separate
individual notices. The notice content was the same as above. They were
published as individual notices either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. They are repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power
Station (CPS), Unit No.1, DeWitt County, Illinois
Date of amendment request: September 17, 2018. A publicly-available
version is in ADAMS under Accession No. ML18260A307.
Description of amendment request: The amendment would recapture
low-power testing time to extend the full-power operating license
(FPOL) to expire on April 17, 2027, instead of the current expiration
date of September 29, 2026.
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 amendment does not involve a significant increase
in the probability or consequences of an accident previously
evaluated because it does not involve a change to the design
configuration or operation of the facility. The proposed change does
not affect the source term, containment isolation or radiological
release assumptions used in evaluating the radiological consequences
of an accident previously analyzed in the CPS Updated Safety
Analysis Report (USAR).
CPS was designed and constructed to ensure at least a 40-year
service life. Design features provide for inspection of structures,
systems, and components during this service life. Surveillance,
inspection, and maintenance practices, which have been implemented
in accordance with the American Society of Mechanical Engineers
(ASME) Boiler and Pressure Vessel Code and the CPS Technical
Specifications, provide assurance that any degradation in plant
safety-related equipment will be identified and corrected to ensure
continued safe operation of the unit throughout the duration of the
facility operating license.
The low-power testing recapture period requested by this
amendment is for 6.5 months. This time period is insignificant from
an aging effects perspective, particularly when considered in
conjunction with the surveillance, inspection, and maintenance
programs described above.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any previously evaluated?
Response: No.
The proposed amendment would revise the expiration date of the
facility operating license to base it upon the issuance date of the
FPOL and not the issuance date of the low-power testing license. The
proposed change does not involve physical alteration of plant
systems, structures, or components, or changes in parameters
governing the manner in which the plant is operated and maintained.
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 would revise the expiration date of the
facility operating license to base it upon the issuance date of the
FPOL and not the issuance date of the low-power testing license. No
physical changes are being made to the design features or operation
of the facility.
Margin of safety is associated with confidence in the ability of
the fission produce barriers (i.e., fuel cladding, reactor coolant
system pressure boundary, and containment structure) to limit the
radiological dose to the public and control room operators in the
event of an accident. The proposed amendment to the facility
operating license has no impact on the margin of safety and
robustness provided in the design and construction of the facility.
In addition, the proposed amendment will not relax any of the
criteria used to establish safety limits, nor will the proposed
amendment relax safety system settings or limiting conditions for
operation as defined in the Technical Specifications.
Therefore, the proposed amendment does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
[[Page 814]]
Attorney for licensee: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, 4300 Winfield Road, Warrenville, IL 60555.
NRC Branch Chief: David J. Wrona.
V. Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items can be accessed as described in the
``Obtaining Information and Submitting Comments'' section of this
document.
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287,
Oconee Nuclear Station, Units 1, 2, and 3, Oconee County, South
Carolina
Date of amendment request: October 20, 2017, as supplemented by
letters dated June 15, July 20, and September 21, 2018.
Brief description of amendments: The amendments revise the Updated
Final Safety Analysis Report (UFSAR) to provide off-nominal success
criteria for maintaining the reactor in a safe shutdown condition when
using the Standby Shutdown Facility (SSF) to mitigate a Turbine
Building Flood occurring when an Oconee Unit is not at nominal full
power conditions. The amendments also revise the UFSAR to allow the use
of the Main Steam Atmospheric Dump Valves, when available, to enhance
SSF mitigation capabilities.
Date of issuance: December 17, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 410, 412, and 411. A publicly-available version is
in ADAMS under Accession No. ML18311A134; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Facility Operating License Nos. DPR-38, DPR-47 and DPR-55:
Amendments revised the UFSAR.
Date of initial notice in Federal Register: July 3, 2018 (83 FR
31193), as corrected by a notice published on July 10, 2018 (83 FR
31979), that changed the period for filing petitions to account for a
Federal holiday. The supplemental letters dated June 15, July 20, and
September 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 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 December 17, 2018.
No significant hazards consideration comments received: No.
Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50-
458, River Bend Station, Unit 1 (RBS), West Feliciana Parish, Louisiana
Date of amendment request: January 29, 2018, as supplemented by
letters dated June 21, August 15, and November 13, 2018.
Brief description of amendment: The amendment revised the RBS
Updated Safety Analysis Report to reflect the relocation of the reactor
core isolation cooling injection point from the reactor vessel head
spray nozzle to the `A' Feedwater line via the `A' Residual Heat
Removal shutdown cooling return line.
Date of issuance: December 21, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days from the date of issuance.
Amendment No.: 194. A publicly-available version is in ADAMS under
Accession No. ML18345A342; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. NPF-47: The amendment revised the
Updated Safety Analysis Report.
Date of initial notice in Federal Register: May 22, 2018 (83 FR
23732). The supplemental letters dated June 21, August 15, and November
13, 2018, provided additional information that clarified the
application, did not expand the scope of the application as originally
noticed, and did not change the NRC staff's original proposed no
significant hazards consideration determination as published in the
Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated December 21, 2018.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-286, Indian Point
Nuclear Generating Unit No. 3 (Indian Point 3), Westchester County, New
York
Date of amendment request: December 8, 2017, as supplemented by
letter dated July 3, 2018.
Brief description of amendment: The amendment revised Technical
Specification 5.5.15, ``Containment Leakage Rate Testing Program,'' to
extend the frequency of the primary containment integrated leak rate
test, or Type A test, at Indian Point 3. Specifically, the amendment
allows for a one-time extension of the integrated leak rate test
frequency from 15 years to no later than the plant restart after the
Indian Point 3 Spring 2021 (3R21) Refueling Outage (i.e., approximately
16 years).
Date of issuance: December 20, 2018.
Effective date: As of the date of issuance, and shall be
implemented within 30 days.
Amendment No.: 265. A publicly-available version is in ADAMS under
Accession No. ML18337A422; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Amended Facility Operating License No. DPR-64: The amendment
revised the Amended Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: March 13, 2018 (83 FR
10916). The supplemental letter dated July 3, 2018, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change
[[Page 815]]
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 December 20, 2018.
No significant hazards consideration comments received: No.
Entergy Operations, Inc., Docket No. 50-368, Arkansas Nuclear One, Unit
2 (ANO-2), Pope County, Arkansas
Date of amendment request: December 14, 2017.
Brief description of amendment: The amendment revised the technical
specification (TS) requirements in ANO-2 TS 3.3.3.6, ``Post-Accident
Instrumentation,'' to ensure both Category 1 and Type A Regulatory
Guide 1.97, Revision 3, ``Instrumentation for Light-Water-Cooled
Nuclear Power Plants to Assess Plant and Environs Conditions During and
Following an Accident,'' instrumentation is included in the
specification (unless already addressed within another specification)
and gains greater consistency with NUREG-1432, Revision 4, ``Standard
Technical Specifications, Combustion Engineering Plants.''
Date of issuance: December 19, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment No.: 313. A publicly-available version is in ADAMS under
Accession No. ML18317A382; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-6: The amendment revised
the Renewed Facility Operating License and TS.
Date of initial notice in Federal Register: February 27, 2018 (83
FR 8515).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated December 19, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle
County Station (LSCS), Units 1 and 2, LaSalle County, Illinois
Date of amendment request: February 27, 2018.
Brief description of amendment: The amendments revised the LSCS
Technical Specification 3.4.4, ``Safety/Relief Valves (S/RVs).''
Specifically, the amendments change the as-found tolerances with
respect to the lift setpoint lower tolerance limit for the S/RVs as
delineated in Surveillance Requirement 3.4.4.1 from -3 percent to -5
percent. The as-found tolerances are used for determining operability
and to increase sample sizes for S/RV testing should the tolerance be
exceeded.
Date of issuance: December 19, 2018.
Effective date: As of the date of issuance and shall be implemented
within 45 days of issuance.
Amendment No.: Unit 1--232; Unit 2--218. A publicly-available
version is in ADAMS under Accession No. ML18278A030; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-11 and NPF-18: The
amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: April 10, 2018 (83 FR
15416).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated December 19, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island
Nuclear Station, Unit 1, Dauphin County, Pennsylvania
Date of amendment request: November 10, 2017, as supplemented by
letters dated October 10, 2018, and October 29, 2018.
Brief description of amendment: The amendment revised Section 6.0,
``Administrative Controls,'' of the Three Mile Island Nuclear Station,
Unit 1, Technical Specifications, which makes changes to the
organization, staffing, and training requirements. The amendment also
revised Section 1.0, ``Definitions,'' of the Technical Specifications
to add two new positions for Certified Fuel Handler and Non-Certified
Operator.
Date of issuance: December 14, 2018.
Effective date: The amendment will be effective upon the licensee's
submittal of the certifications required by 10 CFR 50.82(a)(1)(i) and
(ii), and shall be implemented within 60 days of the effective date of
the amendment, but may not exceed December 31, 2019.
Amendment No.: 295. A publicly-available version is in ADAMS under
Accession No. ML18305B419; documents related to this amendment is
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-50: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: February 13, 2018 (83
FR 6225). The supplemental letters dated October 10, 2018, and October
29, 2018, provided additional information that clarified the
application, did not expand the scope of the application as originally
noticed, and did not change the NRC staff's original proposed no
significant hazards consideration determination as published in the
Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated December 14, 2018.
No significant hazards consideration comments received: No.
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: December 18, 2017.
Brief description of amendments: The amendments revised Technical
Specification 3/4.3.1, ``Reactor Trip System Instrumentation,'' and
Technical Specification 3/4.3.2, ``Engineered Safety Feature Actuation
System Instrumentation,'' to increase the completion times and bypass
test times at Salem Nuclear Generating Station, Unit Nos. 1 and 2.
These changes are consistent with the NRC-approved Technical
Specifications Task Force (TSTF) Travelers TSTF-411, Revision 1,
``Surveillance Test Interval Extension for Components of the Reactor
Protection System (WCAP-15376-P),'' and TSTF-418, Revision 2, ``RPS
[Reactor Protection System] and ESFAS [Engineered Safety Feature
Actuation System] Test Times and Completion Times (WCAP-14333),'' or
are supported by plant-specific analysis.
Date of issuance: December 19, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment Nos.: 325 (Unit No. 1) and 306 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18318A266;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-70 and DPR-75: The
amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
[[Page 816]]
Date of initial notice in Federal Register: March 13, 2018 (83 FR
10921). The supplemental letters dated February 9, 2018 and July 17,
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 December 19, 2018.
No significant hazards consideration comments received: No.
Tennessee Valley Authority, Docket No. 50-391, Watts Bar Nuclear Plant,
Unit 2, Rhea County, Tennessee
Date of amendment request: October 31, 2018.
Brief description of amendment: The amendment revised the
completion date for License Condition 2.C.(5) for the Watts Bar Nuclear
Plant, Unit 2, regarding the completion of action to resolve the issues
identified in NRC Bulletin 2012-01, ``Design Vulnerability in Electric
Power System'' (ADAMS Accession No. ML12074A115), from December 31,
2018, to December 31, 2019, to align with the remainder of the
Tennessee Valley Authority fleet and with the nuclear industry.
Date of issuance: December 21, 2018.
Effective date: As of the date of issuance and shall be implemented
immediately.
Amendment No.: 23. A publicly-available version is in ADAMS under
Accession No. ML18334A333; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. NPF-96: The amendment revised the
Facility Operating License.
Date of initial notice in Federal Register: November 14, 2018 (83
FR 56876).
The Commission's related evaluation of the amendment and final
determination of no significant hazards consideration is contained in a
Safety Evaluation dated December 21, 2018.
No significant hazards consideration comments received: One comment
was received on December 14, 2018. The public comment and the NRC staff
response are provided in the Safety Evaluation.
Dated at Rockville, Maryland, this 25th day of January 2019.
For the Nuclear Regulatory Commission.
Gregory F. Suber,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2019-00358 Filed 1-30-19; 8:45 am]
BILLING CODE 7590-01-P