[Federal Register Volume 84, Number 78 (Tuesday, April 23, 2019)]
[Notices]
[Pages 16890-16897]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-07933]
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NUCLEAR REGULATORY COMMISSION
[NRC-2019-0099]
Biweekly Notice: Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice.
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SUMMARY: Pursuant to the Atomic Energy Act of 1954, as amended (the
Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this
regular biweekly notice. The Act requires the Commission to publish
notice of any amendments issued, or proposed to be issued, and grants
the Commission the authority to issue and make immediately effective
any amendment to an operating license or combined license, as
applicable, upon a determination by the Commission that such amendment
involves no significant hazards consideration, notwithstanding the
pendency before the Commission of a request for a hearing from any
person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued, from March 26, 2019 to April 8, 2019. The last
biweekly notice was published on April 9, 2019.
DATES: Comments must be filed by May 23, 2019. A request for a hearing
must be filed by June 24, 2019.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0099. Address
questions about NRC dockets IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this document.
Mail comments to: 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: Lynn Ronewicz, Office of Nuclear
Reactor Regulations, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-1927, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2019-0099, 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-2019-0099.
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
[[Page 16891]]
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-2019-0099, 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 NRC is publishing this regular biweekly notice.
The Act requires the Commission to publish notice of any amendments
issued, or proposed to be issued, and grants the Commission the
authority to issue and make immediately effective any amendment to an
operating license or combined license, as applicable, upon a
determination by the Commission that such amendment involves no
significant hazards consideration, notwithstanding the pendency before
the Commission of a request for a hearing from any person.
III. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment
period such that failure to act in a timely way would result, for
example in derating or shutdown of the facility. If the Commission
takes action prior to the expiration of either the comment period or
the notice period, it will publish in the Federal Register a notice of
issuance. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed, the
Commission or a presiding officer will rule on the petition and, if
appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the petitioner to relief. A petitioner who
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that party's admitted
contentions, including the opportunity to present evidence, consistent
with the NRC's regulations, policies, and procedures.
Petitions must be filed no later than 60 days from the date of
publication of this notice. Petitions and motions for leave to file new
or amended contentions that are filed after the deadline will not be
entertained absent a determination by the presiding officer
[[Page 16892]]
that the filing demonstrates good cause by satisfying the three factors
in 10 CFR 2.309(c)(1)(i) through (iii). The petition must be filed in
accordance with the filing instructions in the ``Electronic Submissions
(E-Filing)'' section of this document.
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to establish when the hearing is held. If the final determination is
that the amendment request involves no significant hazards
consideration, the Commission may issue the amendment and make it
immediately effective, notwithstanding the request for a hearing. Any
hearing would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of the amendment unless the Commission finds an imminent
danger to the health or safety of the public, in which case it will
issue an appropriate order or rule under 10 CFR part 2.
A State, local governmental body, Federally-recognized Indian
Tribe, or agency thereof, may submit a petition to the Commission to
participate as a party under 10 CFR 2.309(h)(1). The petition should
state the nature and extent of the petitioner's interest in the
proceeding. The petition should be submitted to the Commission no later
than 60 days from the date of publication of this notice. The petition
must be filed in accordance with the filing instructions in the
``Electronic Submissions (E-Filing)'' section of this document, and
should meet the requirements for petitions set forth in this section,
except that under 10 CFR 2.309(h)(2) a State, local governmental body,
or Federally recognized Indian Tribe, or agency thereof does not need
to address the standing requirements in 10 CFR 2.309(d) if the facility
is located within its boundaries. Alternatively, a State, local
governmental body, Federally-recognized Indian Tribe, or agency thereof
may participate as a non-party under 10 CFR 2.315(c).
If a hearing is granted, any person who is not a party to the
proceeding and is not affiliated with or represented by a party may, at
the discretion of the presiding officer, be permitted to make a limited
appearance pursuant to the provisions of 10 CFR 2.315(a). A person
making a limited appearance may make an oral or written statement of
his or her position on the issues but may not otherwise participate in
the proceeding. A limited appearance may be made at any session of the
hearing or at any prehearing conference, subject to the limits and
conditions as may be imposed by the presiding officer. Details
regarding the opportunity to make a limited appearance will be provided
by the presiding officer if such sessions are scheduled.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing and petition for leave to intervene (petition), any
motion or other document filed in the proceeding prior to the
submission of a request for hearing or petition to intervene, and
documents filed by interested governmental entities that request to
participate under 10 CFR 2.315(c), must be filed in accordance with the
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR
46562; August 3, 2012). The E-Filing process requires participants to
submit and serve all adjudicatory documents over the internet, or in
some cases to mail copies on electronic storage media. Detailed
guidance on making electronic submissions may be found in the Guidance
for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit
paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to (1) request a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign submissions and access the E-Filing
system for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a petition or
other adjudicatory document (even in instances in which the
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a
digital ID certificate and a docket has been created, the participant
can then submit adjudicatory documents. Submissions must be in Portable
Document Format (PDF). Additional guidance on PDF submissions is
available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the
time 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,
[[Page 16893]]
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
application(s), 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.
Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire
Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina
Date of amendment request: February 5, 2019. A publicly-available
version is in ADAMS under Accession No. ML19042A117.
Description of amendment request: The amendments would modify
Technical Specification (TS) 3.5.2, ECCS [Emergency Core Cooling
System]--Operating''; TS 3.6.6, ``Containment Spray System''; TS 3.7.5,
``Auxiliary Feedwater (AFW) System''; TS 3.7.6, ``Component Cooling
Water (CCW) System''; TS 3.7.7, ``Nuclear Service Water System
(NSWS)''; TS 3.7.9, ``Control Room Area Ventilation System (CRAVS)'';
TS 3.7.11, ``Auxiliary Building Filtered Ventilation Exhaust System
(ABFVES)''; TS 3.8.1, ``AC [Alternate Current] Sources--Operating'';
and TS 3.8.4, ``DC [Direct Current] Sources--Operating,'' to remove
expired TS footnotes. Additionally, the amendments would fix an
editorial error in Section 3.0, ``SR [Surveillance Requirement]
APPLICABILITY,'' specifically, SR 3.0.5.
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.
This LAR [license amendment request] proposes administrative
non-technical changes only. These proposed changes do not adversely
affect accident initiators or precursors nor alter the design
assumptions, conditions, or configurations of the facility. The
proposed changes do not alter or prevent the ability of structures,
systems, and components (SSCs) to perform their intended function to
mitigate the consequences of an initiating event within the assumed
limits.
Given the above discussion, it is concluded the proposed
amendment does not significantly increase 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.
This LAR proposes administrative non-technical changes only. The
proposed changes will not alter the design requirements of any
Structure, System or Component (SSC) or its function during accident
conditions. No new or different accidents result from the proposed
changes. The changes do not involve a physical alteration of the
plant or any changes in methods governing normal plant operation.
The changes do not alter assumptions made in the safety analysis.
Given the above discussion, it is concluded 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 the margin of safety?
Response: No.
This LAR proposes administrative non-technical changes only. The
proposed changes do not alter the manner in which safety limits,
limiting safety systems settings or limiting conditions for
operation are determined. The safety analysis acceptance criteria
are not affected by these changes. The proposed changes will not
result in plant operation in a configuration outside the design
basis. The proposed changes do not adversely affect systems that
respond to safety shutdown the plant and to maintain the plant in a
safe shutdown condition.
Given the above discussion, it is concluded the proposed
amendment does not involve a significant reduction in the safety
margin.
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 B. Nolan, Deputy General Counsel, Duke
Energy Carolinas, LLC, 550 South Tryon Street--DEC45A Charlotte, NC
28202-1802.
NRC Branch Chief: Michael T. Markley.
Exelon FitzPatrick, LLC and Exelon Generation Company, LLC, Docket
No. 50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County,
New York.
Date of amendment request: March 7, 2019. A publicly-available
version is in ADAMS under Accession No. ML19066A251.
Description of amendment request: The amendment would revise the
James A. FitzPatrick Nuclear Power Plant Technical Specification
requirements regarding ventilation system testing in accordance with
Technical Specifications Task Force (TSTF) Traveler, TSTF-522, Revision
0, ``Revise Ventilation System Surveillance Requirements to Operate for
10 Hours per Month'' (ADAMS Accession No. ML100890316). The NRC
approved TSTF-522, Revision 0, as part of the consolidated line item
improvement process on September 20, 2012 (77 FR 58421).
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?
[[Page 16894]]
Response: No.
The proposed change replaces an existing Surveillance
Requirement to operate the SGT [Standby Gas Treatment] System
equipped with electric heaters for a continuous 10-hour period every
31 days with a requirement to operate the systems for 15 continuous
minutes with heaters operating.
The system is not an accident initiator and therefore, these
changes do not involve a significant increase in the probability of
an accident. The proposed system and filter testing change is
consistent with current regulatory guidance for the system and will
continue to assure that the system performs the design function
which may include mitigating accidents. Thus, the change does not
involve a significant increase in the consequences of an accident.
Therefore, it is concluded that this change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed change replaces an existing Surveillance
Requirement to operate the SGT System for a continuous 10-hour
period every 31 days with a requirement to operate the system for 15
continuous minutes with heaters operating.
The change proposed for the ventilation system does not change
any system operations or maintenance activities. Testing
requirements will be revised and will continue to demonstrate that
the Limiting Conditions for Operation are met, and the system
components are capable of performing their intended safety
functions. The change does not create new failure modes or
mechanisms and no new accident precursors are generated.
Therefore, it is concluded that this change does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed change replaces an existing Surveillance
Requirement to operate the SGT System equipped with electric heaters
for a continuous 10-hour period every 31 days with a requirement to
operate the systems for 15 continuous minutes with heaters
operating, if needed.
The design basis for the ventilation systems' heaters is to heat
the incoming air which reduces the relative humidity. The heater
testing change proposed will continue to demonstrate that the
heaters are capable of heating the air and will perform their design
function. The proposed change is consistent with regulatory
guidance.
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: Donald P. Ferraro, Assistant General
Counsel, Exelon Generation Company, LLC, 200 Exelon Way, Suite 305,
Kennett Square, PA 19348.
NRC Branch Chief: James G. Danna.
Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna
Nuclear Power Plant, Wayne County, New York
Date of amendment request: January 15, 2019. A publicly-available
version is in ADAMS under Accession No. ML19017A136.
Description of amendment request: The amendment would revise the
emergency response organization (ERO) positions identified in the
Emergency Plan for the R. E. Ginna Nuclear Power Plant.
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:
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.
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 Ginna Emergency Plan do not increase
the probability or consequences of an accident. The proposed changes
do not impact the function of plant Structures, Systems, or
Components (SSCs). The proposed changes do not affect accident
initiators or accident precursors, nor do the changes alter design
assumptions. The proposed changes do not alter or prevent the
ability of the onsite ERO to perform their intended functions to
mitigate the consequences of an accident or event. The proposed
changes remove ERO positions no longer credited or considered
necessary in support of Emergency Plan implementation.
Therefore, the proposed changes to the Ginna Emergency Plan do
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 have no impact on the design, function, or
operation of any plant SSCs. The proposed changes do not affect
plant equipment or accident analyses. The proposed changes do not
involve a physical alteration of the plant (i.e., no new or
different type of equipment will be installed), a change in the
method of plant operation, or new operator actions. The proposed
changes do not introduce failure modes that could result in a new
accident, and the proposed changes do not alter assumptions made in
the safety analysis. The proposed changes remove ERO positions no
longer credited or considered necessary in support of Emergency Plan
implementation.
Therefore, the proposed changes to the Ginna Emergency Plan do
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.
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 do not adversely affect existing plant
safety margins or the reliability of the equipment assumed to
operate in the safety analyses. There are no changes 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. Margins of safety are unaffected by the
proposed changes to the ERO staffing.
The proposed changes are associated with the Ginna Emergency
Plan staffing and do not impact operation of the plant or its
response to transients or accidents. The proposed 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. Safety analysis
acceptance criteria are not affected by these proposed changes. The
proposed changes to the Emergency Plan will continue to provide the
necessary onsite ERO response staff.
Therefore, the proposed changes to the Ginna Emergency Plan do
not involve a significant reduction in a margin of safety.
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.
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
[[Page 16895]]
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.
Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Unit Nos.
1, 2, and 3, Maricopa County, Arizona
Date of application for amendments: May 25, 2018, as supplemented
by letters dated October 12, 2018, and January 31, 2019.
Brief description of amendments: The amendments documented approval
of elimination of periodic response time testing for a specific
pressure transmitter, consistent with the Palo Verde Nuclear Generating
Station, Unit Nos. 1, 2, and 3, Technical Specifications.
Date of issuance: April 3, 2019.
Effective date: As of the date of issuance and shall be implemented
within 30 days from the date of issuance.
Amendment Nos.: 208 (Unit 1), 208 (Unit 2), and 208 (Unit 3). A
publicly-available version is in ADAMS under Accession No. ML19070A218.
Documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. NPF-41, NPF-51, and NPF-74:
The amendments approved allocated response time verification usage for
a specific set of replacement components in lieu of directly measured
response time testing.
Date of initial notice in Federal Register: July 31, 2018 (83 FR
36973). The supplemental letters dated October 12, 2018, and January
31, 2019, 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 April 3, 2019.
No significant hazards consideration comments received: No.
Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear
Power Plant, Unit 1, Wake County, North Carolina
Date of amendment request: October 19, 2017, as supplemented by
letters dated January 11, 2018, and September 19, 2018.
Brief description of amendment: The amendment revised the Renewed
Facility Operating License to authorize revision of the Shearon Harris
Nuclear Power Plant Updated Final Safety Analysis Report to incorporate
the process based on the Tornado Missile Risk Evaluator Methodology
described in its application, as supplemented. This methodology will
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.
Date of issuance: March 29, 2019.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment No.: 169. A publicly-available version is in ADAMS under
Accession No. ML18347A385; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-63: The amendment
revised the Renewed Facility Operating License.
Date of initial notice in Federal Register: February 13, 2018 (83
FR 6221). The supplemental letter dated September 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 as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 29, 2019.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. STN50-455, Byron Station,
Unit No. 2, Ogle County, Illinois
Date of amendment request: March 8, 2018, as supplemented by
letters dated July 2, 2018; December 18, 2018; and January 16, 2019.
Brief description of amendment: The amendment revised Technical
Specification (TS) 4.2.1 to authorize use of two lead test assemblies
containing a limited number of accident tolerant fuel lead test rods
during Byron Station, Unit No. 2, refueling cycles 22, 23, and 24. The
lead test assemblies are non-limiting under steady state reactor
conditions and will comply with fuel limits specified in the core
operating limits report and TSs under all operational conditions.
Date of issuance: April 3, 2019.
Effective date: As of the date of issuance and shall be implemented
prior to startup with the lead test assemblies.
Amendment No: 207. A publicly-available version is in ADAMS under
Accession No. ML19038A017; documents related to this amendment are
listed in the related Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-66: The amendment
revised the Renewed Facility Operating License and TSs.
Date of initial notice in Federal Register: November 6, 2018 (83 FR
55573). The supplements dated July 2, 2018, and December 18, 2018,
provided additional information that clarified the application, did not
expand the scope of the application as originally noticed, and did not
change the NRC staff's original proposed no significant hazards
consideration determination as published in the Federal Register. The
supplement dated January 16, 2019, changed the scope of the application
as originally noticed by eliminating the license condition and
requesting a change to TS 4.2.1. The change in scope and the updated
proposed significant hazards consideration was published in the Federal
Register on February 1, 2019 (84 FR 1240).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 3, 2019.
[[Page 16896]]
No significant hazards consideration comments received: No.
Florida Power & Light Company, Docket Nos. 50-250 and 50-251, Turkey
Point Nuclear Generating Unit Nos. 3 and 4, Miami-Dade County, Florida
Date of amendment request: October 17, 2018; as supplemented by
letters dated October 24, 2018; December 3, 2018; and January 31, 2019.
Brief description of amendments: The amendments modified the
Renewed Facility Operating Licenses by revising paragraph 3.D,
``Transition License Conditions,'' to eliminate reliance on NRC
approval of the Flowserve Reactor Coolant Pump (RCP) Seal Topical
Report as a condition of Turkey Point Nuclear Generating's transition
to National Fire Protection Association Standard 805, and instead
documented the guidance outlined in NRC-approved Topical Report WCAP-
16175-P-A, Revision 0, ``Model for Failure of RCP Seals Given Loss of
Seal Cooling in CE [Combustion Engineering] NSSS [Nuclear Steam Supply
System] Plants.'' A non-proprietary version of WCAP-16175-P-A, Revision
0, can be found in ADAMS under Accession No. ML071130383.
Date of issuance: March 27, 2019.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment Nos.: 286 (Unit No. 3) and 280 (Unit No. 4). A publicly-
available version is in ADAMS under Accession No. ML19064A903;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-31 and DPR-41: The
amendments revised the Renewed Facility Operating Licenses.
Date of initial notice in Federal Register: December 26, 2018 (83
FR 66318). The supplemental letters dated December 3, 2018, and January
31, 2019, 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 27, 2019.
No significant hazards consideration comments received: No.
NextEra Energy Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point
Beach Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowoc
County, Wisconsin
Date of amendment request: March 31, 2017, as supplemented by
letters dated April 12, 2018 (two); May 29, 2018; August 30, 2018; and
March 13, 2019.
Brief description of amendments: The amendments revised the Point
Beach Nuclear Plant, Units 1 and 2, operating licenses by adding a
license condition to resolve construction truss design code
nonconformances. The amendments approved a risk-informed approach to
resolve legacy design code nonconformances associated with construction
trusses in the containment buildings of Point Beach Nuclear Plant,
Units 1 and 2, following the guidance in Regulatory Guide 1.174,
Revision 2, ``An Approach for Using Probabilistic Risk Assessment in
Risk-Informed Decisions on Plant-Specific Changes to the Licensing
Basis,'' issued May 2011.
Date of issuance: March 26, 2019.
Effective date: As of the date of issuance and shall be implemented
in accordance with the requirements specified in paragraphs 4.I and 4.H
of Renewed Facility Operating License Nos. DPR-24 and DPR-27,
respectively.
Amendment Nos.: 263 (Unit 1) and 266 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML18345A110; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-24 and DPR-27: The
amendments revised the Renewed Facility Operating Licenses.
Date of initial notice in Federal Register: June 19, 2017 (82 FR
27890). The supplemental letters dated April 12, 2018 (two); May 29,
2018; August 30, 2018; and March 13, 2019, 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 26, 2019.
No significant hazards consideration comments received: No.
NextEra Energy, Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point
Beach Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowoc
County, Wisconsin
Date of amendment request: July 30, 2018.
Brief description of amendments: The amendments revised the Point
Beach Nuclear Plant, Units 1 and 2, Technical Specifications (TSs),
consistent with NRC-approved Technical Specifications Task Force (TSTF)
Traveler TSTF-547, Revision 1, ``Clarification of Rod Position
Requirements.'' The amendments provide time to repair rod movement
failures that do not affect rod operability, correct conflicts between
the TSs, increase consistency between the subject TSs, and improve the
format and presentation.
Date of issuance: March 27, 2019.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 264 (Unit 1) and 267 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML19052A544; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-24 and DPR-27: The
amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: November 6, 2018 (83 FR
55575).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated March 27, 2019.
No significant hazards consideration comments received: No.
NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit
No. 1, Rockingham County, New Hampshire
Date of amendment request: March 16, 2018.
Description of amendment request: The amendment revised the
frequencies for performing the relative pressure measurement and the
assessment of the control room envelope boundary required by Technical
Specification 6.7.6.l, ``Control Room Envelope Habitability Program.''
Date of issuance: March 29, 2019.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment No.: 160. A publicly-available version is in ADAMS under
Accession No. ML19065A215; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
[[Page 16897]]
Renewed Facility Operating License No. NPF-86: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: July 3, 2018 (83 FR
31186).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 29, 2019.
No significant hazards consideration comments received: No.
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station,
Salem County, New Jersey
Date of amendment request: April 13, 2018, as supplemented by two
letters dated October 17, 2018.
Brief description of amendment: The amendment revised Hope Creek
Generating Station Technical Specification 3.8.3.1, ``Distribution--
Operating,'' to increase the alternating current inverters allowed
outage time from 24 hours to 7 days. The change was based on
application of the Hope Creek Generating Station probabilistic risk
assessment in support of a risk-informed extension and on additional
considerations and compensatory actions.
Date of issuance: March 27, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days of the date of issuance.
Amendment No.: 215. A publicly-available version is in ADAMS under
Accession No. ML19065A156; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-57: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: June 19, 2018 (83 FR
28462). Two supplemental letters dated October 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 amendment is contained
in a Safety Evaluation dated March 27, 2019.
No significant hazards consideration comments received: No.
Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296,
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Limestone County,
Alabama
Date of amendment request: October 18, 2018, as supplemented by
letters dated February 13, 2019, and March 8, 2019.
Brief description of amendments: The amendments revised the Renewed
Facility Operating Licenses by changing license conditions associated
with the fire protection program controlled by 10 CFR 50.48(c),
``National Fire Protection Association Standard NFPA 805.'' The amended
license conditions incorporate changes made to Table S-2, ``Plant
Modifications Committed,'' in Tennessee Valley Authority letter dated
October 18, 2018, as supplemented by letters dated February 13, 2019,
and March 8, 2019, which describes modifications necessary to
transition into full compliance with 10 CFR 50.48(c).
Date of issuance: April 2, 2019.
Effective date: As of the date of issuance and shall be implemented
immediately.
Amendment Nos.: 307 (Unit 1), 330, (Unit 2), and 290 (Unit 3). A
publicly-available version is in ADAMS under Accession No. ML19037A137;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68:
The amendments revised the Renewed Facility Operating Licenses.
Date of initial notice in Federal Register: December 18, 2018 (83
FR 64897). The supplemental letters dated February 13, 2019, and March
8, 2019, 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 April 2, 2019.
No significant hazards consideration comments received: No.
Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek
Generating Station, Unit 1, Coffey County, Kansas
Date of amendment request: May 9, 2018, as supplemented by letter
dated November 19, 2018.
Brief description of amendment: The amendment revised the Wolf
Creek Generating Station Radiological Emergency Response Plan to (1)
reduce the number of required emergency response organization
positions, (2) standardize activation times for the technical support
center to 75 minutes, (3) replace the current full-time normal work
hours licensed medical practitioner position with on-shift first aid
responders, and (4) remove reference to performing dose assessment
using containment pressure indication.
Date of issuance: April 1, 2019.
Effective date: As of the date of issuance and shall be implemented
within 180 days from the date of issuance.
Amendment No.: 220. A publicly-available version is in ADAMS under
Accession No. ML19052A546; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-42. The amendment
revised the Wolf Creek Generating Station Radiological Emergency
Response Plan.
Date of initial notice in Federal Register: July 3, 2018 (83 FR
31187). The supplemental letter dated November 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 as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 1, 2019.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 16th day of April, 2019
For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2019-07933 Filed 4-22-19; 8:45 am]
BILLING CODE 7590-01-P